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

doi:10.11884/HPLPB202234.210362

Journals >High Power Laser and Particle Beams >Volume 34 >Issue 2 >Page 026017 > Article

High Power Laser and Particle Beams
Vol. 34, Issue 2, 026017 (2022)

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

Yuan Yuan¹, Chenglong Zhang¹, Guoming Liu^1、*, Shuhong Du¹, Xiaodong Huo¹, Zhiyuan Feng², and Xia’nan Du³

Author Affiliations

¹China Nuclear Power Engineering Co., Ltd, Beijing 100840, China

²Department of Engineering Physics, Tsinghua University, Beijing 100084, China

³School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China

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DOI: 10.11884/HPLPB202234.210362 Cite this Article

Yuan Yuan, Chenglong Zhang, Guoming Liu, Shuhong Du, Xiaodong Huo, Zhiyuan Feng, Xia’nan Du. 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(2): 026017 Copy Citation Text

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References

[1] Wu Zongxin, Zhang Zuoyi. The advanced nuclear energy system high temperature gascooled react. Beijing: Tsinghua University Press, 2004

[3] Tsuyoshi Y, Yasuni K, Yuta E. Temperature effect on reactivity in VHTRC1 ce[R]. VHTRCGCREXP001, 2006.

[4] Wang K, Li Z G, She D, et al. RMC – A Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 82, 121-129(2015).

[5] Wu Gaochen. Research on continuous energy Monte Carlo homogenization group constant generation based on RMC[D]. Beijing: Tsinghua University, 2018

[6] Yuan Y, Xing J, Huo X D, et al. Research on the on-the-fly homogenization method based on RMC code for criticality calculations[J]. Annals of Nuclear Energy, 135, 106985(2020).

[7] Liu S, She D, Liang J G, et al. Development of random geometry capability in RMC code for stochastic media analysis[J]. Annals of Nuclear Energy, 85, 903-908(2015).

[9] Joel D R. CASMO5: a fuel assembly burnup program user’s manual[R]. SSP07431 Rev 9, 2015.

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