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Research Output 2008 2020

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Conference article
2018

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

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

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

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

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

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
2013

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

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

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