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Jason Hales
Tytuł
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Multidimensional multiphysics simulation of nuclear fuel behavior
RL Williamson, JD Hales, SR Novascone, MR Tonks, DR Gaston, ...
Journal of Nuclear Materials 423 (1-3), 149-163, 2012
7042012
BISON theory manual the equations behind nuclear fuel analysis
JD Hales, RL Williamson, SR Novascone, G Pastore, BW Spencer, ...
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016
2582016
BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms
RL Williamson, JD Hales, SR Novascone, G Pastore, KA Gamble, ...
Nuclear Technology 207 (7), 954-980, 2021
2132021
2.0-MOOSE: Enabling massively parallel multiphysics simulation
AD Lindsay, DR Gaston, CJ Permann, JM Miller, D Andrš, AE Slaughter, ...
SoftwareX 20, 101202, 2022
1942022
Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling
G Pastore, LP Swiler, JD Hales, SR Novascone, DM Perez, BW Spencer, ...
Journal of Nuclear Materials 456, 398-408, 2015
1902015
Multidimensional multiphysics simulation of TRISO particle fuel
JD Hales, RL Williamson, SR Novascone, DM Perez, BW Spencer, ...
Journal of Nuclear Materials 443 (1-3), 531-543, 2013
1792013
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
KA Gamble, T Barani, D Pizzocri, JD Hales, KA Terrani, G Pastore
Journal of nuclear materials 491, 55-66, 2017
1572017
Validating the BISON fuel performance code to integral LWR experiments
RL Williamson, KA Gamble, DM Perez, SR Novascone, G Pastore, ...
Nuclear Engineering and Design 301, 232-244, 2016
1492016
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions
X Wu, T Kozlowski, JD Hales
Annals of Nuclear Energy 85, 763-775, 2015
1452015
A review of fuel performance modelling
P Van Uffelen, J Hales, W Li, G Rossiter, R Williamson
Journal of Nuclear Materials 516, 373-412, 2019
1192019
Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings
M Wagih, B Spencer, J Hales, K Shirvan
Annals of Nuclear Energy 120, 304-318, 2018
1162018
Verification of the BISON fuel performance code
JD Hales, SR Novascone, BW Spencer, RL Williamson, G Pastore, ...
Annals of Nuclear Energy 71, 81-90, 2014
1162014
Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding
O Courty, AT Motta, JD Hales
Journal of Nuclear Materials 452 (1-3), 311-320, 2014
1112014
Multiscale modeling of thermal conductivity of high burnup structures in UO2 fuels
XM Bai, MR Tonks, Y Zhang, JD Hales
Journal of Nuclear Materials 470, 208-215, 2016
902016
TRISO particle fuel performance and failure analysis with BISON
W Jiang, JD Hales, BW Spencer, BP Collin, AE Slaughter, SR Novascone, ...
Journal of Nuclear Materials 548, 152795, 2021
882021
Asymptotic expansion homogenization for multiscale nuclear fuel analysis
JD Hales, MR Tonks, K Chockalingam, DM Perez, SR Novascone, ...
Computational Materials Science 99, 290-297, 2015
782015
A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools
D Pizzocri, G Pastore, T Barani, A Magni, L Luzzi, P Van Uffelen, SA Pitts, ...
Journal of Nuclear Materials 502, 323-330, 2018
682018
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions
T Barani, G Pastore, D Pizzocri, DA Andersson, C Matthews, A Alfonsi, ...
Journal of Nuclear Materials 522, 97-110, 2019
582019
Discrete element method for simulation of early-life thermal fracturing behavior in ceramic nuclear fuel pellets
H Huang, B Spencer, J Hales
Nuclear Engineering and Design 278, 515-528, 2014
572014
Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code
Y Che, G Pastore, J Hales, K Shirvan
Nuclear Engineering and Design 337, 271-278, 2018
522018
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