3D Neutron Transport and HPC: A PWR Full Core Calculation Using PENTRAN SN Code and IBM BLUEGENE/P Computers
Author:
Affiliation:
1. EDF R&D
2. Nuclear and Radiological Engineering Program, Georgia Institute of Technology
Publisher
The Atomic Energy Society of Japan
Subject
General Medicine
Cited by 8 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Influence of the spatial grid type on the result of calculating the neutron fields in the nuclear power plant shielding;Nuclear Energy and Technology;2023-06-20
2. Design of an ultra-compact imaging chamber and radiation beamstop for a neutron radiography system employing particle transport;Nuclear Engineering and Design;2022-01
3. Computational design and optimization of a neutron imaging beamline using Monte Carlo and deterministic SN radiation transport for the Utah TRIGA reactor;Nuclear Engineering and Design;2021-10
4. 3D SN and Monte Carlo calculations of the Utah TRIGA reactor core using PENTRAN and MCNP6;Annals of Nuclear Energy;2021-06
5. Experimental and Computational Dose Rate Evaluation Using SN and Monte Carlo Method for a Packaged 241AmBe Neutron Source;Nuclear Science and Engineering;2021-04-30
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