If you made any changes in Pure, your changes will be visible here soon.

Research Output 2008 2020

2020

Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator

Bae, J. W., Rykhlevskii, A., Chee, G. & Huff, K. D., May 2020, In : Annals of Nuclear Energy. 139, 107230.

Research output: Contribution to journalArticle

Nuclear fuels
Simulators
Pressurized water reactors
Neural networks
Deep learning
2019

Fuel cycle performance of fast spectrum molten salt reactor designs

Rykhlevskii, A., Betzler, B. R., Worrall, A. & Huff, K., Jan 1 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, p. 342-353 12 p. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Salt
Reactor
Cycle
Unit
Cell

Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor

Rykhlevskii, A., Bae, J. W. & Huff, K. D., Jun 2019, In : Annals of Nuclear Energy. 128, p. 366-379 14 p.

Research output: Contribution to journalArticle

Breeder reactors
Thorium
Molten materials
Salts
Nuclear fuel reprocessing

Standardized verification of the CYCLUS fuel cycle simulator

Bae, J. W., Peterson-Droogh, J. L. & Huff, K. D., Jun 2019, In : Annals of Nuclear Energy. 128, p. 288-291 4 p.

Research output: Contribution to journalArticle

Nuclear fuels
Simulators
Specifications

Synergistic spent nuclear fuel dynamics within the European Union

Bae, J. W., Singer, C. E. & Huff, K. D., Jul 2019, In : Progress in Nuclear Energy. 114, p. 1-12 12 p.

Research output: Contribution to journalArticle

Fast reactors
Spent fuels
Nuclear fuels
European Union
Sodium

Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)

Ashraf, O., Rykhlevskii, A., Tikhomirov, G. V. & Huff, K. D., Jan 1 2019, (Accepted/In press) In : Annals of Nuclear Energy. 107115.

Research output: Contribution to journalArticle

Core analysis
Thorium
Fluids
Reactor operation
Criticality (nuclear fission)
2018
machine learning
Gamma rays
Learning systems
Spectroscopy
gamma rays

Introduction to Moltres: An application for simulation of Molten Salt Reactors

Lindsay, A., Ridley, G., Rykhlevskii, A. & Huff, K., Apr 2018, In : Annals of Nuclear Energy. 114, p. 530-540 11 p.

Research output: Contribution to journalArticle

Physics
Hydraulic models
Neutrons
Fluids
Experiments

Journal of Open Source Software (JOSS): Design and first-year review

Smith, A. M., Niemeyer, K. E., Katz, D. S., Barba, L. A., Githinji, G., Gymrek, M., Huff, K. D., Madan, C. R., Mayes, A. C., Moerman, K. M., Prins, P., Ram, K., Rokem, A., Teal, T. K., Guimera, R. V. & Vanderplas, J. T., Feb 12 2018, In : PeerJ Computer Science. 2018, 2, e147.

Research output: Contribution to journalArticle

Software design
Open source software
Metadata
Deposits

Pyre: A cyclus pyroprocessing facility archetype

Westphal, G. T. & Huff, K. D., Jan 1 2018, p. 73-76. 4 p.

Research output: Contribution to conferencePaper

Throughput
Flowcharting

Validation of spent nuclear fuel output by CYCLUS, a fuel cycle simulator code

Chee, G. J., Park, G. & Huff, K. D., Jan 1 2018, In : Transactions of the American Nuclear Society. 119, p. 219-222 4 p.

Research output: Contribution to journalConference article

Spent fuels
Nuclear fuels
Simulators
2017

Benefits of siting a borehole repository on non-operating nuclear facility

Bae, J. W., Roy, W. & Huff, K., Jan 1 2017, ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal. American Nuclear Society, p. 876-883 8 p. (ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

repository
borehole
power plant
nuclear power plant
viability

Developing an open, modular simulation framework for nuclear fuel cycle analysis

Huff, K., Oct 17 2017, The Practice of Reproducible Research: Case Studies and Lessons from the Data-Intensive Sciences. University of California Press, p. 285-290 6 p.

Research output: Chapter in Book/Report/Conference proceedingChapter

simulation
analysis
nuclear fuel

Full-core analysis of thorium-fueled molten salt breeder reactor using the SERPENT 2 Monte Carlo code

Rykhlevskii, A., Lindsay, A. & Huff, K. D., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 1343-1346 4 p.

Research output: Contribution to journalConference article

Core analysis
Breeder reactors
Thorium
Molten materials
Salts

Lessons learned

Huff, K., Oct 17 2017, The Practice of Reproducible Research: Case Studies and Lessons from the Data-Intensive Sciences. University of California Press, p. 41-60 20 p.

Research output: Chapter in Book/Report/Conference proceedingChapter

Online reprocessing simulation fot thorium-fueled molten salt breeder reactor

Rykhlevskii, A., Lindsay, A. & Huff, K. D., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 239-242 4 p.

Research output: Contribution to journalConference article

Breeder reactors
Thorium
Molten materials
Salts

Rapid methods for radionuclide contaminant transport in nuclear fuel cycle simulation

Huff, K. D., Dec 2017, In : Advances in Engineering Software. 114, p. 268-281 14 p.

Research output: Contribution to journalArticle

Nuclear fuels
Radioisotopes
Impurities
Simulators
Radioactive wastes

Synergistic spent nuclear fuel dynamics within the European union

Bae, J. W., Huff, K. D. & Singer, C. E., Jan 1 2017, In : Transactions of the American Nuclear Society. 117, p. 261-265 5 p.

Research output: Contribution to journalConference article

Light water reactors
Fast reactors
Spent fuels
Nuclear fuels
Sodium
2016

A sensitivity study of a coupled kinetics and thermal-hydraulics model for fluoride-salt-cooled, high-Temperature reactor (FHR) transient analysis

Wang, X., Huff, K. D., Aufiero, M., Peterson, P. F. & Fratoni, M., Jan 1 2016, International Congress on Advances in Nuclear Power Plants, ICAPP 2016. American Nuclear Society, p. 399-406 8 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2016; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Hydraulic models
Transient analysis
Salts
Kinetics

Coupled reactor kinetics and heat transfer model for fluoride salt-cooled high-temperature reactor transient analysis

Wang, X., Huff, K. D., Aufiero, M., Peterson, P. F. & Fratoni, M., Jan 1 2016, Student Paper Competition. American Society of Mechanical Engineers (ASME), V005T15A055. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 5).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Transient analysis
Neutrons
Salts
Heat transfer

Design summary of the Mark-I pebble-bed, fluoride salt-cooled, high-temperature reactor commercial power plant

Andreades, C., Cisneros, A. T., Choi, J. K., Chong, A. Y. K., Fratoni, M., Hong, S., Huddar, L. R., Huff, K. D., Kendrick, J., Krumwiede, D. L., Laufer, M. R., Munk, M., Scarlat, R. O., Zweibaum, N., Greenspan, E., Wang, X. & Peterson, P., Sep 2016, In : Nuclear Technology. 195, 3, p. 223-238 16 p.

Research output: Contribution to journalArticle

High temperature reactors
power plants
fluorides
beds
Power plants

Fundamental concepts in the Cyclus nuclear fuel cycle simulation framework

Huff, K. D., Gidden, M. J., Carlsen, R. W., Flanagan, R. R., McGarry, M. B., Opotowsky, A. C., Schneider, E. A., Scopatz, A. M. & Wilson, P. P. H., Apr 2016, In : Advances in Engineering Software. 94, p. 46-59 14 p.

Research output: Contribution to journalArticle

Nuclear fuels
Simulators
Ecosystems
Software architecture
Nuclear energy

Lightning talk: "I solemnly pledge" A manifesto for personal responsibility in the engineering of academic software

Allen, A., Aragon, C., Becker, C., Carver, J. C., Chis, A., Combemale, B., Croucher, M., Crowston, K., Garijo, D., Gehani, A., Goble, C., Haines, R., Hirschfeld, R., Howison, J., Huff, K., Jay, C., Katz, D. S., Kirchner, C., Kuksenok, K., Lämmel, R. & 5 others, Nierstrasz, O., Turk, M., Van Nieuwpoort, R. V., Vaughn, M. & Vinju, J., Jan 1 2016, In : CEUR Workshop Proceedings. 1686

Research output: Contribution to journalConference article

Lightning
Feedback
2015

Modernizing computational nuclear engineering education in the open

Huff, K. D. & Scopatz, A. M., Jan 1 2015, In : Transactions of the American Nuclear Society. 113, p. 111-114 4 p.

Research output: Contribution to journalConference article

Nuclear engineering
Engineering education
2014

Best Practices for Scientific Computing

Wilson, G., Aruliah, D. A., Brown, C. T., Chue Hong, N. P., Davis, M., Guy, R. T., Haddock, S. H. D., Huff, K. D., Mitchell, I. M., Plumbley, M. D., Waugh, B., White, E. P. & Wilson, P., Jan 2014, In : PLoS biology. 12, 1, e1001745.

Research output: Contribution to journalArticle

Natural sciences computing

Design of the Mark-I pebble-bed, fluoride-salt-cooled, high-temperature reactor commercial power plant

Krumwiede, D. L., Andreades, C., Choi, J. K., Cisneros, A. T., Huddar, L., Huff, K. D., Laufer, M. R., Munk, M., Scarlat, R. O., Seiffied, J. E., Zweibaum, N., Greenspan, E. & Peterson, P. F., Jan 1 2014, International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, p. 413-422 10 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Power plants
Salts
Coolants
Computer aided design

Extensions to the cyclus ecosystem in support of market-driven transition capability LLNL-PROC-656426

Huff, K. D., Fratoni, M. & Greenberg, H. R., Jan 1 2014, In : Transactions of the American Nuclear Society. 111, p. 245-248 4 p.

Research output: Contribution to journalConference article

Ecosystems

PyNE progress report

Bates, C. R., Biondo, E., Huff, K. D., Kiesling, K., Scopatz, A., Carlsen, R., Davis, A., Gidden, M., Haines, T., Howland, J., Huff, B., Manalo, K., Opotowsky, A., Slaybaugh, R., Relson, E., Romano, P., Shriwise, P., Xia, J. D., Wilson, P. & Zachman, J., 2014, In : Transactions of the American Nuclear Society. 111, p. 1165-1168 4 p.

Research output: Contribution to journalArticle

2013

An agent-based framework for fuel cycle simulation with recycling

Gidden, M. J., Wilson, P. P. H., Huff, K. D. & Carlsen, R. W., Jan 1 2013, p. 1425-1436. 12 p.

Research output: Contribution to conferencePaper

Recycling
Mathematical programming
Nuclear fuels
Dynamical systems
Simulators

Cyclus fuel cycle simulation capabilities with the cyder disposal system model

Huff, K. D., Jan 1 2013, p. 1276-1283. 8 p.

Research output: Contribution to conferencePaper

Dynamic determination of thermal repository capacity for fuel cycle analysis

Huff, K. D. & Bara, A. T., Jan 1 2013, In : Transactions of the American Nuclear Society. 108, p. 123-126 4 p.

Research output: Contribution to journalConference article

Hot Temperature
2012

Key processes and parameters in a generic clay disposal system model

Huff, K. D. & Nutt, W. M., Dec 1 2012, In : Transactions of the American Nuclear Society. 107, p. 208-211 4 p.

Research output: Contribution to journalConference article

Clay

Numerical calibration of an analytical generic nuclear repository heat transfer model

Huff, K. D. & Bauer, T. H., Dec 1 2012, In : Transactions of the American Nuclear Society. 106, p. 260-263 4 p.

Research output: Contribution to journalConference article

Calibration
Heat transfer

Once-through benchmarks with CYCLUS, a modular, open-source fuel cycle simulator

Gidden, M. J., Wilson, P. P. H., Huff, K. D. & Carlsen, R. W., 2012, In : Transactions of the American Nuclear Society. 107, p. 264-266 3 p.

Research output: Contribution to journalArticle

Simulators

PyNE: Python for nuclear engineering

Scopatz, A. M., Romano, P. K., Wilson, P. P. H. & Huff, K. D., Dec 1 2012, In : Transactions of the American Nuclear Society. 107, p. 985-987 3 p.

Research output: Contribution to journalConference article

Nuclear engineering
2011

Open architecture and modular paradigm of CYCLUS , a fuel cycle simulation code

Huff, K. D., Wilson, P. P. H. & Gidden, M. J., 2011, In : Transactions of the American Nuclear Society. 104, p. 183-184 2 p.

Research output: Contribution to journalArticle

Rapid peer education of a computational nuclear engineering skill suite

Huff, K. D., Scopatz, A. M., Preston, N. D. & Wilson, P. P. H., Dec 1 2011, In : Transactions of the American Nuclear Society. 104, p. 103-104 2 p.

Research output: Contribution to journalConference article

Nuclear engineering
Education
2009

GENIUSv2 discrete facilities/materials modeling of international fuel cycle robustness

Huff, K. D., Oliver, K. M., Wilson, P. P. H., Ahn, T. W., Dunn, K. & Elmore, R., Dec 1 2009, In : Transactions of the American Nuclear Society. 101, p. 239-240 2 p.

Research output: Contribution to journalConference article

GENIUSv2 recipe approximation methodology for mixed-oxide fuel

Elmore, R. A., Oliver, K. M., Wilson, P. P. H., Ahn, T. W., Dunn, K. & Huff, K., Dec 1 2009, In : Transactions of the American Nuclear Society. 101, p. 241-242 2 p.

Research output: Contribution to journalConference article

Mixed oxide fuels
2008

Liquid-solid-like transition in quasi-one-dimensional driven granular media

Clerc, M. G., Cordero, P., Dunstan, J., Huff, K., Mujica, N., Risso, D. & Varas, G., Mar 2008, In : Nature Physics. 4, 3, p. 249-254 6 p.

Research output: Contribution to journalArticle

liquids
fluids
coagulation
thermodynamic equilibrium
gases