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William Wieselquist
William Wieselquist
Email yang diverifikasi di ornl.gov
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SCALE code system
WA Wieselquist, RA Lefebvre, MA Jessee
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020
2222020
VERA core simulator methodology for pressurized water reactor cycle depletion
B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ...
Nuclear Science and Engineering 185 (1), 217-231, 2017
1202017
PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM benchmark phase I
W Wieselquist, T Zhu, A Vasiliev, H Ferroukhi
Science and Technology of Nuclear Installations 2013, 2013
912013
Nuclide depletion capabilities in the Shift Monte Carlo code
GG Davidson, TM Pandya, SR Johnson, TM Evans, AE Isotalo, CA Gentry, ...
Annals of Nuclear Energy 114, 259-276, 2018
592018
VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12
A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ...
Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016
522016
Polaris: a new two-dimensional lattice physics analysis capability for the SCALE code system
MA Jessee, WA Wieselquist, TM Evans, SP Hamilton, JJ Jarrell, KS Kim, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014
472014
Current nuclear data needs for applications
K Kolos, V Sobes, R Vogt, CE Romano, MS Smith, LA Bernstein, ...
Physical Review Research 4 (2), 021001, 2022
462022
The SCALE 6.2 ORIGEN API for high performance depletion
WA Wieselquist
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015
402015
VERA core simulator methodology for PWR cycle depletion
B Kochunas, BS Collins, D Jabaay, KS Kim, A Graham, S Stimpson, ...
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Oak Ridge …, 2015
322015
A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN
AE Isotalo, WA Wieselquist
Annals of Nuclear Energy 85, 68-77, 2015
312015
SCALE 6.3. 0 User Manual
WA Wieselquist, RA Lefebvre
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2021
302021
SCALE capabilities for high temperature gas-cooled reactor analysis
F Bostelmann, C Celik, ML Williams, RJ Ellis, G Ilas, WA Wieselquist
Annals of Nuclear Energy 147, 107673, 2020
262020
SCALE Code System, Version 6.2. 4
WA Wieselquist, RA Lefebvre, MA Jessee, D Wiarda, ME Dunn, ...
Oak Ridge National Laboratory, ORNL/TM-2005/39, 2020
252020
Benchmark for Uncertainty Analysis in Modelling (UAM) for design, operation and safety analysis of LWRs, Volume III: Specification and Support Data for the System Cases (Phase III)
J Hou, M Avramova, K Ivanov, E Royer, M Jessee, J Zhang, W Wieselquist, ...
Nuclear Energy Agency, 2017
242017
A new framework for sampling-based uncertainty quantification of the six-group reactor kinetic parameters
MI Radaideh, WA Wieselquist, T Kozlowski
Annals of Nuclear Energy 127, 1-11, 2019
232019
SCALE code system, ORNL/TM-2005/39, version 6.2. 4
WA Wieselquist, RA Lefebvre, MA Jessee
Oak Ridge National Laboratory,, Oak Ridge, TN, 2020
222020
A cell-local finite difference discretization of the low-order quasidiffusion equations for neutral particle transport on unstructured quadrilateral meshes
WA Wieselquist, DY Anistratov, JE Morel
Journal of Computational Physics 273, 343-357, 2014
222014
Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
W Wieselquist, A Vasiliev, H Ferroukhi
Proceedings of the PHYSOR-2012 conference, Advances in Reactor Physics …, 2012
222012
Overview of SCALE 6.2
BT Rearden, ME Dunn, D Wiarda, C Celik, KB Bekar, ML Williams, ...
Proceedings of ANS NCSD 2013, Wilmington, North Carolina, September 29–October 3, 2013
212013
Uncertainty and sensitivity analysis in criticality calculations with perturbation theory and sampling
F Bostelmann, FP Weiss, A Aures, K Velkov, W Zwermann, BT Rearden, ...
ANS MC2015, Nashville, TN, USA, 2015
202015
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