Publications
Our publications are listed below.
Books
- Scopatz, Anthony M., and Kathryn D. Huff. 2015. Effective Computation in Physics: Field Guide to Research with Python. 1st ed. Sebastopol, CA: O’Reilly Media. http://shop.oreilly.com/product/0636920033424.do.
Effective Computation in Physics is a handy guide to the types of problems you run into with computational physics—such as version control, bash scripts, object orientation, large databases, and parallel machines. The authors provide detailed scientific computing motivations, clear and concise tutorials, and references to further information about each of the topics presented.This book fills the existing training gap for students and scientists who conduct physics in a world where simulations have replaced desktop experiments and sophisticated data traversing algorithms have replaced pen and paper analysis.Provides a central source that ties various pieces of computational physics togetherContains coverage of the Python programming language aimed toward physicistsHelps you properly analyze and compellingly visualize your dataIncludes chapters on hot topics like NumPy and HDF5
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Book Chapters
- Huff, Kathryn. 2019. “Chapter One - Economics of Advanced Reactors and Fuel Cycles.” In Storage and Hybridization of Nuclear Energy, edited by Hitesh Bindra, 1st ed., 1:1–20. Cambridge, MA, United States: Science & Technology Books Elsevier, Inc. https://doi.org/10.1016/B978-0-12-813975-2.00001-6.
Many dynamic factors influence nuclear reactor and fuel cycle economics. Costs drive the equation, but policies affecting electricity pricing also influence nuclear power revenues at a fundamental level. In current reactors and their associated fuel cycles, capital, operation, and maintenance costs increasingly dominate the economics of nuclear power. Advanced reactor designs and fuel cycle choices can impact these costs both positively and negatively. While fuel cycle advancements also impact fuel costs, this component has a relatively small impact on the overall cost of nuclear electricity production, particularly in comparison to capital costs. If advanced reactors can offer very high-temperature heat appropriate for industrial processing, natively couple with storage technologies, or can otherwise acheive load following behavior, then they may become more financially feasible than the current fleet.
@incollection{huff_chapter_2019, address = {Cambridge, MA, United States}, edition = {1}, title = {Chapter {One} - {Economics} of {Advanced} {Reactors} and {Fuel} {Cycles}}, volume = {1}, isbn = {978-0-12-813975-2}, url = {http://www.sciencedirect.com/science/article/pii/B9780128139752000016}, booktitle = {Storage and {Hybridization} of {Nuclear} {Energy}}, publisher = {Science \& Technology Books Elsevier, Inc.}, author = {Huff, Kathryn}, editor = {Bindra, Hitesh}, month = jan, year = {2019}, doi = {10.1016/B978-0-12-813975-2.00001-6}, keywords = {Economics, Levelized cost of electricity, Reprocessing, Enrichment, Advanced nuclear fuel cycles, Advanced nuclear reactors, Conversion, Fuel cycles, Fuel fabrication, Milling, Mining, Waste management}, pages = {1--20}, file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/5KJ27BJ8/Huff - 2019 - Chapter One - Economics of Advanced Reactors and F.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/N84EB2DY/B9780128139752000016.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/N6A4JEIS/B9780128139752000016.html:text/html;Huff - 2018 - Economics of Advanced Reactors and Fuel Cycles (In.pdf:/Users/huff/Zotero/storage/A82V2LSU/Huff - 2018 - Economics of Advanced Reactors and Fuel Cycles (In.pdf:application/pdf} } - ———. 2017. “Lessons Learned.” In The Practice of Reproducible Research, edited by Justin Kitzes, Fatma Imamoglu, and Daniel Turek, 1st ed. Vol. 1. University of California, Berkeley: University of California Press.
The Practice of Reproducible Research presents concrete examples of how researchers in the data-intensive sciences are working to improve the reproducibility of their research projects. In each of the thirty-one case studies in this volume, the author or team describes the workflow that they used to complete a real-world research project. Authors highlight how they utilized particular tools, ideas, and practices to support reproducibility, emphasizing the very practical how, rather than the why or what, of conducting reproducible research. Part 1 provides an accessible introduction to reproducible research, a basic reproducible research project template, and a synthesis of lessons learned from across the thirty-one case studies. Parts 2 and 3 focus on the case studies themselves. The Practice of Reproducible Research is an invaluable resource for students and researchers who wish to better understand the practice of data-intensive sciences and learn how to make their own research more reproducible.
@incollection{huff_lessons_2017, address = {University of California, Berkeley}, edition = {1}, title = {Lessons {Learned}}, volume = {1}, booktitle = {The {Practice} of {Reproducible} {Research}}, publisher = {University of California Press}, author = {Huff, Kathryn}, editor = {Kitzes, Justin and Imamoglu, Fatma and Turek, Daniel}, year = {2017} } - ———. 2017. “Case Study: Cyclus Project.” In The Practice of Reproducible Research, edited by Justin Kitzes, Fatma Imamoglu, and Daniel Turek, 1st ed. Vol. 1. University of California, Berkeley: University of California Press.
The Practice of Reproducible Research presents concrete examples of how researchers in the data-intensive sciences are working to improve the reproducibility of their research projects. In each of the thirty-one case studies in this volume, the author or team describes the workflow that they used to complete a real-world research project. Authors highlight how they utilized particular tools, ideas, and practices to support reproducibility, emphasizing the very practical how, rather than the why or what, of conducting reproducible research. Part 1 provides an accessible introduction to reproducible research, a basic reproducible research project template, and a synthesis of lessons learned from across the thirty-one case studies. Parts 2 and 3 focus on the case studies themselves. The Practice of Reproducible Research is an invaluable resource for students and researchers who wish to better understand the practice of data-intensive sciences and learn how to make their own research more reproducible.
@incollection{huff_case_2017, address = {University of California, Berkeley}, edition = {1}, title = {Case {Study}: {Cyclus} {Project}}, volume = {1}, booktitle = {The {Practice} of {Reproducible} {Research}}, publisher = {University of California Press}, author = {Huff, Kathryn}, editor = {Kitzes, Justin and Imamoglu, Fatma and Turek, Daniel}, year = {2017} }
Journal Articles
- Bachmann, Amanda M., Roberto Fairhurst-Agosta, Zoë Richter, Nathan Ryan, and Madicken Munk. 2021. “Enrichment Dynamics for Advanced Reactor HALEU Support.” EPJ Nuclear Sciences & Technologies 7: 22. https://doi.org/10.1051/epjn/2021021.
Transitioning to High Assay Low Enriched Uranium-fueled reactors will alter the material requirements of the current nuclear fuel cycle, in terms of the mass of enriched uranium and Separative Work Unit capacity. This work simulates multiple fuel cycle scenarios using Cyclus to compare how the type of the advanced reactor deployed and the energy growth demand affect the material requirements of the transition to High Assay Low Enriched Uranium-fueled reactors. Fuel cycle scenarios considered include the current fleet of Light Water Reactors in the U.S. as well as a no-growth and a 1% growth transition to either the Ultra Safe Nuclear Corporation Micro Modular Reactor or the X-energy Xe-100 reactor from the current fleet of U.S. Light Water Reactors. This work explored parameters of interest including the number of advanced reactors deployed, the mass of enriched uranium sent to the reactors, and the Separative Work Unit capacity required to enrich natural uranium for the reactors. Deploying Micro Modular Reactors requires a higher average mass and Separative Work Unit capacity than deploying Xe-100 reactors, and a lower enriched uranium mass and a higher Separative Work Unity capacity than required to fuel Light Water Reactors before the transition. Fueling Xe-100 reactors requires less enriched uranium and Separative Work Unit capacity than fueling Light Water Reactors before the transition.
@article{bachmann_enrichment_2021, title = {Enrichment dynamics for advanced reactor {HALEU} support}, volume = {7}, copyright = {© A. M. Bachmann et al., Published by EDP Sciences, 2021}, issn = {2491-9292}, url = {https://www.epj-n.org/articles/epjn/abs/2021/01/epjn210024/epjn210024.html}, doi = {10.1051/epjn/2021021}, language = {en}, urldate = {2021-12-02}, journal = {EPJ Nuclear Sciences \& Technologies}, author = {Bachmann, Amanda M. and Fairhurst-Agosta, Roberto and Richter, Zoë and Ryan, Nathan and Munk, Madicken}, year = {2021}, note = {Publisher: EDP Sciences}, pages = {22} } - Chee, Gwendolyn J., Roberto E. Fairhurst Agosta, Jin Whan Bae, Robert R. Flanagan, Anthony M. Scopatz, and Kathryn D. Huff. 2020. “Demand Driven Deployment Capabilities in Cyclus, a Fuel Cycle Simulator.” Nuclear Technology.
The present United States’ nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identified four nuclear fuel cycle options, which make nuclear energy technology more desirable. Successfully analyzing the transitions from the current fuel cycle to these promising fuel cycles requires a nuclear fuel cycle simulator that can predictively and automatically deploy fuel cycle facilities to meet user-defined power demand. This work developed the d3ploy capability in Cyclus, a nuclear fuel cycle simulator, to automatically deploy fuel cycle facilities to meet user-defined power demand. User-controlled capabilities such as supply buffers, facility preferences, prediction algorithms, and installed capacity deployment were introduced to give users tools to minimize power undersupply in a transition scenario simulation. We demonstrate d3ploy’s capability to predict future commodities’ supply and demand, and automatically deploy fuel cycle facilities to meet the predicted demand. We use d3ploy to set up transition scenarios for promising nuclear fuel cycle options.
@article{chee_demand_2020, title = {Demand {Driven} {Deployment} {Capabilities} in {Cyclus}, a {Fuel} {Cycle} {Simulator}}, journal = {Nuclear Technology}, author = {Chee, Gwendolyn J. and Agosta, Roberto E. Fairhurst and Bae, Jin Whan and Flanagan, Robert R. and Scopatz, Anthony M. and Huff, Kathryn D.}, year = {2020}, file = {Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:/Users/huff/Zotero/storage/WK7485EH/Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:application/pdf} } - Bae, Jin Whan, Andrei Rykhlevskii, Gwendolyn Chee, and Kathryn D. Huff. 2020. “Deep Learning Approach to Nuclear Fuel Transmutation in a Fuel Cycle Simulator.” Annals of Nuclear Energy 139 (May): 107230. https://doi.org/10.1016/j.anucene.2019.107230.
We trained a neural network model to predict Pressurized Water Reactor (PWR) Used Nuclear Fuel (UNF) composition given initial enrichment and burnup. This quick, flexible, medium-fidelity method to estimate depleted PWR fuel assembly compositions is used to model scenarios in which the PWR fuel burnup and enrichment vary over time. The Used Nuclear Fuel Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) Unified Database (UDB) provided a ground truth on which the model trained. We validated the model by comparing the U.S. UNF inventory profile predicted by the model with the UDB UNF inventory profile. The neural network yields less than 1% error for UNF inventory decay heat and activity and less than 2% error for major isotopic inventory. The neural network model takes 0.27 s for 100 predictions, compared to 118 s for 100 Oak Ridge Isotope GENeration (ORIGEN) calculations. We also implemented this model into Cyclus, an agent-based Nuclear Fuel Cycle (NFC) simulator, to perform rapid, medium-fidelity PWR depletion calculations. This model also allows discharge of batches with assemblies of varying burnup. Since the original private data cannot be retrieved from the model, this trained model can provide open-source depletion capabilities to NFC simulators. We show that training an artificial neural network with a dataset from a complex fuel depletion model can provide rapid, medium-fidelity depletion capabilities to large-scale fuel cycle simulations.
@article{bae_deep_2020, title = {Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator}, volume = {139}, issn = {0306-4549}, url = {http://www.sciencedirect.com/science/article/pii/S0306454919307406}, doi = {10.1016/j.anucene.2019.107230}, language = {en}, urldate = {2020-01-07}, journal = {Annals of Nuclear Energy}, author = {Bae, Jin Whan and Rykhlevskii, Andrei and Chee, Gwendolyn and Huff, Kathryn D.}, month = may, year = {2020}, note = {github.com/jbae11/depletion\_rom}, keywords = {Simulation, Depletion, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Molten salt breeder reactor, Molten salt reactor, Online reprocessing, Python, Salt treatment, Artificial neural network, Machine learning, Spent nuclear fuel}, pages = {107230}, file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/U7IJI82D/S0306454919307406.html:text/html;Bae et al. - 2020 - Deep learning approach to nuclear fuel transmutati.pdf:/Users/huff/Zotero/storage/63AWUGKG/Bae et al. - 2020 - Deep learning approach to nuclear fuel transmutati.pdf:application/pdf} } - Ashraf, O., Andrei Rykhlevskii, G.V. Tikhomirov, and Kathryn D. Huff. 2020. “Whole Core Analysis of the Single-Fluid Double-Zone Thorium Molten Salt Reactor (SD-TMSR).” Annals of Nuclear Energy, 107115, 137 (March): 107115. https://doi.org/https://doi.org/10.1016/j.anucene.2019.107115.
The SD-TMSR (2,250 MWth) is a Single-fluid Double-zone Thorium-based Molten Salt Reactor. The active core of the SD-TMSR is divided into the inner zone (486 fuel tubes) and the outer zone (522 fuel tubes) to improve the Th-U3 breeding performance. This work adopted the SERPENT-2 Monte Carlo code to analyze the whole core model of the SD-TMSR. Built-in SERPENT-2 capabilities simulated online reprocessing and refueling and calculated the multiplication factor and Breeding Ratio (BR). We found that the molten salt Temperature Coefficient of Reactivity (\alphaT) was negative for initial and equilibrium states. This study investigated the variation of the multiplication factor, BR, and build-up of important nuclides in the core as a function of burnup. Under online reprocessing and refueling, we studied the variation of the reactivity during 60 years of reactor operation. Additionally, the neutron spectrum shift during the reactor operation was calculated. Finally, these simulations determined the appropriate 232Th and 233U feed rates for maintaining criticality and enabled analysis of the overall SD-TMSR fuel cycle performance.
@article{ASHRAF2019107115, series = {107115}, title = {Whole core analysis of the single-fluid double-zone thorium molten salt reactor ({SD}-{TMSR})}, volume = {137}, issn = {0306-4549}, url = {http://www.sciencedirect.com/science/article/pii/S0306454919306255}, doi = {https://doi.org/10.1016/j.anucene.2019.107115}, language = {en}, journal = {Annals of Nuclear Energy}, author = {Ashraf, O. and Rykhlevskii, Andrei and Tikhomirov, G.V. and Huff, Kathryn D.}, month = mar, year = {2020}, keywords = {Burnup, Online reprocessing, MSR, Thorium fuel cycle, Breeding reactor, Monte carlo code}, pages = {107115}, file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/IUEQ9KGP/Ashraf et al. - 2019 - Whole core analysis of the single-fluid double-zon.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/X8N4UACM/S0306454919306255.html:text/html} } - Kamuda, Mark, Jifu Zhao, and Kathryn Huff. 2020. “A Comparison of Machine Learning Methods for Automated Gamma-Ray Spectroscopy.” Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Symposium on Radiation Measurements and Applications XVII, 954 (February): 161385. https://doi.org/10.1016/j.nima.2018.10.063.
Pattern recognition algorithms such as artificial neural networks (NNs) and convolution neural networks (CNNs) are prime candidates to perform automated gamma-ray spectroscopy. The way these models train and operate mimic how trained spectroscopists identify spectra. These models have shown promise in identifying gamma-ray spectra with large calibration drift and unknown background radiation fields. In this work, two algorithms for mixtures of radioisotopes based on NN and CNN are presented and evaluated.
@article{kamuda_comparison_2020, series = {Symposium on {Radiation} {Measurements} and {Applications} {XVII}}, title = {A comparison of machine learning methods for automated gamma-ray spectroscopy}, volume = {954}, issn = {0168-9002}, url = {http://www.sciencedirect.com/science/article/pii/S0168900218313779}, doi = {10.1016/j.nima.2018.10.063}, language = {en}, urldate = {2020-01-28}, journal = {Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment}, author = {Kamuda, Mark and Zhao, Jifu and Huff, Kathryn}, month = feb, year = {2020}, keywords = {Automated isotope identification, Gamma-ray spectroscopy, Neural networks}, pages = {161385}, file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/F5ALG4UY/Kamuda et al. - 2018 - A comparison of machine learning methods for autom.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/PG4A68CJ/S0168900218313779.html:text/html;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/RQ2N9TKJ/Kamuda et al. - 2020 - A comparison of machine learning methods for autom.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/BD2NFXV9/S0168900218313779.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/MZ2HLMXB/S0168900218313779.html:text/html;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/NJB6SVXR/Kamuda et al. - 2020 - A comparison of machine learning methods for autom.pdf:application/pdf} } - Miernicki, Elizabeth A., Alexander L. Heald, Kathryn D. Huff, Caleb S. Brooks, and Andrew J. Margenot. 2020. “Nuclear Waste Heat Use in Agriculture: History and Opportunities in the United States.” Journal of Cleaner Production 267 (September): 121918. https://doi.org/10.1016/j.jclepro.2020.121918.
Nuclear power plants (NPPs) produce a large amount of waste heat (WH) that has generally been perceived and regulated as an environmental liability. Given the abundance of WH from NPPs and the ubiquity of generally low-grade heat requirements of agricultural operations, from production to post-harvest, there is remarkable potential to harness NPP WH for agricultural uses with mutual economic advantages to NPPs and agricultural sectors. Taking advantage of this WH resource may improve the financial outlook of both the partnered power plants and agricultural businesses by providing an additional revenue stream, decreased heating costs, and a reduced carbon footprint. This review summarizes and interprets the historical discourse and research on agricultural applications of NPP WH in the U.S., and synthesizes technical constraints, unknowns, and opportunities for realizing the benefits of WH derived from the nuclear energy sector for agricultural value chains. Previous applications of WH in the agricultural industry demonstrate that this is a viable option to the benefit of the parties involved under the right conditions, but relatively little has been done to further this technology in the U.S. in recent years or explore novel applications. A revival of interest in this technology may be warranted given the current outlook for NPPs in the U.S. and a general interest in reducing the environmental impact of agriculture.
@article{miernicki_nuclear_2020, title = {Nuclear waste heat use in agriculture: {History} and opportunities in the {United} {States}}, volume = {267}, issn = {0959-6526}, shorttitle = {Nuclear waste heat use in agriculture}, url = {http://www.sciencedirect.com/science/article/pii/S095965262031965X}, doi = {10.1016/j.jclepro.2020.121918}, language = {en}, urldate = {2020-06-03}, journal = {Journal of Cleaner Production}, author = {Miernicki, Elizabeth A. and Heald, Alexander L. and Huff, Kathryn D. and Brooks, Caleb S. and Margenot, Andrew J.}, month = sep, year = {2020}, pages = {121918}, file = {Elizabeth A. Miernicki et al. - 2019 - Nuclear waste heat use in agriculture history and.pdf:/Users/huff/Zotero/storage/ABSAF3SA/Elizabeth A. Miernicki et al. - 2019 - Nuclear waste heat use in agriculture history and.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/ETHXEJLI/S095965262031965X.html:text/html;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/A89NY9G3/Miernicki et al. - 2020 - Nuclear waste heat use in agriculture History and.pdf:application/pdf} } - Bae, Jin Whan, Clifford E. Singer, and Kathryn D. Huff. 2019. “Synergistic Spent Nuclear Fuel Dynamics within the European Union.” Progress in Nuclear Energy 114 (July): 1–12. https://doi.org/10.1016/j.pnucene.2019.02.001.
The French 2012–2015 Commission Nationale d’Evaluation Reports emphasize preparation for a transition from Light Water Reactors (LWRs) to Sodium-Cooled Fast Reactors (SFRs). We used the Cyclus nuclear fuel cycle simulator to explore the feasibility of enabling a French transition to an SFR fleet by using Used Nuclear Fuel (UNF) from other European Union (EU) nations. A Cyclus simulation captured nuclear power deployment in the EU from 1970 to 2160. In this simulation, France begins its planned transition to SFRs as existing LWRs are decommissioned. These SFRs are fueled with UNF accumulated by other EU nations and reprocessed in France. The impact of reactor lifetime extensions and SFR breeding ratios on time-to-transition were investigated with additional simulations. These simulations demonstrate that France can avoid deployment of additional LWRs by accepting UNF from other EU nations, that lifetime extensions delay time-to-transition, and improved breeding ratios are not particularly impactful.
@article{bae_synergistic_2019, title = {Synergistic spent nuclear fuel dynamics within the {European} {Union}}, volume = {114}, issn = {0149-1970}, url = {http://www.sciencedirect.com/science/article/pii/S014919701930037X}, doi = {10.1016/j.pnucene.2019.02.001}, urldate = {2019-04-15}, journal = {Progress in Nuclear Energy}, author = {Bae, Jin Whan and Singer, Clifford E. and Huff, Kathryn D.}, month = jul, year = {2019}, keywords = {Simulation, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Transition, Spent nuclear fuel, Agent-based, European union}, pages = {1--12}, file = {Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:/Users/huff/Zotero/storage/3QBIMRIH/Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/FUTLQJAP/Bae et al. - 2019 - Synergistic spent nuclear fuel dynamics within the.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/E9FXRY45/S014919701930037X.html:text/html} } - Rykhlevskii, Andrei, Jin Whan Bae, and Kathryn D. Huff. 2019. “Modeling and Simulation of Online Reprocessing in the Thorium-Fueled Molten Salt Breeder Reactor.” Annals of Nuclear Energy 128 (June): 366–79. https://doi.org/10.1016/j.anucene.2019.01.030.
In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. To further develop these MSR concepts, researchers need simulation tools for analyzing liquid-fueled MSR depletion and fuel processing. However, most contemporary nuclear reactor physics software is unable to perform high-fidelity full-core depletion calculations for a reactor design with online reprocessing. This paper introduces a Python package, SaltProc, which couples with the Monte Carlo code, SERPENT2 to simulate MSR online reprocessing by modeling the changing isotopic composition of MSR fuel salt. This work demonstrates SaltProc capabilities for a full-core, high-fidelity model of the commercial Molten Salt Breeder Reactor (MSBR) concept and verifies these results to results in the literature from independent, lower-fidelity analyses.
@article{rykhlevskii_modeling_2019, title = {Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor}, volume = {128}, issn = {0306-4549}, url = {http://www.sciencedirect.com/science/article/pii/S0306454919300350}, doi = {10.1016/j.anucene.2019.01.030}, urldate = {2019-01-25}, journal = {Annals of Nuclear Energy}, author = {Rykhlevskii, Andrei and Bae, Jin Whan and Huff, Kathryn D.}, month = jun, year = {2019}, keywords = {Simulation, Depletion, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Molten salt breeder reactor, Molten salt reactor, Online reprocessing, Python, Salt treatment}, pages = {366--379}, file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/W5RDKFMS/S0306454919300350.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/P6PJ667C/S0306454919300350.html:text/html;Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:/Users/huff/Zotero/storage/IQPHC25M/Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:application/pdf} } - Bae, Jin Whan, Joshua L. Peterson-Droogh, and Kathryn D. Huff. 2019. “Standardized Verification of the Cyclus Fuel Cycle Simulator.” Annals of Nuclear Energy 128 (June): 288–91. https://doi.org/10.1016/j.anucene.2019.01.014.
Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of Cyclus, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, Cyclus demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the Cycamore reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.
@article{bae_standardized_2019, title = {Standardized verification of the {Cyclus} fuel cycle simulator}, volume = {128}, issn = {0306-4549}, url = {http://www.sciencedirect.com/science/article/pii/S0306454919300179}, doi = {10.1016/j.anucene.2019.01.014}, urldate = {2019-01-25}, journal = {Annals of Nuclear Energy}, author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.}, month = jun, year = {2019}, keywords = {Simulation, Verification, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, C}, pages = {288--291}, file = {Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:/Users/huff/Zotero/storage/T6Q5G2AW/Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/UXQWH3GA/Bae et al. - 2019 - Standardized verification of the Cyclus fuel cycle.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/WFFQBL3B/S0306454919300179.html:text/html} } - Lindsay, Alexander, Gavin Ridley, Andrei Rykhlevskii, and Kathryn Huff. 2018. “Introduction to Moltres: An Application for Simulation of Molten Salt Reactors.” Annals of Nuclear Energy 114 (April): 530–40. https://doi.org/10.1016/j.anucene.2017.12.025.
Moltres is a new physics application for modeling coupled physics in fluid-fuelled, molten salt reactors. This paper describes its neutronics model, thermal hydraulics model, and their coupling in the MOOSE framework. Neutron and precursor equations are implemented using an action system that allows use of an arbitrary number of groups with no change in the input card. Results for many-channel configurations in 2D-axisymmetric and 3D coordinates are presented and compared against other coupled models as well as the Molten Salt Reactor Experiment.
@article{lindsay_introduction_2018, title = {Introduction to {Moltres}: {An} application for simulation of {Molten} {Salt} {Reactors}}, volume = {114}, issn = {0306-4549}, shorttitle = {Introduction to {Moltres}}, url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454917304760}, doi = {10.1016/j.anucene.2017.12.025}, language = {en}, urldate = {2018-01-08}, journal = {Annals of Nuclear Energy}, author = {Lindsay, Alexander and Ridley, Gavin and Rykhlevskii, Andrei and Huff, Kathryn}, month = apr, year = {2018}, keywords = {Simulation, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics}, pages = {530--540}, file = {Moltres.pdf:/Users/huff/Zotero/storage/4XDXRICB/Moltres.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/E2T9U5IX/Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/3DT9TEY3/S0306454917304760.html:text/html;Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:/Users/huff/Zotero/storage/RCWUNGTP/Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf} } - Smith, Arfon M., Kyle E. Niemeyer, Daniel S. Katz, Lorena A. Barba, George Githinji, Melissa Gymrek, Kathryn D. Huff, et al. 2018. “Journal of Open Source Software (JOSS): Design and First-Year Review.” PeerJ Computer Science 4 (February): e147. https://doi.org/10.7717/peerj-cs.147.
This article describes the motivation, design, and progress of the Journal of Open Source Software (JOSS). JOSS is a free and open-access journal that publishes articles describing research software. It has the dual goals of improving the quality of the software submitted and providing a mechanism for research software developers to receive credit. While designed to work within the current merit system of science, JOSS addresses the dearth of rewards for key contributions to science made in the form of software. JOSS publishes articles that encapsulate scholarship contained in the software itself, and its rigorous peer review targets the software components: functionality, documentation, tests, continuous integration, and the license. A JOSS article contains an abstract describing the purpose and functionality of the software, references, and a link to the software archive. The article is the entry point of a JOSS submission, which encompasses the full set of software artifacts. Submission and review proceed in the open, on GitHub. Editors, reviewers, and authors work collaboratively and openly. Unlike other journals, JOSS does not reject articles requiring major revision; while not yet accepted, articles remain visible and under review until the authors make adequate changes (or withdraw, if unable to meet requirements). Once an article is accepted, JOSS gives it a digital object identifier (DOI), deposits its metadata in Crossref, and the article can begin collecting citations on indexers like Google Scholar and other services. Authors retain copyright of their JOSS article, releasing it under a Creative Commons Attribution 4.0 International License. In its first year, starting in May 2016, JOSS published 111 articles, with more than 40 additional articles under review. JOSS is a sponsored project of the nonprofit organization NumFOCUS and is an affiliate of the Open Source Initiative (OSI).
@article{smith_journal_2018, title = {Journal of {Open} {Source} {Software} ({JOSS}): design and first-year review}, volume = {4}, issn = {2376-5992}, shorttitle = {Journal of {Open} {Source} {Software} ({JOSS})}, url = {https://peerj.com/articles/cs-147}, doi = {10.7717/peerj-cs.147}, language = {en}, urldate = {2018-02-19}, journal = {PeerJ Computer Science}, author = {Smith, Arfon M. and Niemeyer, Kyle E. and Katz, Daniel S. and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn D. and Madan, Christopher R. and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy K. and Guimera, Roman Valls and Vanderplas, Jacob T.}, month = feb, year = {2018}, pages = {e147}, file = {Snapshot:/Users/huff/Zotero/storage/T7FU3G6Z/cs-147.html:text/html;Full Text PDF:/Users/huff/Zotero/storage/MCQBTVVB/Smith et al. - 2018 - Journal of Open Source Software (JOSS) design and.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/GNCWWW38/cs-147.html:text/html;Fulltext:/Users/huff/Zotero/storage/SUEMGFP2/cs-147.html:text/html} } - Lindsay, Alexander, and Kathryn Huff. 2018. “Moltres: Finite Element Based Simulation of Molten Salt Reactors.” The Journal of Open Source Software 3 (21): 1–2. https://doi.org/10.21105/joss.00298.
Moltres is a physics application for multiphysics modeling of fluid-fueled molten salt reactors (MSRs) (Lindsay et al. 2018). It couples equations for neutron diffusion, thermal hydraulics, and delayed neutron precursor transport. Neutron diffusion and precursor transport equations are set-up using an action system that allows the user to use an arbitrary number of neutron energy and precursor groups respectively with minimal input changes. Moltres sits on top of the Multi-physics Object-Oriented Simulation Environment (Gaston et al. 2015) and hence uses the finite element method to discretize the governing partial differential equations. In general the resulting system of non-linear algebraic equations is linearized using the Newton-Raphson method and then solved using the Portable, Extensible Toolkit for Scientific Computation (Balay et al. 2017). Assembly of the Jacobian and residual, and the linear solve are parallelized using MPI which allows Moltres to be run in massively parallel environments. Runs on the Blue Waters supercomputer at Illinois have utilized up to 608 cores. Moltres and MOOSE allow use of different basis functions for different system variables. Because of the purely diffusive nature of the neutron diffusion equations, neutron fluxes are typically discretized using continuous first-degree Lagrange polynomials and the degrees of freedom are associated with mesh nodes. The temperature variable may also be discretized with a continuous Lagrange basis, or a discontinuous basis of arbitrary degree monomials may be employed depending on the relative balance of heat convection to conduction. The purely hyperbolic precursor transport is currently discretized using constant monomials, which is equivalent to a first-order finite volume discretization. Moltres supports both segregated (through Picard iteration) and monolithic solutions of the equation system. However, due to the feedback between the power spectrum and temperature dependence of macroscopic cross-sections, monolithic solves have demonstrated superior robustness with segregated techniques often unable to converge to a solution. This result emphasizes the importance of a fully coupled multi-physics framework like the one that Moltres and MOOSE provide and suggests that iteratively coupling codes devoted to single physics (Kópházi, Lathouwers, and Kloosterman 2009) may result in limited flexibility.
@article{lindsay_moltres_2018, title = {Moltres: finite element based simulation of molten salt reactors}, volume = {3}, shorttitle = {Moltres}, url = {https://doi.org/10.21105/joss.00298}, doi = {10.21105/joss.00298}, number = {21}, urldate = {2018-01-08}, journal = {The Journal of Open Source Software}, author = {Lindsay, Alexander and Huff, Kathryn}, month = jan, year = {2018}, pages = {1--2}, file = {Snapshot:/Users/huff/Zotero/storage/E3ARQ46H/joss.html:text/html;Full Text PDF:/Users/huff/Zotero/storage/MJIZZW4P/Lindsay and Huff - 2018 - Moltres finite element based simulation of molten.pdf:application/pdf} } - Huff, Kathryn. 2017. “Rapid Methods for Radionuclide Contaminant Transport in Nuclear Fuel Cycle Simulation.” Advances in Engineering Software 114 (December): 268–81. https://doi.org/10.1016/j.advengsoft.2017.07.006.
Nuclear fuel cycle and nuclear waste disposal decisions are technologically coupled. However, current nuclear fuel cycle simulators lack dynamic repository performance analysis due to the computational burden of high-fidelity hydrolgic contaminant transport models. The Cyder disposal environment and repository module was developed to fill this gap. It implements medium-fidelity hydrologic radionuclide transport models to support assessment appropriate for fuel cycle simulation in the Cyclus fuel cycle simulator. Rapid modeling of hundreds of discrete waste packages in a geologic environment is enabled within this module by a suite of four closed form models for advective, dispersive, coupled, and idealized contaminant transport: a Degradation Rate model, a Mixed Cell model, a Lumped Parameter model, and a 1-D Permeable Porous Medium model. A summary of the Cyder module, its timestepping algorithm, and the mathematical models implemented within it are presented. Additionally, parametric demonstrations simulations performed with Cyder are presented and shown to demonstrate functional agreement with parametric simulations conducted in a standalone hydrologic transport model, the Clay Generic Disposal System Model developed by the Used Fuel Disposition Campaign Department of Energy Office of Nuclear Energy.
@article{huff_rapid_2017, title = {Rapid methods for radionuclide contaminant transport in nuclear fuel cycle simulation}, volume = {114}, issn = {0965-9978}, url = {http://www.sciencedirect.com/science/article/pii/S0965997817302703}, doi = {10.1016/j.advengsoft.2017.07.006}, urldate = {2019-03-03}, journal = {Advances in Engineering Software}, author = {Huff, Kathryn}, month = dec, year = {2017}, note = {https://doi.org/10.1016/j.advengsoft.2017.07.006}, keywords = {Simulation, Nuclear Fuel Cycle, Repository, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Hydrologic contaminant transport, nuclear engineering, simulation}, pages = {268--281}, file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/27XJEXE8/S0965997817302703.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/34UH4PHR/S0965997817302703.html:text/html;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/PMST2RA5/PMST2RA5.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/XR4V3VZV/Huff - Rapid methods for radionuclide contaminant transpo.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/ZETJXGMB/S0965997817302703.html:text/html} } - Allen, Alice, Cecilia Aragon, Christoph Becker, Jeffrey Carver, Andrei Chis, Benoit Combemale, Mike Croucher, et al. 2017. “Engineering Academic Software (Dagstuhl Perspectives Workshop 16252).” Edited by Alice Allen et al. Dagstuhl Manifestos 6 (1): 1–20. https://doi.org/10.4230/DagMan.6.1.1.
Software is often a critical component of scientific research. It can be a component of the academic research methods used to produce research results, or it may itself be an academic research result. Software, however, has rarely been considered to be a citable artifact in its own right. With the advent of open-source software, artifact evaluation committees of conferences, and journals that include source code and running systems as part of the published artifacts, we foresee that software will increasingly be recognized as part of the academic process. The quality and sustainability of this software must be accounted for, both a priori and a posteriori. The Dagstuhl Perspectives Workshop on “Engineering Academic Software” has examined the strengths, weaknesses, risks, and opportunities of academic software engineering. A key outcome of the workshop is this Dagstuhl Manifesto, serving as a roadmap towards future professional software engineering for software-based research instruments and other software produced and used in an academic context. The manifesto is expressed in terms of a series of actionable “pledges” that users and developers of academic research software can take as concrete steps towards improving the environment in which that software is produced.
@article{allen_engineering_2017, title = {Engineering {Academic} {Software} ({Dagstuhl} {Perspectives} {Workshop} 16252)}, volume = {6}, issn = {2193-2433}, url = {http://drops.dagstuhl.de/opus/volltexte/2017/7146}, doi = {10.4230/DagMan.6.1.1}, number = {1}, journal = {Dagstuhl Manifestos}, author = {Allen, Alice and Aragon, Cecilia and Becker, Christoph and Carver, Jeffrey and Chis, Andrei and Combemale, Benoit and Croucher, Mike and Crowston, Kevin and Garijo, Daniel and Gehani, Ashish and Goble, Carole and Haines, Robert and Hirschfeld, Robert and Howison, James and Huff, Kathryn and Jay, Caroline and Katz, Daniel S. and Kirchner, Claude and Kuksenok, Katie and L{\"a}mmel, Ralf and Nierstrasz, Oscar and Turk, Matt and Nieuwpoort, Rob van and Vaughn, Matthew and Vinju, Jurgen J.}, editor = {al, Alice Allen et}, year = {2017}, keywords = {Academic software, Research software, Software citation, Software sustainability}, pages = {1--20}, file = {Full Text PDF:/Users/huff/Zotero/storage/AP6TACTU/Allen et al. - 2017 - Engineering Academic Software (Dagstuhl Perspectiv.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/VCZFTX9V/7146.html:text/html} } - Andreades, Charalampos, Anselmo T. Cisneros, Jae Keun Choi, Alexandre YK Chong, Massimiliano Fratoni, Sea Hong, Lakshana R. Huddar, et al. 2016. “Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant.” Nuclear Technology 195 (3): 222–38. https://doi.org/10.13182/NT16-2.
The University of California, Berkeley (UCB), has developed a preconceptual design for a commercial pebble-bed (PB), fluoride salt–cooled, high-temperature reactor (FHR) (PB-FHR). The baseline design for this Mark-I PB-FHR (Mk1) plant is a 236-MW(thermal) reactor. The Mk1 uses a fluoride salt coolant with solid, coated-particle pebble fuel. The Mk1 design differs from earlier FHR designs because it uses a nuclear air-Brayton combined cycle designed to produce 100 MW(electric) of base-load electricity using a modified General Electric 7FB gas turbine. For peak electricity generation, the Mk1 has the ability to boost power output up to 242 MW(electric) using natural gas co-firing. The Mk1 uses direct heating of the power conversion fluid (air) with the primary coolant salt rather than using an intermediate coolant loop. By combining results from computational neutronics, thermal hydraulics, and pebble dynamics, UCB has developed a detailed design of the annular core and other key functional features. Both an active normal shutdown cooling system and a passive, natural-circulation-driven emergency decay heat removal system are included. Computational models of the FHR-validated using experimental data from the literature and from scaled thermal-hydraulic facilities-have led to a set of design criteria and system requirements for the Mk1 to operate safely and reliably. Three-dimensional, computer-aided-design models derived from the Mk1 design criteria are presented.
@article{andreades_design_2016, title = {Design {Summary} of the {Mark}-{I} {Pebble}-{Bed}, {Fluoride} {Salt}{\textendash}{Cooled}, {High}-{Temperature} {Reactor} {Commercial} {Power} {Plant}}, volume = {195}, issn = {00295450}, url = {http://www.ans.org/pubs/journals/nt/a_38935}, doi = {10.13182/NT16-2}, number = {3}, urldate = {2016-09-09}, journal = {Nuclear Technology}, author = {Andreades, Charalampos and Cisneros, Anselmo T. and Choi, Jae Keun and Chong, Alexandre YK and Fratoni, Massimiliano and Hong, Sea and Huddar, Lakshana R. and Huff, Kathryn D. and Kendrick, James and Krumwiede, David L. and Laufer, Michael and Munk, Madicken and Scarlat, Raluca O. and Wang, Xin and Zwiebaum, Nicolas and Greenspan, Ehud and Peterson, Per}, month = sep, year = {2016}, pages = {222--238}, file = {Snapshot:/Users/huff/Zotero/storage/C3TI9AHZ/a_38935.html:text/html;Snapshot:/Users/huff/Zotero/storage/BQ6TP5U7/a_38935.html:text/html} } - Huff, Kathryn D., Matthew J. Gidden, Robert W. Carlsen, Robert R. Flanagan, Meghan B. McGarry, Arrielle C. Opotowsky, Erich A. Schneider, Anthony M. Scopatz, and Paul P. H. Wilson. 2016. “Fundamental Concepts in the Cyclus Nuclear Fuel Cycle Simulation Framework.” Advances in Engineering Software 94 (April): 46–59. https://doi.org/10.1016/j.advengsoft.2016.01.014.
As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.
@article{huff_fundamental_2016, title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework}, volume = {94}, issn = {0965-9978}, url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229}, doi = {10.1016/j.advengsoft.2016.01.014}, language = {en}, urldate = {2016-02-12}, journal = {Advances in Engineering Software}, author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.}, month = apr, year = {2016}, note = {arXiv: 1509.03604}, keywords = {Simulation, Nuclear fuel cycle, Computer Science - Software Engineering, Computer Science - Mathematical Software, agent based modeling, Computer Science - Computational Engineering, Finance, and Science, Computer Science - Multiagent Systems, D.2.13, D.2.4, I.6.7, I.6.8, Object orientation, Systems analysis, nuclear engineering, simulation, Agent based modeling, Nuclear engineering, and Science, Computer Science - Computational Engineering, Finance}, pages = {46--59}, file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/E7DK64AA/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/JCCZAZB3/S0965997816300229.html:text/html;fundamentals.pdf:/Users/huff/Zotero/storage/C6G4NQJH/fundamentals.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/F9KVM9DZ/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/4FI3T63Q/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/EVBNKXMA/S0965997816300229.html:text/html;fundamentals.pdf:/Users/huff/Zotero/storage/BRJECDWC/fundamentals.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/HXSDS7VW/1509.html:text/html;arXiv.org Snapshot:/Users/huff/Zotero/storage/WQVTXAN2/1509.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/63CHUQ54/login.html:text/html;arXiv.org Snapshot:/Users/huff/Zotero/storage/EVFA3LC6/1509.html:text/html;arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/GN7WIP38/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/275X4LV5/S0965997816300229.html:text/html;Snapshot:/Users/huff/Zotero/storage/9DRDIPZV/S0965997816300229.html:text/html;Fulltext:/Users/huff/Zotero/storage/3IMCACE5/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:/Users/huff/Zotero/storage/FAM6DNLV/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf} } - Wilson, Greg, D. A. Aruliah, C. Titus Brown, Neil P. Chue Hong, Matt Davis, Richard T. Guy, Steven H. D. Haddock, et al. 2014. “Best Practices for Scientific Computing.” PLoS Biol 12 (1): e1001745. https://doi.org/10.1371/journal.pbio.1001745.
We describe a set of best practices for scientific software development, based on research and experience, that will improve scientists’ productivity and the reliability of their software.
@article{wilson_best_2014, title = {Best {Practices} for {Scientific} {Computing}}, volume = {12}, url = {http://dx.doi.org/10.1371/journal.pbio.1001745}, doi = {10.1371/journal.pbio.1001745}, number = {1}, urldate = {2014-09-08}, journal = {PLoS Biol}, author = {Wilson, Greg and Aruliah, D. A. and Brown, C. Titus and Chue Hong, Neil P. and Davis, Matt and Guy, Richard T. and Haddock, Steven H. D. and Huff, Kathryn D. and Mitchell, Ian M. and Plumbley, Mark D. and Waugh, Ben and White, Ethan P. and Wilson, Paul}, month = jan, year = {2014}, keywords = {Science, science, Computer Science - Software Engineering, Computer Science - Mathematical Software, recommendation, software}, pages = {e1001745}, file = {PLoS Snapshot:/Users/huff/Zotero/storage/JWG3964F/infodoi10.1371journal.pbio.html:text/html;PLoS Full Text PDF:/Users/huff/Zotero/storage/JG3XZ3EN/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Full Text PDF:/Users/huff/Zotero/storage/T7PS6IGX/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/GEAQU4PR/Wilson et al. - 2012 - Best Practices for Scientific Computing.html:text/html;1210.0530 PDF:/Users/huff/Zotero/storage/RUGPQ89Z/Wilson et al. - 2012 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Snapshot:/Users/huff/Zotero/storage/GVVR84ZK/infodoi10.1371journal.pbio.html:text/html;PLoS Snapshot:/Users/huff/Zotero/storage/A9HDSJBB/Wilson et al. - 2014 - Best Practices for Scientific Computing.html:text/html;PLoS Snapshot:/Users/huff/Zotero/storage/FXDIXXQ2/Wilson et al. - 2014 - Best Practices for Scientific Computing.html:text/html;PLoS Full Text PDF:/Users/huff/Zotero/storage/NZPICHHU/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Full Text PDF:/Users/huff/Zotero/storage/DRSWE54I/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/TNJ5VZBD/Wilson et al. - 2012 - Best Practices for Scientific Computing.html:text/html;1210.0530 PDF:/Users/huff/Zotero/storage/6BWMN925/Wilson et al. - 2012 - Best Practices for Scientific Computing.pdf:application/pdf} } - Clerc, M. G., P. Cordero, J. Dunstan, Kathryn D. Huff, N. Mujica, D. Risso, and G. Varas. 2008. “Liquid-Solid-like Transition in Quasi-One-Dimensional Driven Granular Media.” Nature Physics 4 (3): 249–54. https://doi.org/10.1038/nphys884.
The theory of non-ideal gases at thermodynamic equilibrium, for instance the van der Waals gas model, has played a central role in our understanding of coexisting phases, as well as the transitions between them. In contrast, the theory fails with granular matter because collisions between the grains dissipate energy, and their macroscopic size renders thermal fluctuations negligible. When a mass of grains is subjected to mechanical vibration, it can make a transition to a fluid state. In this state, granular matter exhibits patterns and instabilities that resemble those of molecular fluids. Here, we report a granular solid–liquid phase transition in a vibrating granular monolayer. Unexpectedly, the transition is mediated by waves and is triggered by a negative compressibility, as for van der Waals phase coexistence, although the system does not satisfy the hypotheses used to understand atomic systems. The dynamic behaviour that we observe—coalescence, coagulation and wave propagation—is common to a wide class of phase transitions. We have combined experimental, numerical and theoretical studies to build a theoretical framework for this transition.
@article{clerc_liquid-solid-like_2008, title = {Liquid-solid-like transition in quasi-one-dimensional driven granular media}, volume = {4}, issn = {1745-2473}, url = {http://dx.doi.org.ezproxy.library.wisc.edu/10.1038/nphys884}, doi = {10.1038/nphys884}, number = {3}, urldate = {2010-09-18}, journal = {Nature Physics}, author = {Clerc, M. G. and Cordero, P. and Dunstan, J. and Huff, Kathryn D. and Mujica, N. and Risso, D. and Varas, G.}, month = mar, year = {2008}, keywords = {KHuff}, pages = {249--254}, file = {Nature Snapshot:/Users/huff/Zotero/storage/BW5WXVHE/nphys884.html:text/html} }
In Progress / Submitted
- Ashraf, O., Andrei Rykhlevskii, G.V. Tikhomirov, and Kathryn D. Huff. 2020. “Preliminary Design of Control Rods in the Single-Fluid Double-Zone Thorium Molten Salt Reactor (SD-TMSR). Part I: Design Development, Material Selection, and Worth Analysis.” Submitted.
@article{ashraf_preliminary_2020, title = {Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor ({SD}-{TMSR}). {Part} {I}: {Design} development, material selection, and worth analysis}, journal = {Submitted}, author = {Ashraf, O. and Rykhlevskii, Andrei and Tikhomirov, G.V. and Huff, Kathryn D.}, year = {2020}, keywords = {Burnup, Online reprocessing, MSR, Thorium fuel cycle, Breeding reactor, Monte carlo code}, file = {Ashraf et al. - 2020 - Preliminary design of control rods in the single-f.pdf:/Users/huff/Zotero/storage/RBGV8RDL/Ashraf et al. - 2020 - Preliminary design of control rods in the single-f.pdf:application/pdf} }
Conference Proceedings
- Bachmann, Amanda M., and Kathryn D. Huff. 2021. “Comparing HALEU Demand Among Advanced Reactor Fuel Cycle Transitions.” In Proceedings of the 2021 ANS Virtual Annual Meeting, 124:134–37. Virtual. https://www.ans.org/pubs/transactions/article-49551/.
@inproceedings{bachmann_comparing_2021, address = {Virtual}, title = {Comparing {HALEU} {Demand} {Among} {Advanced} {Reactor} {Fuel} {Cycle} {Transitions}}, volume = {124}, url = {https://www.ans.org/pubs/transactions/article-49551/}, urldate = {2021-06-29}, booktitle = {Proceedings of the 2021 {ANS} {Virtual} {Annual} {Meeting}}, author = {Bachmann, Amanda M. and Huff, Kathryn D.}, month = jun, year = {2021}, pages = {134--137} } - ———. 2021. “Enriched Uranium Supply Requirements for the Transition to Advanced Reactors.” In Proceedings of the American Nuclear Society 2021 National Student Conference, Virtual: American Nuclear Society.
Current nuclear reactors employed in the United States use Low Enriched Uranium (LEU)fuel enriched to no more than 5%. New reactor designs, such as the Ultra Safe Nuclear Cor-poration (USNC) Micro Modular Reactor (MMR)TM, will require High Assay Low EnrichedUranium (HALEU) fuel enriched between 5-20%. To meet HALEU fuel requirements, theU.S. Department of Energy is considering recovery and downblending of High Enriched Ura-nium (HEU) fuel and enriching natural uranium to the required levels [1], with each of thesemethods containing their own limitations. Recovery and downblending of HEU fuel is lim-ited by the existing physical supply of HEU as well as downblending capacity. Enrichment ofnatural uranium is limited by centrifuge capacity, in terms of Separative Work Unit (SWU).This work aims to quantify the resource requirements of the current U.S. reactor fleetand of the transition to different reactors that require HALEU fuel. Fuel cycle simulationsare completed usingCyclus, an agent-based fuel cycle simulator [2]. Transition scenariosconsidered include use of the USNC MMRTMand the X-energy Xe-100TMreactor, which bothrequire HALEU fuel. Resource requirements of interest include enriched fuel requirementsat each enrichment level, HEU required to meet HALEU demand, and natural uranium andSWU required to meet HALEU demand. These metrics will inform the material requirementsand provide insight into the best method to meet fuel requirements for these transitionscenarios
@inproceedings{bachmann_enriched_2021, address = {Virtual}, title = {Enriched {Uranium} {Supply} {Requirements} for the {Transition} to {Advanced} {Reactors}}, language = {English}, booktitle = {Proceedings of the {American} {Nuclear} {Society} 2021 {National} {Student} {Conference},}, publisher = {American Nuclear Society}, author = {Bachmann, Amanda M. and Huff, Kathryn D.}, month = apr, year = {2021} } - Dotson, Samuel G., and Kathryn D. Huff. 2020. “Optimal Sizing of a Micro-Reactor for Embedded Grid Systems.” In Transactions of the American Nuclear Society Student Conference. Raleigh, N.C.: American Nuclear Society.
There has been significant work recently to develop en- ergy system concepts that incorporate a mixture of nuclear energy, variable renewable energy (VRE) and energy storage techniques. These systems are often referred to as nuclear hy- brid energy systems (NHES) and are generally robust, reliable, economically appealing, and have low to zero greenhouse gas (GHG) emissions [1, 2, 3, 4]. In 2015, the University of Illi- nois at Urbana-Champaign (UIUC) made a commitment to reach carbon neutrality by 2050 in the Illinois Climate Ac- tion Plan (iCAP) [5]. This plan identified nuclear energy as a potential contributor to this goal. In this work we use the RAVEN framework to find the optimal size for a micro-reactor that would minimize the levelized cost of electricity (LCOE) for the UIUC embedded grid. The greatest source economic variability is contained in the capital costs of a micro-reactor. Thus we examine both scenarios where the reactor is provided at no cost to the university and purchased at full price.
@inproceedings{dotson_optimal_2020, address = {Raleigh, N.C.}, title = {Optimal {Sizing} of a {Micro}-{Reactor} for {Embedded} {Grid} {Systems}}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Conference}}, publisher = {American Nuclear Society}, author = {Dotson, Samuel G. and Huff, Kathryn D.}, month = mar, year = {2020}, file = {Dotson and Huff - 2020 - Optimal Sizing of a Micro-Reactor for Embedded Gri.pdf:/Users/huff/Zotero/storage/XL93Z3I5/Dotson and Huff - 2020 - Optimal Sizing of a Micro-Reactor for Embedded Gri.pdf:application/pdf} } - ———. 2020. “Optimal Sizing of a Micro-Reactor for Embedded Grid Systems.” In Transactions of the American Nuclear Society Annual Meeting, 3. Phoenix, AZ: American Nuclear Society.
There has been significant work recently to develop en- ergy system concepts that incorporate a mixture of nuclear energy, variable renewable energy (VRE) and energy storage techniques. These systems are often referred to as nuclear hy- brid energy systems (NHES) and are generally robust, reliable, economically appealing, and have low to zero greenhouse gas (GHG) emissions [1, 2, 3, 4]. In 2015, the University of Illi- nois at Urbana-Champaign (UIUC) made a commitment to reach carbon neutrality by 2050 in the Illinois Climate Ac- tion Plan (iCAP) [5]. This plan identified nuclear energy as a potential contributor to this goal. In this work we use the RAVEN framework to find the optimal size for a micro-reactor that would minimize the levelized cost of electricity (LCOE) for the UIUC embedded grid. The greatest source economic variability is contained in the capital costs of a micro-reactor. Thus we examine both scenarios where the reactor is provided at no cost to the university and purchased at full price.
@inproceedings{dotson_optimal_2020-1, address = {Phoenix, AZ}, title = {Optimal {Sizing} of a {Micro}-reactor for {Embedded} {Grid} {Systems}}, language = {en}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}}, publisher = {American Nuclear Society}, author = {Dotson, Samuel G. and Huff, Kathryn D.}, month = jun, year = {2020}, pages = {3}, file = {Dotson and Huff - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:/Users/huff/Zotero/storage/6GA7KQ62/Dotson and Huff - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:application/pdf} } - Fairhurst Agosta, Roberto, Samuel Dotson, and Kathryn Huff. 2020. “Hydrogen Economy in Champaign-Urbana, IL.” In Transactions of the American Nuclear Society Student Conference. Raleigh, NC: American Nuclear Society.
@inproceedings{fairhurst_agosta_hydrogen_2020, address = {Raleigh, NC}, title = {Hydrogen {Economy} in {Champaign}-{Urbana}, {IL}}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Conference}}, publisher = {American Nuclear Society}, author = {Fairhurst Agosta, Roberto and Dotson, Samuel and Huff, Kathryn}, month = mar, year = {2020}, file = {Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:/Users/huff/Zotero/storage/3B4B9NS6/Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:application/pdf} } - ———. 2020. “Hydrogen Economy in Champaign-Urbana, IL.” In Transactions of the American Nuclear Society Annual Meeting. Phoeniz, AZ: American Nuclear Society.
@inproceedings{fairhurst_agosta_hydrogen_2020-1, address = {Phoeniz, AZ}, title = {Hydrogen {Economy} in {Champaign}-{Urbana}, {IL}}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}}, publisher = {American Nuclear Society}, author = {Fairhurst Agosta, Roberto and Dotson, Samuel and Huff, Kathryn}, month = jun, year = {2020}, file = {Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:/Users/huff/Zotero/storage/QR3RJ9Y9/Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:application/pdf} } - Chee, Gwendolyn J. 2019. “Demand Driven Deployment Capabilities in Cyclus.” In Proceedings of the Technical Workshop on Fuel Cycle Simulation 2019. Champaign, IL. arfc.github.io/twofcs19.
For many fuel cycle simulators, it is currently up to the user to define a deployment scheme of supporting facilities or provide an infinite inventory of commodities to ensure that there is no gap in the supply chain. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand responsive deployment decisions into the dynamics of the simulation logic. In this work, we develop demand driven deployment capabilities in Cyclus, d3ploy. User-controlled capabilities such as supply/ capacity buffers, constraint deployment, prediction algorithms, and installed capacity deployment were introduced in d3ploy to give a user the tools to minimize commodity undersupply in a simulation. We demonstrate d3ploy’s capability to automatically deploy fuel cycle facilities to meet various types of user-defined power demands: constant, linearly increasing, and sinusoidal.
@inproceedings{chee_demand_2019, address = {Champaign, IL}, title = {Demand {Driven} {Deployment} {Capabilities} in {Cyclus}}, url = {arfc.github.io/twofcs19}, booktitle = {Proceedings of the {Technical} {Workshop} on {Fuel} {Cycle} {Simulation} 2019}, author = {Chee, Gwendolyn J.}, collaborator = {Flanagan, Robert R. and Huff, Kathryn D}, month = jun, year = {2019}, file = {2019-chee-twofcs-pres.pdf:/Users/huff/Zotero/storage/V95BLIN6/2019-chee-twofcs-pres.pdf:application/pdf;2019-chee-twofcs-pres.pptx:/Users/huff/Zotero/storage/N49L9PAI/2019-chee-twofcs-pres.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation} } - Huff, Kathryn D. 2019. “Demand Driven Cycamore Archetypes FY16 NEUP Award Summary.” In Presentations in the DOE-NE Systems Analysis and Integration (SA&I) Campaign. Argonne, IL, United States.
@inproceedings{huff_demand_2019, address = {Argonne, IL, United States}, title = {Demand {Driven} {Cycamore} {Archetypes} {FY16} {NEUP} {Award} {Summary}}, booktitle = {Presentations in the {DOE}-{NE} {Systems} {Analysis} and {Integration} ({SA}\&{I}) {Campaign}}, author = {Huff, Kathryn D.}, month = sep, year = {2019} } - Chee, Gwendolyn, Jin Whan Bae, Kathryn D. Huff, Robert R. Flanagan, and Roberto Fairhurst. 2019. “Demonstration of Demand-Driven Deployment Capabilities in Cyclus.” In Proceedings of Global/Top Fuel 2019. Seattle, WA, United States: American Nuclear Society.
@inproceedings{chee_demonstration_2019, address = {Seattle, WA, United States}, title = {Demonstration of {Demand}-{Driven} {Deployment} {Capabilities} in {Cyclus}}, booktitle = {Proceedings of {Global}/{Top} {Fuel} 2019}, publisher = {American Nuclear Society}, author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D. and Flanagan, Robert R. and Fairhurst, Roberto}, month = sep, year = {2019}, file = {Chee et al. - 2019 - Demonstration of Demand-Driven Deployment Capabili.pdf:/Users/huff/Zotero/storage/DAS8F5HF/Chee et al. - 2019 - Demonstration of Demand-Driven Deployment Capabili.pdf:application/pdf} } - Flanagan, Robert R., Jin Whan Bae, Kathryn D. Huff, Gwendolyn J. Chee, and Roberto Fairhurst. 2019. “Methods for Automated Fuel Cycle Facility Deployment.” In Proceedings of Global/Top Fuel 2019. Seattle, WA, United States: American Nuclear Society.
@inproceedings{flanagan_methods_2019, address = {Seattle, WA, United States}, title = {Methods for {Automated} {Fuel} {Cycle} {Facility} {Deployment}}, booktitle = {Proceedings of {Global}/{Top} {Fuel} 2019}, publisher = {American Nuclear Society}, author = {Flanagan, Robert R. and Bae, Jin Whan and Huff, Kathryn D. and Chee, Gwendolyn J. and Fairhurst, Roberto}, month = sep, year = {2019} } - Chaube, Anshuman, James Stubbins, and Kathryn D. Huff. 2019. “Dynamic Transition Analysis with TIMES.” In I2CNER Annual Symposium. Fukuoka, Japan: Kyushu University.
@inproceedings{chaube_dynamic_2019, address = {Fukuoka, Japan}, title = {Dynamic {Transition} {Analysis} with {TIMES}}, booktitle = {{I2CNER} {Annual} {Symposium}}, publisher = {Kyushu University}, author = {Chaube, Anshuman and Stubbins, James and Huff, Kathryn D.}, month = feb, year = {2019}, note = {(Presentation)} } - Rykhlevskii, Andrei, Benjamin R. Betzler, Andrew Worrall, and Kathryn D. Huff. 2019. “Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs.” In Proceedings of Mathematics and Computation 2019. Portland, OR: American Nuclear Society.
@inproceedings{rykhlevskii_fuel_2019, address = {Portland, OR}, title = {Fuel {Cycle} {Performance} of {Fast} {Spectrum} {Molten} {Salt} {Reactor} {Designs}}, booktitle = {Proceedings of {Mathematics} and {Computation} 2019}, publisher = {American Nuclear Society}, author = {Rykhlevskii, Andrei and Betzler, Benjamin R. and Worrall, Andrew and Huff, Kathryn D.}, month = aug, year = {2019}, file = {Rykhlevskii et al. - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:/Users/huff/Zotero/storage/22VH9KTC/Rykhlevskii et al. - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:application/pdf} } - Hague, Emma J., Mark Kamuda, William P. Ford, Eric T. Moore, and Johanna Turk. 2019. “A Comparison of Adaptive and Template Matching Techniques for Radio-Isotope Identification.” In Algorithms, Technologies, and Applications for Multispectral and Hyperspectral Imagery XXV, 10986:1098608. International Society for Optics and Photonics. https://doi.org/10.1117/12.2519062.
We compare and contrast the effectiveness of a set of adaptive and non-adaptive algorithms for isotope identification based on gamma-ray spectra. One dimensional energy spectra are simulated for a variety of dwell-times and source to detector distances in order to reflect conditions typically encountered in radiological emergency response and environmental monitoring applications. We find that adaptive methods are more accurate and computationally efficient than non-adaptive in cases of operational interest.
@inproceedings{hague_comparison_2019, title = {A comparison of adaptive and template matching techniques for radio-isotope identification}, volume = {10986}, url = {https://www.spiedigitallibrary.org/conference-proceedings-of-spie/10986/1098608/A-comparison-of-adaptive-and-template-matching-techniques-for-radio/10.1117/12.2519062.short}, doi = {10.1117/12.2519062}, urldate = {2019-10-30}, booktitle = {Algorithms, {Technologies}, and {Applications} for {Multispectral} and {Hyperspectral} {Imagery} {XXV}}, publisher = {International Society for Optics and Photonics}, author = {Hague, Emma J. and Kamuda, Mark and Ford, William P. and Moore, Eric T. and Turk, Johanna}, month = may, year = {2019}, pages = {1098608}, file = {Snapshot:/Users/huff/Zotero/storage/B5NG8X8D/12.2519062.html:text/html;Full Text PDF:/Users/huff/Zotero/storage/5ZBQBNJH/Hague et al. - 2019 - A comparison of adaptive and template matching tec.pdf:application/pdf} } - Chee, Gwendolyn J., and Kathryn D. Huff. 2019. “Simulation of Spent Nuclear Fuel Loading into a Final Waste Repository.” In WM Symposia 2019 Proceedings. Phoenix, AZ: Roy G. Post Foundation.
@inproceedings{chee_simulation_2019, address = {Phoenix, AZ}, title = {Simulation of {Spent} {Nuclear} {Fuel} loading into a {Final} {Waste} {Repository}}, booktitle = {{WM} {Symposia} 2019 {Proceedings}}, publisher = {Roy G. Post Foundation}, author = {Chee, Gwendolyn J. and Huff, Kathryn D.}, month = apr, year = {2019}, file = {Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:/Users/huff/Zotero/storage/8BZG9D2S/Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:application/pdf} } - Betzler, Benjamin R., Andrei Rykhlevskii, Andrew Worrall, and Kathryn D. Huff. 2019. “Impacts of Fast-Spectrum Molten Salt Reactor Characteristics on Fuel Cycle Performance.” In Proceedings of GLOBAL International Fuel Cycle Conference. Seattle, WA, United States: American Nuclear Society.
@inproceedings{betzler_impacts_2019, address = {Seattle, WA, United States}, title = {Impacts of {Fast}-{Spectrum} {Molten} {Salt} {Reactor} {Characteristics} on {Fuel} {Cycle} {Performance}}, booktitle = {Proceedings of {GLOBAL} {International} {Fuel} {Cycle} {Conference}}, publisher = {American Nuclear Society}, author = {Betzler, Benjamin R. and Rykhlevskii, Andrei and Worrall, Andrew and Huff, Kathryn D.}, month = sep, year = {2019}, file = {Snapshot:/Users/huff/Zotero/storage/SNHMA7NT/1566987.html:text/html;Full Text:/Users/huff/Zotero/storage/NAL94YJC/Betzler et al. - 2019 - Impacts of Fast-Spectrum Molten Salt Reactor Chara.pdf:application/pdf} } - Park, Sun Myung, Andrei Rykhlevskii, and Kathryn Huff. 2019. “Safety Analysis of Molten Salt Fast Reactor Fuel Composition Using Moltres.” In Proceedings of GLOBAL International Fuel Cycle Conference. Seattle, WA, United States: American Nuclear Society. https://doi.org/10.31224/osf.io/7ce89.
The Molten Salt Fast Reactor (MSFR) has garnered much interest for its inherent safety and sustainbility features. The MSFR can adopt a closed thorium fuel cycle for sustainable operation through the breeding of 233 U from 232 Th. The fuel composition changes significantly over the course of its lifespan. In this study, we investigated the steady state and transient behavior of the MSFR using Moltres, a coupled neutronics/thermal-hydraulics code developed within the Multiphysics Object Oriented Simulation Environment (MOOSE) framework. Three different fuel compositions, start-up, early-life, and equilibrium, were examined for potentially dangerous core temperature excursions during a unprotected loss of heat sink (ULOHS) accident. The six-group and total neutron flux distributions showed good agreement with SERPENT and published MSFR results, while the temperature distribution and total power showed discrepancies which can be attributed toknown sources of error. For the transient behavior under the ULOHS scenario, while the transition time towards the new steady state core temperature is also in good agreement with existing MSFR simulations by Fiorina et al., Moltres under-estimated the temperature rise by a factor of ten, due to the same sources of error affecting the steady state results. While an MSFR loaded with start-up fuel composition operates at a higher temperature than with the other two fuel compositions, all three cases were shown to be inherently safe due to thestrong negative temperature feedback.
@inproceedings{park_safety_2019, address = {Seattle, WA, United States}, title = {Safety {Analysis} of {Molten} {Salt} {Fast} {Reactor} {Fuel} {Composition} using {Moltres}}, url = {https://osf.io/7ce89}, doi = {10.31224/osf.io/7ce89}, urldate = {2019-11-05}, booktitle = {Proceedings of {GLOBAL} {International} {Fuel} {Cycle} {Conference}}, publisher = {American Nuclear Society}, author = {Park, Sun Myung and Rykhlevskii, Andrei and Huff, Kathryn}, month = sep, year = {2019}, file = {Park et al. - 2019 - Safety Analysis of Molten Salt Fast Reactor Fuel C.pdf:/Users/huff/Zotero/storage/EXYUTUGW/Park et al. - 2019 - Safety Analysis of Molten Salt Fast Reactor Fuel C.pdf:application/pdf} } - Rykhlevskii, Andrei, Daniel O’Grady, Tomasz Kozlowski, and Kathryn D. Huff. 2019. “The Impact of Xenon-135 on Load Following Transatomic Power Molten Salt Reactor.” In Transactions of the American Nuclear Society. Washington, DC, United States: American Nuclear Society.
@inproceedings{rykhlevskii_impact_2019, address = {Washington, DC, United States}, title = {The {Impact} of {Xenon}-135 on {Load} {Following} {Transatomic} {Power} {Molten} {Salt} {Reactor}}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Rykhlevskii, Andrei and O'Grady, Daniel and Kozlowski, Tomasz and Huff, Kathryn D.}, month = nov, year = {2019}, file = {Rykhlevskii et al. - 2019 - The Impact of Xenon-135 on Load Following Transato.pdf:/Users/huff/Zotero/storage/FS387NEW/Rykhlevskii et al. - 2019 - The Impact of Xenon-135 on Load Following Transato.pdf:application/pdf} } - Kissinger, Louis. 2018. “Simulating the Spent Fuel Recipe of a Sodium-Cooled Fast Reactor.” In Proceedings of the American Nuclear Society 2018 National Student Conference, Gainesville, FL, United States: American Nuclear Society.
@inproceedings{kissinger_simulating_2018, address = {Gainesville, FL, United States}, title = {Simulating the {Spent} {Fuel} {Recipe} of a {Sodium}-{Cooled} {Fast} {Reactor}}, booktitle = {Proceedings of the {American} {Nuclear} {Society} 2018 {National} {Student} {Conference},}, publisher = {American Nuclear Society}, author = {Kissinger, Louis}, month = apr, year = {2018} } - Westphal, Gregory, and Kathryn D. Huff. 2018. “Signatures and Observables in the Nuclear Fuel Cycle.” In CNEC Annual Workshop. Raleigh, N.C.: North Carolina State University.
@inproceedings{westphal_signatures_2018, address = {Raleigh, N.C.}, title = {Signatures and {Observables} in the {Nuclear} {Fuel} {Cycle}}, booktitle = {{CNEC} {Annual} {Workshop}}, publisher = {North Carolina State University}, author = {Westphal, Gregory and Huff, Kathryn D.}, month = feb, year = {2018}, note = {(Poster)} } - Chaube, Anshuman, James Stubbins, and Kathryn D. Huff. 2018. “Dynamic Transition Analysis with TIMES.” In I2CNER Annual Symposium. Fukuoka, Japan: Kyushu University.
@inproceedings{chaube_dynamic_2018, address = {Fukuoka, Japan}, title = {Dynamic {Transition} {Analysis} with {TIMES}}, booktitle = {{I2CNER} {Annual} {Symposium}}, publisher = {Kyushu University}, author = {Chaube, Anshuman and Stubbins, James and Huff, Kathryn D.}, month = jan, year = {2018}, note = {(Poster)}, file = {poster.pdf:/Users/huff/Zotero/storage/VL5BDNQB/poster.pdf:application/pdf} } - Kamuda, Mark. 2018. “A Comparison of Machine Learning Methods for Automated Gamma-Ray Spectroscopy.” In Proceedings of SORMA2018. Ann Arbor, MI. http://arfc.github.io/pres/2018-06-13-SORMA.pdf.
This poster outlines progress made comparing fully connected neural networks and convolution neural networks for isotope quantification in NaI gamma-ray spectra.
@inproceedings{kamuda_comparison_2018-1, address = {Ann Arbor, MI}, title = {A {Comparison} of {Machine} {Learning} {Methods} for {Automated} {Gamma}-{Ray} {Spectroscopy}}, url = {http://arfc.github.io/pres/2018-06-13-SORMA.pdf}, booktitle = {Proceedings of {SORMA2018}}, author = {Kamuda, Mark}, collaborator = {Zhao, Jifu and Huff, Kathryn}, month = jun, year = {2018} } - Westphal, Greg, and Kathryn Huff. 2018. “PyRe: A Cyclus Pyroprocessing Facility Archetype.” In Proceedings of the 2018 Advances in Nuclear Nonproliferation Technology and Policy Conference. Orlando, FL: American Nuclear Society.
This work assesses system parameters that influence separation efficiency and throughput of pyroprocessing facilities. We leverage these parameters to implement a customizable pyroprocessing facility archetype, PyRe, for use with the Cyclus framework. This generic facility model will allow simulations to quantify signatures and observables associated with various operational modes and material throughputs for a variety of facility designs. Such quantification can aid timely detection of material diversion. This paper describes the facility archetype design, pyroprocessing flowsheets captured by the model, and simulation capabilities it enables. To analyze data retrieved from the model, we additionally propose a class for tracking and observing signatures and observables which will be extensible for other facility archetypes in the future.
@inproceedings{westphal_pyre_2018, address = {Orlando, FL}, title = {{PyRe}: {A} {Cyclus} {Pyroprocessing} {Facility} {Archetype}}, booktitle = {Proceedings of the 2018 {Advances} in {Nuclear} {Nonproliferation} {Technology} and {Policy} {Conference}}, publisher = {American Nuclear Society}, author = {Westphal, Greg and Huff, Kathryn}, month = nov, year = {2018}, file = {2018-westphal-antpc.pdf:/Users/huff/Zotero/storage/UDEC8I6A/2018-westphal-antpc.pdf:application/pdf} } - Chee, Gwendolyn, Gyutae Park, and Kathryn D. Huff. 2018. “Validation of Spent Nuclear Fuel Output by Cyclus, a Fuel Cycle Simulator Code.” In Proceedings of the American Nuclear Society Winter Meeting 2018. Orlando, FL: American Nuclear Society.
Cyclus, a nuclear fuel cycle simulator, was used to simulate the United States’ nuclear fuel cycle from 1967 through 2013. The spent nuclear spent nuclear fuel (SNF) inventory from the Cyclus simulation was compared to the SNF inventory from the Department of Energy (DOE) sponsored Used Nuclear Fuel Storage, Transportation & Disposal Analysis Resource and Data System (UNFST&DARDS) Unified Database (UDB). The UDB provides comprehensive and consistent technical data on reactor sites and SNF from the beginning of nuclear reactor operation in the United States (US) until 2013. This comparison between Cyclus and UDB establishes a realistic validation of Cyclus’ capability to produce total spent fuel mass and accurate isotopic compositions that closely match reality.
@inproceedings{chee_validation_2018, address = {Orlando, FL}, title = {Validation of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}}, shorttitle = {Fuel {Cycle} {Analysis}}, booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting} 2018}, publisher = {American Nuclear Society}, author = {Chee, Gwendolyn and Park, Gyutae and Huff, Kathryn D.}, month = nov, year = {2018}, file = {Gwendolyn-Chee-ANSWinter2018.pdf:/Users/huff/Zotero/storage/IYYD7F3R/Gwendolyn-Chee-ANSWinter2018.pdf:application/pdf;Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:/Users/huff/Zotero/storage/PE67YJBQ/Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:application/pdf} } - Bae, Jin Whan, Joshua L. Peterson-Droogh, and Kathryn D. Huff. 2018. “Impact of Composition Approximation on Simulated Nuclear Fuel Cycle Metrics.” In Proceedings of the American Nuclear Society Winter Meeting. Orlando, FL: American Nuclear Society. http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf.
@inproceedings{bae_impact_2018-1, address = {Orlando, FL}, title = {Impact of {Composition} {Approximation} on {Simulated} {Nuclear} {Fuel} {Cycle} {Metrics}}, url = {http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf}, booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting}}, publisher = {American Nuclear Society}, author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.}, month = nov, year = {2018} } - Chee, Gwendolyn, Jin Whan Bae, and Kathryn D. Huff. 2018. “Numerical Experiments for Testing Demand-Driven Deployment Algorithms.” In Proceedings of the American Nuclear Society 2018 National Student Conference, Gainesville, FL, United States: American Nuclear Society.
For many fuel cycle simulators, it is currently up to the user to define a deployment scheme for each component of the fuel cycle to avoid gaps in the supply chain. This same goal could also be achieved by setting all the facility’s ca- pacities to infinity. However, this does not reflect real-world conditions [1]. To address this gap in capability of fuel cycle simulators, the Demand-Driven Cycamore Archetype project (NEUP-FY16-10512) is developing prediction algorithms to give Cyclus demand-driven deployment capabilities. This means that Cyclus will have the capability to deploy sup- porting fuel cycle facilities to meet front-end and back-end demands of the fuel cycle. The project is a collaboration between the University of Illinois Urbana-Champaign and the University of South Carolina. This paper will discuss the numerical experiments required to test the various prediction algorithms designed for the project. In particular, this work describes tests for the non-optimizing algorithm.
@inproceedings{chee_numerical_2018, address = {Gainesville, FL, United States}, title = {Numerical {Experiments} for testing {Demand}-{Driven} {Deployment} {Algorithms}}, booktitle = {Proceedings of the {American} {Nuclear} {Society} 2018 {National} {Student} {Conference},}, publisher = {American Nuclear Society}, author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D.}, month = apr, year = {2018}, file = {GwendolynChee-ansstuconf2018.pptx:/Users/huff/Zotero/storage/3AMPECLL/GwendolynChee-ansstuconf2018.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation;GwendolynChee-ansstuconf2018.pdf:/Users/huff/Zotero/storage/Z6KJXWVH/GwendolynChee-ansstuconf2018.pdf:application/pdf;Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:/Users/huff/Zotero/storage/ZWG7WHKJ/Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:application/pdf;Fulltext:/Users/huff/Zotero/storage/8729QICM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/7I6MM7HM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf} } - Huff, Kathryn D., Jin Whan Bae, Kathryn A. Mummah, Robert R. Flanagan, and Anthony M. Scopatz. 2017. “Current Status of Predictive Transition Capability in Fuel Cycle Simulation.” In Proceedings of Global 2017, 11. Seoul, South Korea: American Nuclear Society.
Nuclear fuel cycle simulation scenarios are most naturally described as constrained objective functions. The objectives are often systemic demands such as “achieve 1% growth for total electricity production and reach 10% uranium utilization”. The constraints take the form of nuclear fuel cycle technology availability (“reprocessing begins after 2025 and fast reactors first become available in 2050”). To match the natural constrained objective form of the scenario definition, NFC simulators must bring demand responsive deployment decisions into the dynamics of the simulation logic. In particular, a NFC simulator should have the capability to deploy supporting fuel cycle facilities to enable a demand to be met. Take, for instance, the standard once through fuel cycle. Reactors may be deployed to meet a objective power demand. However, new mines, mills, and enrichment facilities will also need to be deployed to ensure that reactors have sufficient fuel to produce power. In many simulators, the unrealistic solution to this problem is to simply have infinite capacity support facilities. Alternatively, detailing the deployment timeline of all facilities becomes the responsibility of the user. The authors seek to identify the most flexible, general, and performant algorithms applicable to this modeling challenge. Accordingly, a review was conducted of current NFC simulation tools to determine the current capabilites for demand-driven and transition scenarios. Additionally, the authors investigated promising algorithmic innovations that have been successful for similar applications in other domains such as economics and industrial engineering.
@inproceedings{huff_current_2017, address = {Seoul, South Korea}, title = {Current {Status} of {Predictive} {Transition} {Capability} in {Fuel} {Cycle} {Simulation}}, language = {en}, booktitle = {Proceedings of {Global} 2017}, publisher = {American Nuclear Society}, author = {Huff, Kathryn D. and Bae, Jin Whan and Mummah, Kathryn A. and Flanagan, Robert R. and Scopatz, Anthony M.}, month = sep, year = {2017}, pages = {11}, file = {Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:/Users/huff/Zotero/storage/CDQJ8KB8/Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:application/pdf;Huff et al. - Current Status of Predictive Transition Capability.pdf:/Users/huff/Zotero/storage/LE3726S6/Huff et al. - Current Status of Predictive Transition Capability.pdf:application/pdf} } - Rykhlevskii, Andrei, Alexander Lindsay, and Kathryn D. Huff. 2017. “Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor.” In Transactions of the American Nuclear Society. Washington, DC, United States: American Nuclear Society.
The current paper presents a single-cell model developed using the continuous-energy Serpent 2 Monte Carlo reactor physics software. It was employed to establish a Serpent- based method for finding the equilibrium core composition and core depletion of the Molten Salt Breeder Reactor (MSBR).
@inproceedings{rykhlevskii_online_2017, address = {Washington, DC, United States}, title = {Online reprocessing simulation for thorium-fueled molten salt breeder reactor}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Rykhlevskii, Andrei and Lindsay, Alexander and Huff, Kathryn D.}, month = nov, year = {2017}, file = {msbr_reproc.pdf:/Users/huff/Zotero/storage/PASSAITQ/msbr_reproc.pdf:application/pdf} } - ———. 2017. “Full-Core Analysis of Thorium-Fueled Molten Salt Breeder Reactor Using the SERPENT 2 Monte Carlo Code.” In Transactions of the American Nuclear Society. Washington, DC, United States: American Nuclear Society.
We used the continuous-energy Serpent 2 Monte Carlo particle transport code to calulate whole-core depletion in the thermal spectrum Molten Salt Breeder Reactor (MSBR) . We then compare these results with existing MCNP6 results with a more simplified geometric model. This neutronics model is of sufficient fidelity to inform optimization of fuel salt composition, fuel utilization, neutron fluxes, and spectrum evaluation. Moreover, this model will be employed for depeletion calculations, generation of problem-oriented homogenized nuclear data (multi-group cross sections and diffusion constants) for deterministic reactor codes, and multiphysics simulations.
@inproceedings{rykhlevskii_full-core_2017, address = {Washington, DC, United States}, title = {Full-core analysis of thorium-fueled {Molten} {Salt} {Breeder} {Reactor} using the {SERPENT} 2 {Monte} {Carlo} code}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Rykhlevskii, Andrei and Lindsay, Alexander and Huff, Kathryn D.}, month = nov, year = {2017}, file = {full-core_msbr_model.pdf:/Users/huff/Zotero/storage/3F8DA752/full-core_msbr_model.pdf:application/pdf} } - Ridley, Gavin, Alexander Lindsay, and Kathryn Huff. 2017. “An Introduction to Moltres, an MSR Multiphysics Code.” In Transactions of the American Nuclear Society. Washington D.C.: American Nuclear Society. http://arfc.github.io/pres/2017-10-31-moltres.pdf.
@inproceedings{ridley_introduction_2017, address = {Washington D.C.}, title = {An {Introduction} to {Moltres}, an {MSR} {Multiphysics} {Code}}, url = {http://arfc.github.io/pres/2017-10-31-moltres.pdf}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Ridley, Gavin and Lindsay, Alexander and Huff, Kathryn}, month = oct, year = {2017} } - Bae, Jin Whan, William Roy, and Kathryn D. Huff. 2017. “Benefits of Siting a Borehole Repository at a Non-Operating Nuclear Facility.” In Proceedings of the International High Level Radioactive Waste Management Conference. Charlotte, North Carolina: American Nuclear Society.
This work evaluates a potential solution for two pressing matters in the viability of nuclear energy: spent fuel disposal and power plants that no longer operate. The potential benefits of siting a borehole repository at a shut down nuclear power plant facility are analyzed from the perspective of myriad stake- holders. This assessment indicates that integrated siting will make economic use of the shut down power plant, take advan- tage of spent fuel handling infrastructure at those sites, mini- mize transportation costs, expedite emptying the crowded spent fuel storage pools accross the country, and will do so at sites more likely to have consenting communities.
@inproceedings{bae_benefits_2017, address = {Charlotte, North Carolina}, title = {Benefits of {Siting} a {Borehole} {Repository} at a {Non}-operating {Nuclear} {Facility}}, booktitle = {Proceedings of the {International} {High} {Level} {Radioactive} {Waste} {Management} {Conference}}, publisher = {American Nuclear Society}, author = {Bae, Jin Whan and Roy, William and Huff, Kathryn D.}, month = apr, year = {2017} } - Smith, Arfon, Lorena A. Barba, George Githinji, Melissa Gymrek, Kathryn Huff, Daniel S. Katz, Christopher Madan, et al. 2017. “The Journal of Open Source Software.” In Poster. Vol. Computational Science and Engineering. Atlanta, GA: Society for Industrial and Applied Mathematics. https://doi.org/10.6084/m9.figshare.4688911.v1.
Poster presented at SIAM CSE17 PP108 Minisymposterium: Software Productivity and Sustainability for CSE and Data ScienceAbstract:This poster describes the motivation and progress of the Journal of Open Source Software (JOSS), a free, open-access journal designed to publish brief papers about research software. The primary purpose of JOSS is to enable developers of research software to receive citation credit equivalent to typical archival publications. JOSS papers are deliberately extremely short, and are required to include a short abstract describing the purpose and functionality of the software, authors and their affiliations, and key references, as well as link to an archived version of the software (e.g., DOI obtained from Zenodo). Upon acceptance, papers receive a CrossRef DOI. Rather than a review of a lengthy software paper (including, e.g., methodology, validation, sample results), JOSS submissions undergo rigorous peer review of both the abstract and software itself, including documentation, tests, continuous integration, and licensing. The JOSS review process is modeled on the established approach of the rOpenSci collaboration. The entire submission and review process occurs openly on GitHub; papers not yet accepted remain visible and under review until the authors make appropriate changes for acceptance—unlike other journals, papers requiring major revision are not rejected. Since its public release in May 2016, JOSS has published 26 accepted papers as of September 2016, with an additional 20 submitted and under review.
@inproceedings{smith_journal_2017, address = {Atlanta, GA}, title = {The {Journal} of {Open} {Source} {Software}}, volume = {Computational Science and Engineering}, url = {https://figshare.com/articles/The_Journal_of_Open_Source_Software/4688911}, doi = {10.6084/m9.figshare.4688911.v1}, urldate = {2018-07-22}, booktitle = {Poster}, publisher = {Society for Industrial and Applied Mathematics}, author = {Smith, Arfon and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn and Katz, Daniel S. and Madan, Christopher and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Niemeyer, Kyle and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy and Vanderplas, Jake}, month = feb, year = {2017}, keywords = {Software citation, JOSS, Open research software, Open software, SIAM-CSE17-PP108}, file = {Figshare Snapshot:/Users/huff/Zotero/storage/36AQBT45/4688911.pdf:application/pdf} } - Bae, Jin Whan, Kathryn Huff, and Clifford Singer. 2017. “Synergistic Spent Nuclear Fuel Dynamics Within the European Union.” In Transactions of the American Nuclear Society Winter Conference. Washington, D.C.: American Nuclear Society.
The French strategy recommended by 2012-2015 Commission Nationale d’Evaluation reports [1] emphasizes preparation for a transition from Light Water Reactors (LWRs) to Sodium-Cooled Fast Reactors (SFRs). This paper uses Cyclus to explore the feasibility of using Used Nuclear Fuel (UNF) from other EU nations for French transition into a SFR fleet without additional construction of LWRs. A Cyclus simulation is run from 1950 to 2160 for EU to track the UNF mass and to determine the necessary reprocessing and mixed oxide (MOX) fabrication capacity to support the transition into SFRs. The study concludes that France can avoid deployment of additional LWRs by accepting UNF from other EU nations.
@inproceedings{bae_synergistic_2017, address = {Washington, D.C.}, title = {Synergistic {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union}}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Winter} {Conference}}, publisher = {American Nuclear Society}, author = {Bae, Jin Whan and Huff, Kathryn and Singer, Clifford}, month = oct, year = {2017}, file = {europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/KEJMSZTE/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/LGFAP2BG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/MKKTZAGM/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/NLNAKMUG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/ZP787VN4/europe_nuclear_paper.pdf:application/pdf} } - Huff, Kathryn. 2015. “PyRK: A Python Package For Nuclear Reactor Kinetics.” In Proceedings of the 14th Python in Science Conference, 87–93. Austin, TX, United States: SciPy. https://doi.org/10.25080/Majora-7b98e3ed-00d.
In this work, a new python package, PyRK (Python for Reactor Kinetics), is introduced. PyRK has been designed to simulate, in zero dimensions, the transient, coupled, thermal-hydraulics and neutronics of time-dependent behavior in nuclear reactors. PyRK is intended for analysis of many commonly studied transient scenarios including normal reactor startup and shutdown as well as abnormal scenarios including Beyond Design Basis Events (BDBEs) such as Accident Transients Without Scram (ATWS). For robustness, this package employs various tools within the scientific python ecosystem. For additional ease of use, it employs a reactor-agnostic, object-oriented data model, allowing nuclear engineers to rapidly prototype nuclear reactor control and safety systems in the context of their novel nuclear reactor designs.
@inproceedings{huff_pyrk:_2015, address = {Austin, TX, United States}, title = {{PyRK}: {A} {Python} {Package} {For} {Nuclear} {Reactor} {Kinetics}}, shorttitle = {{PyRK}}, url = {http://conference.scipy.org/proceedings/scipy2015/kathryn_huff.html}, doi = {10.25080/Majora-7b98e3ed-00d}, urldate = {2018-11-08}, booktitle = {Proceedings of the 14th {Python} in {Science} {Conference}}, publisher = {SciPy}, author = {Huff, Kathryn}, year = {2015}, pages = {87--93}, file = {Snapshot:/Users/huff/Zotero/storage/WN5HB4GE/kathryn_huff.html:text/html;Full Text PDF:/Users/huff/Zotero/storage/W6JJYW6S/Huff - 2015 - PyRK A Python Package For Nuclear Reactor Kinetic.pdf:application/pdf} } - Krumwiede, David L., C. Andreades, J.K. Choi, A.T. Cisneros, Lakshana Huddar, Kathryn D. Huff, M.D. Laufer, et al. 2014. “Design of the Mark-1 Pebble-Bed, Fluoride-Salt-Cooled, High-Temperature Reactor Commercial Power Plant.” In Proceedings of ICAPP. Charlotte, North Carolina.
@inproceedings{krumwiede_design_2014, address = {Charlotte, North Carolina}, title = {Design of the {Mark}-1 {Pebble}-{Bed}, {Fluoride}-{Salt}-{Cooled}, {High}-{Temperature} {Reactor} {Commercial} {Power} {Plant}}, shorttitle = {Paper 14231}, booktitle = {Proceedings of {ICAPP}}, author = {Krumwiede, David L. and Andreades, C. and Choi, J.K. and Cisneros, A.T. and Huddar, Lakshana and Huff, Kathryn D. and Laufer, M.D. and Munk, Madicken and Scarlat, Raluca O. and Seifried, Jeffrey E. and Zwiebaum, Nicolas and Greenspan, Ehud and Peterson, Per F.}, year = {2014}, file = {ICAPP 2014 FHR Design.pdf:/Users/huff/Zotero/storage/BFMHUH6X/ICAPP 2014 FHR Design.pdf:application/pdf} } - Bates, Cameron, Elliot D. Biondo, Kathryn D. Huff, Kalin Kiesling, and Anthony M. Scopatz. 2014. “PyNE Progress Report.” In Transactions of the American Nuclear Society. Anaheim, CA, United States: American Nuclear Society.
PyNE is a suite of free and open source (BSD licensed) tools to aid in computational nuclear science and engineer- ing. PyNE seeks to provide native implementations of com- mon nuclear algorithms, as well as an interface for the script- ing language Python and I/O support for industry standard nuclear codes and data formats. In the past year PyNE has added many features including a Rigorous 2-step Ac- tivation workflow (R2S) [1], Direct Accelerated Geometry Monte Carlo (DAGMC) ray tracing [2], Consistent Adjoint- Weighted Importance Sampling (CADIS) variance reduction [3], and expanded ENSDF parsing support. As a part of our ongoing efforts to implement a verification and validation framework we also added continuous integration using the Build and Test Lab [4] at the University of Wisconsin. The PyNE development team has also improved PyNE’s ease of use by making binaries available for Windows, Mac, and Linux through the conda package manager as well as adding Python 3 support.
@inproceedings{bates_pyne_2014, address = {Anaheim, CA, United States}, title = {{PyNE} {Progress} {Report}}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Bates, Cameron and Biondo, Elliot D. and Huff, Kathryn D. and Kiesling, Kalin and Scopatz, Anthony M.}, month = nov, year = {2014} } - Huff, Kathryn D., Massimiliano Fratoni, and Harris Greenberg. 2014. “Extensions to the Cyclus Ecosystem In Support of Market-Driven Transition Capability.” In Transactions of the American Nuclear Society, 245–48. Fuel Cycle Options Analysis – III. Anaheim, CA, United States: American Nuclear Society.
The C YCLUS Fuel Cycle Simulator [1] is a framework for assessment of nuclear fuel cycle options. While C Y - CLUS has previously been capable of system transitions from the current fuel cycle strategy to a future option, those transitions have never previously been driven by market forces in the simulation. This summary describes a set of libraries [2] that have been contibuted to the C YCLUS framework to enable a market-driven transition analysis. This simulation framework is incomplete without a suite of dynamically loadable libraries representing the process physics of the nuclear fuel cycle (i.e. mining, fuel fabri- cation, chemical processing, transmutation, reprocessing, etc.). Within Cycamore [3], the additional modules reposi- tory within the C YCLUS ecosystem, provides some basic li- braries to represent these processes. However, extension of C YCLUS with new capabilities is community-driven, rely- ing on contributions by user-developers. The libraries con- tributed in this work are examples of such contributions.
@inproceedings{huff_extensions_2014, address = {Anaheim, CA, United States}, series = {Fuel {Cycle} {Options} {Analysis} -- {III}}, title = {Extensions to the {Cyclus} {Ecosystem} {In} {Support} of {Market}-{Driven} {Transition} {Capability}}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Huff, Kathryn D. and Fratoni, Massimiliano and Greenberg, Harris}, month = nov, year = {2014}, note = {LLNL-PROC-656426}, pages = {245--248}, file = {huff_extensions_2014.pdf:/Users/huff/Zotero/storage/MV2TCELS/huff_extensions_2014.pdf:application/pdf} } - Gidden, Matthew, Paul Wilson, Kathryn D. Huff, and Robert W. Carlsen. 2013. “An Agent-Based Framework for Fuel Cycle Simulation with Recycling.” In Proceedings of GLOBAL. Salt Lake City, UT, United States.
Simulation of the nuclear fuel cycle is an established field with multiple players. Prior development work has utilized tech- niques such as system dynamics to provide a solution structure for the matching of supply and demand in these simulations. In general, however, simulation infrastructure development has occured in relatively closed circles, each effort having unique considerations as to the cases which are desired to be modeled. Accordingly, individual simulators tend to have their design decisions driven by specific use cases. Presented in this work is a proposed supply and demand matching algorithm that lever- ages the techniques of the well-studied field of mathematical programming. A generic approach is achieved by treating fa- cilities as individual entities and actors in the supply-demand market which denote preferences amongst commodities. Using such a framework allows for varying levels of interaction fi- delity, ranging from low-fidelity, quick solutions to high-fidelity solutions that model individual transactions (e.g. at the fuel- assembly level). The power of the technique is that it allows such flexibility while still treating the problem in a generic man- ner, encapsulating simulation engine design decisions in such a way that future simulation requirements can be relatively easily added when needed.
@inproceedings{gidden_agent-based_2013, address = {Salt Lake City, UT, United States}, title = {An {Agent}-{Based} {Framework} for {Fuel} {Cycle} {Simulation} with {Recycling}}, booktitle = {Proceedings of {GLOBAL}}, author = {Gidden, Matthew and Wilson, Paul and Huff, Kathryn D. and Carlsen, Robert W.}, month = sep, year = {2013}, file = {paper.pdf:/Users/huff/Zotero/storage/B5S7VPDZ/paper.pdf:application/pdf;abstract.pdf:/Users/huff/Zotero/storage/EGDJQBFB/abstract.pdf:application/pdf} } - Huff, Kathryn D., and Alexander T. Bara. 2013. “Dynamic Determination of Thermal Repository Capacity For Fuel Cycle Analysis.” In Transactions of the American Nuclear Society, 108:123–26. Atlanta, GA, United States: American Nuclear Society.
An algorithm and supporting database for rapid thermal repository capacity calculation implemented in Cyder, a soft- ware library for coupled thermal and hydrologic repository per- formance analysis, is described. Integration of Cyder with the Cyclus fuel cycle simulator is also described. Finally, a proof of principle demonstration is presented in which the rapid cal- culation method described here is compared with results of a more detailed model.
@inproceedings{huff_dynamic_2013, address = {Atlanta, GA, United States}, title = {Dynamic {Determination} of {Thermal} {Repository} {Capacity} {For} {Fuel} {Cycle} {Analysis}}, volume = {108}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Huff, Kathryn D. and Bara, Alexander T.}, month = jun, year = {2013}, pages = {123--126}, file = {trans_v108_n1_pp123-126 (1).pdf:/Users/huff/Zotero/storage/3I456PBS/trans_v108_n1_pp123-126 (1).pdf:application/pdf} } - Huff, Kathryn D. 2013. “Hydrologic Nuclide Transport Models in Cyder, a Geologic Disposal Software Library.” In WM2013. Phoenix, AZ: Waste Management Symposium.
@inproceedings{huff_hydrologic_2013, address = {Phoenix, AZ}, title = {Hydrologic {Nuclide} {Transport} {Models} in {Cyder}, a {Geologic} {Disposal} {Software} {Library}.}, shorttitle = {13328}, booktitle = {{WM2013}}, publisher = {Waste Management Symposium}, author = {Huff, Kathryn D.}, month = feb, year = {2013}, file = {13328.pdf:/Users/huff/Zotero/storage/PDX4HEJI/13328.pdf:application/pdf;13328_corrected.pdf:/Users/huff/Zotero/storage/XH8F792K/13328_corrected.pdf:application/pdf} } - ———. 2013. “Cyclus Fuel Cycle Simulation Capabilities with the Cyder Disposal System Model.” In Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference-Nuclear Energy at a Crossroads. Salt Lake City, UT, United States.
@inproceedings{huff_cyclus_2013, address = {Salt Lake City, UT, United States}, title = {Cyclus {Fuel} {Cycle} {Simulation} {Capabilities} with the {Cyder} {Disposal} {System} {Model}}, booktitle = {Proceedings of {GLOBAL} 2013: {International} {Nuclear} {Fuel} {Cycle} {Conference}-{Nuclear} {Energy} at a {Crossroads}}, author = {Huff, Kathryn D.}, month = oct, year = {2013}, file = {Snapshot:/Users/huff/Zotero/storage/CTPH9CQQ/search.html:text/html;cyder.pdf:/Users/huff/Zotero/storage/BRUIU96K/cyder.pdf:application/pdf;huff_global_2013.pdf:/Users/huff/Zotero/storage/75K3EDPX/huff_global_2013.pdf:application/pdf} } - Huff, Kathryn, and Theodore H. Bauer. 2012. “Numerical Calibration of an Analytical Generic Nuclear Repository Heat Transfer Model.” In Transactions of the American Nuclear Society, 106:260–63. Modeling and Simulation in the Fuel Cycle. Chicago, IL, United States: American Nuclear Society, La Grange Park, IL 60526, United States.
This work describes a benchmarking effort conducted to de- termine the accuracy of a new generic geology thermal repos- itory model relative to more traditional techniques and pro- poses a physically plausible auxillary thermal resistance com- ponent to improve their agreement.
@inproceedings{huff_numerical_2012, address = {Chicago, IL, United States}, series = {Modeling and {Simulation} in the {Fuel} {Cycle}}, title = {Numerical {Calibration} of an {Analytical} {Generic} {Nuclear} {Repository} {Heat} {Transfer} {Model}}, volume = {106}, language = {English}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society, La Grange Park, IL 60526, United States}, author = {Huff, Kathryn and Bauer, Theodore H.}, month = jun, year = {2012}, pages = {260--263}, file = {trans_v106_n1_pp260-263.pdf:/Users/huff/Zotero/storage/ICEUPH4S/trans_v106_n1_pp260-263.pdf:application/pdf;ans2012pres.pdf:/Users/huff/Zotero/storage/CX5QC6ZF/ans2012pres.pdf:application/pdf} } - Scopatz, Anthony, Paul K. Romano, Paul P. H. Wilson, and Kathryn D. Huff. 2012. “PyNE: Python for Nuclear Engineering.” In Transactions of the American Nuclear Society. Vol. 107. San Diego, CA, USA: American Nuclear Society.
PyNE, or ’Python for Nuclear Engineering’ 1 , is a nascent free and open source C++/Cython/Python package for perform- ing common nuclear engineering tasks. This is intended as a base level tool kit - akin to SciPy or Biopython - for common algorithms in the nuclear science and engineering domain. The remainer of this paper is composed of a discussion of the difficulties which prevented PyNE from being written earlier, a listing of the first cut capabilities, and a description of why PyNE has thus far been successful and what future features are currently planned.
@inproceedings{scopatz_pyne:_2012, address = {San Diego, CA, USA}, title = {{PyNE}: {Python} for {Nuclear} {Engineering}}, volume = {107}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Scopatz, Anthony and Romano, Paul K. and Wilson, Paul P. H. and Huff, Kathryn D.}, month = nov, year = {2012}, file = {trans_v107_n1_pp985-987.pdf:/Users/huff/Zotero/storage/TQ9E3XGC/trans_v107_n1_pp985-987.pdf:application/pdf} } - Huff, Kathryn D., and W. Mark Nutt. 2012. “Key Processes and Parameters in a Generic Clay Disposal System Model.” In Transactions of the American Nuclear Society, 107:208–11. Environmental Sciences – General. San Diego, CA: American Nuclear Society. http://epubs.ans.org.ezproxy.library.wisc.edu/download/?a=14711.
Sensitivity analysis was performed with respect to various key processes and parameters affecting long-term post-closure performance of geologic repositories in clay media. Based on the detailed computational Clay Generic Disposal Sys- tem Model (GDSM) developed by the Used Fuel Disposition (UFD) campaign [1], these results provide an overview of the relative importance of processes that affect the repository per- formance of a generic clay disposal concept model. Further analysis supports a basis for development of rapid abstracted models in the context of system level fuel cycle simulation. Processes and parameters found to influence repository perfor- mance include the rate of waste form degradation, timing of waste package failure, and various coupled geochemical and hydrologic characteristics of the natural system including dif- fusion, solubility, and advection.
@inproceedings{huff_key_2012, address = {San Diego, CA}, series = {Environmental {Sciences} -- {General}}, title = {Key {Processes} and {Parameters} in a {Generic} {Clay} {Disposal} {System} {Model}}, volume = {107}, url = {http://epubs.ans.org.ezproxy.library.wisc.edu/download/?a=14711}, language = {English}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Huff, Kathryn D. and Nutt, W. Mark}, month = nov, year = {2012}, pages = {208--211}, file = {ans2012winterpres.pdf:/Users/huff/Zotero/storage/DBZTEAGJ/ans2012winterpres.pdf:application/pdf;trans_v107_n1_pp208-211.pdf:/Users/huff/Zotero/storage/SQMC825E/trans_v107_n1_pp208-211.pdf:application/pdf} } - Gidden, Matthew J., Paul P.H. Wilson, Kathryn D. Huff, and Robert W. Carlsen. 2012. “Once-Through Benchmarks with CYCLUS, a Modular, Open-Source Fuel Cycle Simulator.” In Transactions of the American Nuclear Society, 107:264–66. Nuclear Fuel Cycle Resources, Sustainability, Reuse, and Recycle. San Diego, CA: American Nuclear Society, La Grange Park, IL 60526, United States.
The C YCLUS project, based at the University of Wisconsin - Madison, is an open source platform for exploring the long- term impact of alternative nuclear fuel cycles. The C YCLUS core provides the infrastructure for an agent-based approach, allowing user-provided modules to define the behavior of fuel cycle facilities as they interact to exchange materials. An im- portant consequence of this approach is that innovative facility and material exchange concepts can be introduced to a consis- tent framework allowing for more rigorous comparison. The C YCLUS team has recently grown and now incorporates a vari- ety of expertise: output visualization capability through collab- oration with the University of Utah, server-client communica- tion via the University of Idaho, input visualization and control with the University of Texas - Austin, and social communica- tion expertise through collaborators at UW-Madison to assist the mission-critical goal of relevancy vis-à-vis policy makers. Accordingly, the C YCLUS project is expanding efforts in the realms of both structural capability and benchmarking calcula- tions. A series of once-through fuel cycle scenarios are being con- ducted using the C YCLUS core and accompanying modules. Where needed, additional modules have been added, includ- ing a region model that intelligently makes building decisions given a demand function. The results of these scenarios are then compared with VISION [1] to provide a benchmark of the C YCLUS results.
@inproceedings{gidden_once-through_2012, address = {San Diego, CA}, series = {Nuclear {Fuel} {Cycle} {Resources}, {Sustainability}, {Reuse}, and {Recycle}}, title = {Once-{Through} {Benchmarks} with {CYCLUS}, a {Modular}, {Open}-{Source} {Fuel} {Cycle} {Simulator}}, volume = {107}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society, La Grange Park, IL 60526, United States}, author = {Gidden, Matthew J. and Wilson, Paul P.H. and Huff, Kathryn D. and Carlsen, Robert W.}, month = nov, year = {2012}, pages = {264--266}, file = {trans_v107_n1_pp264-266 (1).pdf:/Users/huff/Zotero/storage/SMGXZFGK/trans_v107_n1_pp264-266 (1).pdf:application/pdf} } - Huff, Kathryn D., A.M. Scopatz, N.D. Preston, and P.P.H. Wilson. 2011. “Rapid Peer Education of a Computational Nuclear Engineering Skill Suite.” In Transactions of the American Nuclear Society, 104:103–4. Training, Human Performance, and Work Force Development. Hollywood, FL, United States: American Nuclear Society, La Grange Park, IL 60526, United States.
Detailed reactor models, massively parallelized calculations, and enormously collaborative simulation projects are increas- ingly integral to nuclear engineering. However, the quality and caliber of this work is limited by a workforce lacking formal training in a software development skill suite that is becom- ing increasingly essential. To address this unmet need, The Hacker Within (THW), a student organization at the University of Wisconsin, has developed a series of short courses address- ing best practices such as version control and test driven code development, as well as basic skills such as UNIX mobility. These ’Boot Camps’ seek to provide time efficient introduc- tions to essential programming languages and tools without turning “biochemists and mechanical engineers into computer scientists.”[1][2]
@inproceedings{huff_rapid_2011, address = {Hollywood, FL, United States}, series = {Training, {Human} {Performance}, and {Work} {Force} {Development}}, title = {Rapid {Peer} {Education} of a {Computational} {Nuclear} {Engineering} {Skill} {Suite}}, volume = {104}, language = {English}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society, La Grange Park, IL 60526, United States}, author = {Huff, Kathryn D. and Scopatz, A.M. and Preston, N.D. and Wilson, P.P.H.}, month = jun, year = {2011}, keywords = {Software, Reactor, Education, Models, Computer Science, The Hacker Within (THW)}, pages = {103--104}, file = {trans_v104_n1_pp103-104.pdf:/Users/huff/Zotero/storage/MF3BA6DB/trans_v104_n1_pp103-104.pdf:application/pdf;thwANS2011pres.pdf:/Users/huff/Zotero/storage/4CW3QC9Q/thwANS2011pres.pdf:application/pdf;Rapid Peer Education Nuclear Engineering.pdf:/Users/huff/Zotero/storage/V438NNXC/Rapid Peer Education Nuclear Engineering.pdf:application/pdf} } - Huff, Kathryn D., Paul PH Wilson, and Matthew J. Gidden. 2011. “Open Architecture and Modular Paradigm of Cyclus, a Fuel Cycle Simulation Code.” In Transactions of the American Nuclear Society, 104:183.
The C YCLUS project at the University of Wisconsin - Madi- son is the result of lessons learned from experience with pre- vious nuclear fuel cycle simulation platforms. The modeling paradigm follows the transacation of discrete quanta of ma- terial among discrete facilities, arranged in a geographic and institutional framework, and trading in flexible markets. Key concepts in the design of C YCLUS include open access to the simulation engine, modularity with regard to functionality, and relevance to both scientific and policy analyses. The combina- tion of modular encapsulation within the software architec- ture and an open development paradigm allows for a bal- ance between collaboration at multiple levels of simulation detail and security of proprietary or sensitive data. When comparing different nuclear fuel cycle concepts, it can be a challenge to find any two systems analyses that com- pare across a common set of metrics with a similar set of un- derlying assumptions. Each analysis is likely to focus on a set of metrics that are of interest to the team performing the analy- sis and involve both implicit and explicit assumptions and con- straints about the behavior of the fuel cycle system. While a strict prescription of these metrics, assumptions and con- straints could be proposed for comparison purposes, another solution is to provide a systems analysis simulation tool that provides sufficient modularity, extensibility and open access, that it can be a basis for harmonzing to a common set. If it becomes easier to modify an existing simulation tool to sup- port the needs of a new analysis than it is to develop a new tool, then it is possible that such a tool will be adopted more universally for such analysis.
@inproceedings{huff_open_2011, title = {Open {Architecture} and {Modular} {Paradigm} of {Cyclus}, a {Fuel} {Cycle} {Simulation} {Code}}, volume = {104}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, author = {Huff, Kathryn D. and Wilson, Paul PH and Gidden, Matthew J.}, month = jun, year = {2011}, pages = {183}, file = {trans_v104_n1_pp183-184.pdf:/Users/huff/Zotero/storage/HJPWVTI8/trans_v104_n1_pp183-184.pdf:application/pdf;cyclusANS2011pres.pdf:/Users/huff/Zotero/storage/H5VT3BKD/cyclusANS2011pres.pdf:application/pdf} } - Huff, Kathryn D. 2011. “Cyclus: An Open, Modular, Next Generation Fuel Cycle Simulator Platform (Poster).” In Proceedings of the Waste Management Symposium. Phoenix, AZ.
CYCLUS is a top-level, next generation, nuclear fuel cycle simulation framework designed with an open development process and modular platform. It employs lessons learned from previous efforts to pursue quantitative assessment of worldwide nuclear energy production, material flows, energy costs, environmental impact, proliferation resistance, and robustness against supply disruption.
@inproceedings{huff_cyclus_2011, address = {Phoenix, AZ}, title = {Cyclus: {An} {Open}, {Modular}, {Next} {Generation} {Fuel} {Cycle} {Simulator} {Platform} (poster)}, booktitle = {Proceedings of the {Waste} {Management} {Symposium}}, author = {Huff, Kathryn D.}, month = mar, year = {2011}, file = {WM2011.pdf:/Users/huff/Zotero/storage/ID9PP8PC/WM2011.pdf:application/pdf;WM2011.pdf:/Users/huff/Zotero/storage/ACQ4MUR5/WM2011.pdf:application/pdf} } - Huff, Kathryn D., Royal A. Elmore, Kyle M. Oliver, and Paul P.H. Wilson. 2010. “MOX Fuel Recipe Approximation Tests in GENIUSv2.” In Transactions of the American Nuclear Society Student Meeting. Ypsilanti, MI.
The GENIUS project (Global Evaluation of Nuclear Infrastructure Utilization Scenarios) was conceived as the top-level nuclear enterprise simulation tool in the Simulation Institute for Nuclear Enterprise Modelling and Analysis (SINEMA) framework1. The current version, GENIUSv2, is an object-oriented C++ application with Python-based pre- and post-processing. The GENIUSv2 tool proposes to inform nuclear fuel cycle technology and policy by providing a richly detailed, modular platform capable of dynamically modeling complexly integrated international fuel cycles such as those involving separations and reprocessing schemes. Here we present results of the GENIUSv2 testing suite which demonstrate neutronics weighting methods for approximating optimal mixed oxide fuel compositions. These weighting methods achieve various levels of success at assembling critical fuel recipes from separated spent fuel streams for fuel cycles incorporating mixed oxide reprocessing. Results of neutronics constraining and neutronics weighting methods are here compared and alternative linear programmatic formulations are proposed for determining mixed-oxide (MOX) fuel compositions from available material.
@inproceedings{huff_mox_2010, address = {Ypsilanti, MI}, title = {{MOX} {Fuel} {Recipe} {Approximation} {Tests} in {GENIUSv2}}, booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Meeting}}, author = {Huff, Kathryn D. and Elmore, Royal A. and Oliver, Kyle M. and Wilson, Paul P.H.}, month = apr, year = {2010}, file = {ansStudent10RAP.doc:/Users/huff/Zotero/storage/V8G5DB2Z/ansStudent10RAP.doc:application/msword} } - Oliver, Kyle M., Paul P.H. Wilson, Arnaud Reveillere, Tae Wook Ahn, Kerry Dunn, Kathryn D. Huff, and Royal A. Elmore. 2009. “Studying International Fuel Cycle Robustness with the GENIUSv2 Discrete Facilities/Materials Fuel Cycle Systems Analysis Tool.” In Proceedings of GLOBAL 2009. GLOBAL 2009: Advanced Nuclear Fuel Cycles and Systems. Paris, France.
@inproceedings{oliver_studying_2009, address = {Paris, France}, series = {{GLOBAL} 2009: {Advanced} {Nuclear} {Fuel} {Cycles} and {Systems}}, title = {Studying international fuel cycle robustness with the {GENIUSv2} discrete facilities/materials fuel cycle systems analysis tool}, booktitle = {Proceedings of {GLOBAL} 2009}, author = {Oliver, Kyle M. and Wilson, Paul P.H. and Reveillere, Arnaud and Ahn, Tae Wook and Dunn, Kerry and Huff, Kathryn D. and Elmore, Royal A.}, month = sep, year = {2009}, keywords = {Discrete Facility/ Discrete Model (DF/DM), Geniusv2, Capacity, Mass Flow Data, Nuclear Fuel Cycle Facilities, Nuclear Fuel Cycle Systems Analysis Tool}, file = {2009_9_Oliver-GENIUS-GLOBAL2009-proceedings.pdf:/Users/huff/Zotero/storage/NUX2KS8H/2009_9_Oliver-GENIUS-GLOBAL2009-proceedings.pdf:application/pdf;2009_9_Oliver-GENIUS-GLOBAL2009-abstract.doc:/Users/huff/Zotero/storage/UQM8PS63/2009_9_Oliver-GENIUS-GLOBAL2009-abstract.doc:application/msword;2009_9_Oliver-GENIUS-GLOBAL2009-submission.pdf:/Users/huff/Zotero/storage/AUWFJWRA/2009_9_Oliver-GENIUS-GLOBAL2009-submission.pdf:application/pdf;2009_9_Oliver-GENIUS-GLOBAL2009-submission.doc:/Users/huff/Zotero/storage/7VZ5TN97/2009_9_Oliver-GENIUS-GLOBAL2009-submission.doc:application/msword} } - Elmore, R. A, K. M Oliver, P. P.H Wilson, Tae Wook Ahn, Kerry L. Dunn, and Kathryn D. Huff. 2009. “GENIUSv2 Recipe Approximation Methodology for Mixed-Oxide Fuel.” In Transactions of the American Nuclear Society, 101:241–42. Nuclear Fuel Cycle Codes and Applications. Washington D.C., United States.
The Simulation Institute for Nuclear Enterprise Modeling and Analysis (SINEMA) developed the GENIUS (Global Evaluation of Nuclear Infrastructure Utilization Scenarios) project as the umbrella nuclear fuel cycle simulation package 1 . GENIUSv2 is the next iteration and is an object-oriented C++ program using Python pre- and post-processing wrappers. As a package, GENIUSv2 supports dynamic modeling of regional and institutional interactions of nuclear fuel cycle facilities, using a discrete material/discrete facility paradigm. The engineering calculations and analysis needed for each different facility and process are handled by separate modules within GENIUSv2. Results from the GENIUSv2 separations module are presented that detail the robust approximation methodology for creating mixed-oxide (MOX) fuel recipes from available separated material.
@inproceedings{elmore_geniusv2_2009, address = {Washington D.C., United States}, series = {Nuclear {Fuel} {Cycle} {Codes} and {Applications}}, title = {{GENIUSv2} {Recipe} {Approximation} {Methodology} for {Mixed}-{Oxide} {Fuel}}, volume = {101}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, author = {Elmore, R. A and Oliver, K. M and Wilson, P. P.H and Ahn, Tae Wook and Dunn, Kerry L. and Huff, Kathryn D.}, month = nov, year = {2009}, keywords = {Code, Mixed-Oxide Fuel (MOX), GENIUS (Global Evaluation of Nuclear Infrastrucutre Utilization Scenarios), Nuclear Fuel Cycle Facilities, C++, Simulation Institute for Nuclear Enterprise Modeling and Analysis (SINEMA)}, pages = {241--242}, file = {2009_11_Elmore_ANS2009Winter_Genius.pdf:/Users/huff/Zotero/storage/SPK8GUTS/2009_11_Elmore_ANS2009Winter_Genius.pdf:application/pdf;2009_11_Elmore-ANS2009Winter_Genius.doc:/Users/huff/Zotero/storage/7G53PPN8/2009_11_Elmore-ANS2009Winter_Genius.doc:application/msword} } - Huff, Kathryn D., K. M Oliver, P. P.H Wilson, Tae W. Ahn, K. Dunn, and R. Elmore. 2009. “GENIUSv2 Discrete Facilities/Materials Modeling of International Fuel Cycle Robustness.” In Transactions of the American Nuclear Society, 101:239–40. Nuclear Fuel Cycle Codes and Applications. Washington D.C., United States: American Nuclear Society.
The GENIUS project (Global Evaluation of Nuclear Infrastructure Utilization Scenarios) was conceived as the top-level nuclear enterprise simulation tool in the Simulation Institute for Nuclear Enterprise Modeling and Analysis (SINEMA) framework 1 . The current version, GENIUSv2, is an object-oriented C++ application with Python-based pre- and post-processing. The GENIUSv2 fuel cycle tool proposes to inform nuclear fuel cycle technology and policy by providing a richly detailed, modular platform capable of dynamically modeling inter-regional and inter-institutional relationships and incorporating user-defined, facility specific technologies. Here we present results from the GENIUSv2 testing suite demonstrating the detailed, robust and modular nature of its modeling capability and computational methodology.
@inproceedings{huff_geniusv2_2009, address = {Washington D.C., United States}, series = {Nuclear {Fuel} {Cycle} {Codes} and {Applications}}, title = {{GENIUSv2} {Discrete} {Facilities}/{Materials} {Modeling} of {International} {Fuel} {Cycle} {Robustness}}, volume = {101}, booktitle = {Transactions of the {American} {Nuclear} {Society}}, publisher = {American Nuclear Society}, author = {Huff, Kathryn D. and Oliver, K. M and Wilson, P. P.H and Ahn, Tae W. and Dunn, K. and Elmore, R.}, month = nov, year = {2009}, keywords = {Geniusv2, Simulation, Code, Technology, C++, Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS), Fuel cycle}, pages = {239--240}, file = {2009_11_Huff-ANS2009Winter_Genius.doc:/Users/huff/Zotero/storage/BD4FSDRE/2009_11_Huff-ANS2009Winter_Genius.doc:application/msword;2009_11_Huff_ANS2009Winter_Genius.pdf:/Users/huff/Zotero/storage/2CEI63AX/2009_11_Huff_ANS2009Winter_Genius.pdf:application/pdf} } - Huff, Kathryn D., Paul P.H. Wilson, and Kyle M. Oliver. 2009. “GENIUS Version 2: Modeling the Worldwide Nuclear Fuel Cycle (Poster).” In Proceedings of the EHub Conference. University of Wisconsin, Madison.
@inproceedings{huff_genius_2009, address = {University of Wisconsin, Madison}, title = {{GENIUS} {Version} 2: {Modeling} the {Worldwide} {Nuclear} {Fuel} {Cycle} (poster)}, booktitle = {Proceedings of the {eHub} {Conference}}, author = {Huff, Kathryn D. and Wilson, Paul P.H. and Oliver, Kyle M.}, month = nov, year = {2009} } - Mujica, Nicolas, Marcel Clerc, Patricio Cordero, Jocelyn Dunstan, Kathryn D. Huff, Loreto Oyarte, Rodrigo Soto, German Varas, and Dino Risso. 2008. “Solid-Liquid-like Transition in Vibrated Granular Monolayers.” In APS Division of Fluid Dynamics Meeting Abstracts. http://adsabs.harvard.edu/abs/2008APS..DFD.HM008M.
The theory of non-ideal gases in thermodynamic equilibrium, for instance the van der Waals gas model, has played a central role in the understanding of coexisting phases. Here, we report a combined experimental, numerical and theoretical study of a liquid-solid-like phase transition which takes place in a vertically vibrated fluidized granular monolayer. The first experimental setup is a long, narrow channel, with a width of the order of a few particle diameters, hence the dynamics is quasi-one-dimensional. We have considered this configuration to characterize the dynamic behavior of the phase transition. The second setup is used to measure the pressure as function of particle density in order to clarify the physical mechanism behind this phase transition. We demonstrate that the transition is mediated by waves and that it is triggered by a negative compressibility as in van der Waals phase coexistence, although the system does not satisfy the hypotheses used to understand atomic systems. Finally, in order to further characterize this phase transition, we study static and dynamic correlation functions, and bond-orientational order parameters.
@inproceedings{mujica_solid-liquid-like_2008, title = {Solid-liquid-like transition in vibrated granular monolayers}, url = {http://adsabs.harvard.edu/abs/2008APS..DFD.HM008M}, language = {en}, urldate = {2014-10-10}, booktitle = {{APS} {Division} of {Fluid} {Dynamics} {Meeting} {Abstracts}}, author = {Mujica, Nicolas and Clerc, Marcel and Cordero, Patricio and Dunstan, Jocelyn and Huff, Kathryn D. and Oyarte, Loreto and Soto, Rodrigo and Varas, German and Risso, Dino}, month = nov, year = {2008}, keywords = {KHuff}, file = {Solid-liquid-like transition in vibrated granular monolayers:/Users/huff/Zotero/storage/WUM5GTPK/2008APS..DFD.html:text/html;Snapshot:/Users/huff/Zotero/storage/4GI7D9UA/2008APS..DFD.html:text/html} } - Rochman, D., R. C. Haight, S. A. Wender, J. M. O’Donnell, A. Michaudon, Kathryn D. Huff, D. J. Vieira, et al. 2005. “First Measurements with a Lead Slowing-Down Spectrometer at LANSCE.” In Proceedings of the International Conference on Nuclear Data for Science and Technology, 769:736–39. https://doi.org/10.1063/1.1945112.
The characteristics of a Lead Slowing-Down Spectrometer (LSDS) installed at the Los Alamos Neutron Science Center (LANSCE) are presented in this paper. This instrument is designed to study neutron-induced fission on ultra small quantities of actinides, on the order of tens of nanograms or less. The measurements of the energy-time relation, energy resolution and neutron flux are compared to simulations performed with MCNPX. Results on neutron-induced fission of 235U and 239Pu with tens of micrograms and tens of nanograms, respectively, are presented. Finally, a digital filter designed to improve the detection of fission events at short time after the proton pulses is described.
@inproceedings{rochman_first_2005, title = {First {Measurements} with a {Lead} {Slowing}-{Down} {Spectrometer} at {LANSCE}}, volume = {769}, isbn = {0094-243X}, url = {http://adsabs.harvard.edu/abs/2005AIPC..769..736R}, doi = {10.1063/1.1945112}, urldate = {2014-10-10}, booktitle = {Proceedings of the {International} {Conference} on {Nuclear} {Data} for {Science} and {Technology}}, author = {Rochman, D. and Haight, R. C. and Wender, S. A. and O'Donnell, J. M. and Michaudon, A. and Huff, Kathryn D. and Vieira, D. J. and Bond, E. and Rundberg, R. S. and Kronenberg, A. and Wilhelmy, J. and Bredeweg, T. A. and Schwantes, J. and Ethvignot, T. and Granier, T. and Petit, M. and Danon, Y.}, month = may, year = {2005}, keywords = {=A, 220{\textless}, Neutron-induced fission, Nucleon-induced reactions, Spectrometers and spectroscopic techniques}, pages = {736--739} }
In The News
- Letzter, Rafi. 2019. “When Chernobyl Blew, They Dumped Boron and Sand into the Breach. What Would We Do Today?” Live Science, May. https://www.livescience.com/65515-chernobyl-in-modern-times-nuclear-emergency.html.
In 1986, the Soviets dumped sand and boron from helicopters onto the exposed Chernobyl uranium core. How would we handle it today?
@article{letzter_when_2019, chapter = {Planet Earth}, title = {When {Chernobyl} {Blew}, {They} {Dumped} {Boron} and {Sand} into the {Breach}. {What} {Would} {We} {Do} {Today}?}, url = {https://www.livescience.com/65515-chernobyl-in-modern-times-nuclear-emergency.html}, urldate = {2019-05-22}, journal = {Live Science}, author = {Letzter, Rafi}, month = may, year = {2019}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/GQFHICX8/65515-chernobyl-in-modern-times-nuclear-emergency.html:text/html} } - Kugelmass, Bret. 2019. “Katy Huff, University of Illinois on Apple Podcasts.” Titans Of Nuclear \Textbar Interviewing World Experts on Nuclear Energy. Urbana, IL: Apple Podcasts. https://www.titansofnuclear.com/katyhuff.
?Show Titans Of Nuclear \textbar Interviewing World Experts on Nuclear Energy, Ep Ep. 145 - Katy Huff, University of Illinois - Apr 10, 2019
@misc{kugelmass_katy_2019, address = {Urbana, IL}, title = {Katy {Huff}, {University} of {Illinois} on {Apple} {Podcasts}}, shorttitle = {?{Titans} {Of} {Nuclear} {\textbar} {Interviewing} {World} {Experts} on {Nuclear} {Energy}}, url = {https://www.titansofnuclear.com/katyhuff}, language = {en-us}, urldate = {2019-04-12}, journal = {Titans Of Nuclear {\textbar} Interviewing World Experts on Nuclear Energy}, publisher = {Apple Podcasts}, author = {Kugelmass, Bret}, collaborator = {Huff, Kathryn D.}, month = apr, year = {2019}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/D2I87WZJ/id1331598443.html:text/html} } - Hu, Jane C. 2019. “Someday the U.S. Will Have to Actually Deal With Its Nuclear Waste Problem.” Slate Magazine Technology (June). https://slate.com/technology/2019/06/department-of-energy-nuclear-waste-reclassification-yucca.html.
The lack of solution is not from lack of discussion. There have been all sorts of wacky ideas floated about where to store nuclear waste.
@article{hu_someday_2019, title = {Someday the {U}.{S}. {Will} {Have} to {Actually} {Deal} {With} {Its} {Nuclear} {Waste} {Problem}}, volume = {Technology}, shorttitle = {Someday the {U}.{S}. {Will} {Have} to {Actually} {Deal} {With} {Its} {Nuclear} {Waste} {Problem}. {The} {Department} of {Energy} has made a move in that direction.}, url = {https://slate.com/technology/2019/06/department-of-energy-nuclear-waste-reclassification-yucca.html}, language = {en}, urldate = {2019-06-09}, journal = {Slate Magazine}, author = {Hu, Jane C.}, month = jun, year = {2019}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/PD4VLBYM/department-of-energy-nuclear-waste-reclassification-yucca.html:text/html} } - Anghel, Diana. 2019. “Krannert Exhibit Raises Awareness of Nuclear Industry.” Campus Newspaper. The Daily Illini. https://dailyillini.com/news/2019/10/24/krannert-nuclear-industry/.
The Krannert Art Museum opened the “Hot Spots: Radioactivity and the Landscape” exhibit on Thursday, taking on the role of bringing attention to the damage done by the nuclear industry on indigenous lands and posing questions of long-term plans for the future. First seen at the University at Buffalo, the exhibit was created for the...
@misc{anghel_krannert_2019, type = {Campus {Newspaper}}, title = {Krannert exhibit raises awareness of nuclear industry}, url = {https://dailyillini.com/news/2019/10/24/krannert-nuclear-industry/}, language = {en, sv}, urldate = {2019-10-25}, journal = {The Daily Illini}, author = {Anghel, Diana}, collaborator = {Huff, Kathryn}, month = oct, year = {2019}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/V3ZLJIZL/krannert-nuclear-industry.html:text/html} } - Huff, Kathryn. 2018. “Creating a Carbon Free Future, Alumni Spotlight: Kathryn Huff, Ph.D.” http://tams.unt.edu/alumni/spotlights/kathryn-huff-phd.
@misc{huff_creating_2018, title = {Creating a {Carbon} {Free} {Future}, {Alumni} {Spotlight}: {Kathryn} {Huff}, {Ph}.{D}.}, shorttitle = {Alumni {Spotlight}: {Kathryn} {Huff}, {Ph}.{D}.}, url = {http://tams.unt.edu/alumni/spotlights/kathryn-huff-phd}, language = {English}, urldate = {2018-09-04}, author = {Huff, Kathryn}, collaborator = {Holland, Miranda}, month = aug, year = {2018}, note = {media}, file = {Kathryn Huff, Ph.D. | Texas Academy of Mathematics & Science:/Users/huff/Zotero/storage/86PFLTUC/kathryn-huff-phd.html:text/html} } - Timmins, Mary. 2018. “Power Source: Nuclear Engineer Katy Huff on Teaching with IPython, Reactor Theory and the Future of Energy.” University of Illinois Alumni Magazine [InClass] Engineering (Summer 2018): 13. https://illinoisalumni.org/2018/08/01/in-class-power-source/.
Nuclear engineer Katy Huff on teaching with IPython, reactor theory and the future of energy.
@article{timmins_power_2018, title = {Power {Source}: {Nuclear} engineer {Katy} {Huff} on teaching with {IPython}, reactor theory and the future of energy}, volume = {[InClass] Engineering}, shorttitle = {Power {Source}}, url = {https://illinoisalumni.org/2018/08/01/in-class-power-source/}, language = {Engilish}, number = {Summer 2018}, journal = {University of Illinois Alumni Magazine}, author = {Timmins, Mary}, collaborator = {Huff, Kathryn}, month = aug, year = {2018}, note = {media}, pages = {13}, file = {Timmins - 2018 - Power Source Nuclear engineer Katy Huff on teachi.pdf:/Users/huff/Zotero/storage/4DFG69KU/Timmins - 2018 - Power Source Nuclear engineer Katy Huff on teachi.pdf:application/pdf} } - Larsen, Holly. 2018. “California Faculty Field Day.” Sandia National Laboratory LabNews, July, 8. http://www.sandia.gov/news/publications/labnews/_assets/documents/issues/2018/labnews07-06-18.pdf.
@article{larsen_california_2018, title = {California {Faculty} {Field} {Day}}, url = {http://www.sandia.gov/news/publications/labnews/_assets/documents/issues/2018/labnews07-06-18.pdf}, language = {en}, journal = {Sandia National Laboratory LabNews}, author = {Larsen, Holly}, month = jul, year = {2018}, note = {media}, pages = {8}, file = {Rappe - Sandia light mixer makes 11 colors at once.pdf:/Users/huff/Zotero/storage/22V6J6WR/Rappe - Sandia light mixer makes 11 colors at once.pdf:application/pdf} } - Silver, Andrew. 2018. “Microsoft’s Purchase of GitHub Leaves Some Scientists Uneasy.” Nature, In Focus, 558 (June): 353. https://doi.org/doi: 10.1038/d41586-018-05426-0.
They fear the data-sharing website will become less open, but other researchers say the buyout could make GitHub more useful.
@article{silver_microsofts_2018, series = {In {Focus}}, title = {Microsoft{\textquoteright}s purchase of {GitHub} leaves some scientists uneasy}, volume = {558}, copyright = {2018 Nature}, shorttitle = {They fear the online platform will become less open, but other researchers say the buyout could make {GitHub} more useful.}, url = {http://www.nature.com/articles/d41586-018-05426-0}, doi = {doi: 10.1038/d41586-018-05426-0}, language = {EN}, urldate = {2018-07-06}, journal = {Nature}, author = {Silver, Andrew}, month = jun, year = {2018}, note = {media}, pages = {353}, file = {Snapshot:/Users/huff/Zotero/storage/ZXWE55CU/d41586-018-05426-0.html:text/html} } - Bowne-Anderson, Hugo. 2018. “Data Science, Nuclear Engineering and the Open Source (with Katy Huff).” Data Framed. New York, NY, USA: Data Camp. https://www.datacamp.com/community/podcast/data-science-nuclear-engineering.
Nuclear engineering, data science and open source software development: where do these all intersect? To find out, join Hugo and Katy Huff, Assistant Professor in the Department of Nuclear, Plasma, an
@misc{bowne-anderson_data_2018, address = {New York, NY, USA}, title = {Data {Science}, {Nuclear} {Engineering} and the {Open} {Source} (with {Katy} {Huff})}, copyright = {DataCamp}, shorttitle = {Data science, nuclear engineering, the importance of interdisciplinary data science and the open source.}, url = {https://www.datacamp.com/community/podcast/data-science-nuclear-engineering}, language = {en}, urldate = {2018-07-06}, journal = {Data Framed}, publisher = {Data Camp}, author = {Bowne-Anderson, Hugo}, collaborator = {Huff, Kathryn D.}, month = mar, year = {2018}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/25KJVGHT/12-data-science-nuclear-engineering-and-the-open-source.html:text/html} } - Mumm, Susan. 2018. “Professor Kathryn Huff on the Possibilities in NPRE.” Urbana, IL: Illinois Engineering. https://www.youtube.com/watch?v=w9d_QMW1hA4.
Assistant Professor in Nuclear, Plasma, and Radiological Engineering talks about students in NPRE and the opportunities that the major has to offer.
@misc{mumm_professor_2018, address = {Urbana, IL}, title = {Professor {Kathryn} {Huff} on the {Possibilities} in {NPRE}}, url = {https://www.youtube.com/watch?v=w9d_QMW1hA4}, urldate = {2018-07-06}, publisher = {Illinois Engineering}, author = {Mumm, Susan}, collaborator = {{Illinois Engineering} and Huff, Kathryn D.}, month = mar, year = {2018}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/PLZD3J8V/watch.html:text/html} } - ———. 2018. “NPRE Researchers to Investigate Load-Following Capabilities for Molten Salt Reactors \Textbar NPRE Illinois.” University. Nuclear, Plasma, and Radiological Engineering News. https://npre.illinois.edu/news/npre-researchers-investigate-load-following-capabilities-molten-salt-reactors.
A team of researchers from Nuclear, Plasma, and Radiological Engineering at the University of Illinois at Urbana-Champaign are examining ways to enable this load-following capability. The scientists are conducting simulations to determine how to remove unwanted fission by-products that slow reaction rates and, thus, energy production.
@misc{mumm_npre_2018, type = {University}, title = {{NPRE} researchers to investigate load-following capabilities for molten salt reactors {\textbar} {NPRE} {Illinois}}, url = {https://npre.illinois.edu/news/npre-researchers-investigate-load-following-capabilities-molten-salt-reactors}, urldate = {2018-10-30}, journal = {Nuclear, Plasma, and Radiological Engineering News}, author = {Mumm, Susan}, month = jun, year = {2018}, note = {media}, file = {NPRE researchers to investigate load-following capabilities for molten salt reactors | NPRE Illinois:/Users/huff/Zotero/storage/8CE8KI6V/npre-researchers-investigate-load-following-capabilities-molten-salt-reactors.html:text/html} } - Hawksworth, Scott. 2018. “Nuclear Engineering Programs with Dr. Kathryn Huff.” Yes College Podcast. Chicago, IL, United States: YesCollege.com. https://yescollege.com/episode/kathryn-huff/.
On this week’s show, we dive into the sciences and explore the exciting field of nuclear engineering! Scott was joined by Dr. Kathryn Huff, Assistant Professor in the Department of Nuclear, Plasma and Radiological Engineering and a Blue Waters Assistant Professor with the National Center for Supercomputing Applications at the University of Illinois at Urbana-Champaign. \textellipsis
@misc{hawksworth_nuclear_2018, address = {Chicago, IL, United States}, title = {Nuclear {Engineering} {Programs} with {Dr}. {Kathryn} {Huff}}, copyright = {YesCollege}, shorttitle = {Ep 17}, url = {https://yescollege.com/episode/kathryn-huff/}, language = {en-US}, urldate = {2018-07-06}, journal = {Yes College Podcast}, publisher = {YesCollege.com}, author = {Hawksworth, Scott}, collaborator = {Huff, Kathryn D.}, month = feb, year = {2018}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/ADXW3UJH/kathryn-huff.html:text/html} } - Perkel, Jeffrey. 2016. “Democratic Databases: Science on GitHub.” Nature News, Toolbox, 538 (7623): 127. https://doi.org/10.1038/538127a.
Scientists are turning to a software–development site to share data and code.
@article{perkel_democratic_2016, series = {Toolbox}, title = {Democratic databases: science on {GitHub}}, volume = {538}, issn = {0028-0836}, shorttitle = {Democratic databases}, url = {http://www.nature.com/news/democratic-databases-science-on-github-1.20719}, doi = {10.1038/538127a}, language = {en}, number = {7623}, urldate = {2018-07-06}, journal = {Nature News}, author = {Perkel, Jeffrey}, month = oct, year = {2016}, note = {media}, pages = {127}, file = {Snapshot:/Users/huff/Zotero/storage/GQPEKFL2/democratic-databases-science-on-github-1.html:text/html} } - Lowery, Jack. 2015. “Women in Data Science: Kathryn Huff.” NYU Center for Data Science. https://cds.nyu.edu/women-data-science-kathryn-huff/.
As part of the Moore-Sloan Data Science Initiative’s ongoing commitment to promoting diversity, we are highlighting the work of 5 exceptional women in the field of data science. The first profile in our series is on Katy Huff, a Berkeley Institute for Data Science, Moore/Sloan fellow. Nuclear power is a highly controversial topic within the \textellipsis
@misc{lowery_women_2015, title = {Women in {Data} {Science}: {Kathryn} {Huff}}, shorttitle = {Women in {Data} {Science}}, url = {https://cds.nyu.edu/women-data-science-kathryn-huff/}, language = {en-US}, urldate = {2018-07-25}, journal = {NYU Center for Data Science}, author = {Lowery, Jack}, month = sep, year = {2015}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/WD4GLQ98/women-data-science-kathryn-huff.html:text/html} } - Tippmann, Sylvia. 2014. “My Digital Toolbox: Nuclear Engineer Katy Huff on Version-Control Systems.” Nature News, Toolbox: Q&A, , September. https://doi.org/10.1038/nature.2014.16014.
Git and GitHub are the ’laboratory notebook of scientific computing’.
@article{tippmann_my_2014, series = {Toolbox: {Q}\&{A}}, title = {My digital toolbox: {Nuclear} engineer {Katy} {Huff} on version-control systems}, issn = {0028-0836}, shorttitle = {My digital toolbox}, url = {http://www.nature.com/news/my-digital-toolbox-nuclear-engineer-katy-huff-on-version-control-systems-1.16014}, doi = {10.1038/nature.2014.16014}, language = {en}, urldate = {2018-07-06}, journal = {Nature News}, author = {Tippmann, Sylvia}, month = sep, year = {2014}, note = {media}, file = {Snapshot:/Users/huff/Zotero/storage/4QXP8EIT/my-digital-toolbox-nuclear-engineer-katy-huff-on-version-control-systems-1.html:text/html} }