Validation of a nuclear code system for prismatic high temperature gas-cooled reactors based on the Very High Temperature Reactor Critical Assembly benchmark

Yuan Yuan; Zhang Chenglong; Liu Guoming; Du Shuhong; Huo Xiaodong; Feng Zhiyuan; Du Xia’nan

doi:10.11884/HPLPB202234.210362

Volume 34 Issue 2

Jan. 2022

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Article Navigation > High Power Laser and Particle Beams > 2022 > 34(2): 026017

Yuan Yuan, Zhang Chenglong, Liu Guoming, et al. Validation of a nuclear code system for prismatic high temperature gas-cooled reactors based on the Very High Temperature Reactor Critical Assembly benchmark[J]. High Power Laser and Particle Beams, 2022, 34: 026017. doi: 10.11884/HPLPB202234.210362

Citation:

Yuan Yuan, Zhang Chenglong, Liu Guoming, et al. Validation of a nuclear code system for prismatic high temperature gas-cooled reactors based on the Very High Temperature Reactor Critical Assembly benchmark[J]. High Power Laser and Particle Beams, 2022, 34: 026017. doi: 10.11884/HPLPB202234.210362

Citation:

Yuan Yuan, Zhang Chenglong, Liu Guoming, et al. Validation of a nuclear code system for prismatic high temperature gas-cooled reactors based on the Very High Temperature Reactor Critical Assembly benchmark[J]. High Power Laser and Particle Beams, 2022, 34: 026017. doi: 10.11884/HPLPB202234.210362

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Validation of a nuclear code system for prismatic high temperature gas-cooled reactors based on the Very High Temperature Reactor Critical Assembly benchmark

doi: 10.11884/HPLPB202234.210362

1.
China Nuclear Power Engineering Co., Ltd, Beijing 100840, China
2.
Department of Engineering Physics, Tsinghua University, Beijing 100084, China
3.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China

Received Date: 2021-08-23
Rev Recd Date: 2021-10-09

Available Online: 2021-10-21

Publish Date: 2022-01-11

Abstract

Abstract

The inherent safety characteristic of high temperature gas-cooled reactor (HTGR) is universally acknowledged. On account of the double-heterogeneity of the coated fuel and the irregular core pattern of the prismatic HTGR, a code system based on Monte-Carlo homogenization and deterministic transport concept was used as a nuclear design code system for prismatic HTGR. An investigation on homogenization model and preliminary validation of this code system is conducted based on VHTRC benchmark which is a prismatic HTGR criticality assembly. The validation results indicate that group constants generation based on Monte-Carlo homogenization and appropriate energy group, then modified by super homogenization (SPH) method further, ensures high precision of homogeneous core calculation.
- prismatic high temperature gas-cooled reactor,
- Monte-Carlo homogenization,
- super homogenization,
- full-corehomogenization,
- core transport

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References(9)

References

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