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Depletion capabilities in the OpenMC Monte Carlo particle transport code
Paul K. Romano, Colin J. Josey, Andrew E. Johnson, Jingang Liang
Argonne National Laboratory Los Alamos National Laboratory Georgia Institute of Technology Tsinghua University
来源Annals of Nuclear Energy
年份2020
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工程Nuclear reactor physics and engineering
Nuclear physics research studies · Nuclear Materials and Properties
参考文献 56
Rational Approximations to the Matrix Exponential in Burnup Calculations
被引 142Maria Pusa · Nuclear Science and Engineering · 2011
A Burnup-Dependent Isomeric Production Branching Ratio Treatment
被引 5Wim Haeck, B. Cochet, Luís M. Aguiar · Nuclear Science and Engineering · 2012
Isotopic Depletion and Decay Methods and Analysis Capabilities in SCALE
被引 173Ian C Gauld, Georgeta Radulescu, Germina Ilas · Nuclear Technology · 2011
此处列出前 3 条
引用本文 92
Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC
被引 24Ethan Peterson, Paul K. Romano, Patrick Shriwise · Nuclear Fusion · 2024
Verification of depletion capability of OpenMC using VERA depletion benchmark
被引 18Jiankai Yu, Benoit Forget · Annals of Nuclear Energy · 2022
Verification of neutron-induced fission product yields evaluated by a tensor decompsition model in transport-burnup simulations
被引 17Qufei Song, Long Zhu, Hui Guo · Nuclear Science and Techniques · 2023
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