Comparison and verification of NECP-X and OpenMC using high-fidelity BEAVRS benchmark models

SHEN Zhirui; SUN Qizheng; HE Donghao; PAN Qingquan; ZHANG Tengfei; PENG Lianghui; YANG Weiyan

doi:10.11889/j.0253-3219.2022.hjs.45.010602

He jishu (Jan 2022)

Comparison and verification of NECP-X and OpenMC using high-fidelity BEAVRS benchmark models

SHEN Zhirui,
SUN Qizheng,
HE Donghao,
PAN Qingquan,
ZHANG Tengfei,
PENG Lianghui,
YANG Weiyan

Affiliations

SHEN Zhirui: School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
SUN Qizheng: School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
HE Donghao: School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
PAN Qingquan: School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
ZHANG Tengfei: School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
PENG Lianghui: Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China
YANG Weiyan: Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China

DOI: https://doi.org/10.11889/j.0253-3219.2022.hjs.45.010602
Journal volume & issue: Vol. 45, no. 1
pp. 010602 – 010602

Abstract

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BackgroundWith the improvement of the understanding of the physical mechanism of neutron transport and the development of high performance computing technology, high-fidelity neutronics calculation has attracted widespread attention worldwide. Both deterministic method and Monte Carlo method are employed by various institutions to achieve high-fidelity goals. NECP-X code uses one-step deterministic method whilst OpenMC uses the Monte Carlo method.PurposeThis study aims to verify the feasibility and accuracy of both NECP-X and OpenMC in modelling high-fidelity reactor cores.MethodsBased on BEAVRS2.0.1 benchmark, two high-fidelity models for pressurized water reactor (PWR), i.e., MODEL 1 consisted of 21 fuel assemblies and MODEL 2 consisted of 193 fuel assemblies, were established. Then, NECP-X (one-step deterministic method) and OpenMC (Monte Carlo method) were respectively adopted in these two high-fidelity models to calculate the effective multiplication factor, the reactor power distribution and the control rod worth of different control rod assemblies inserted in the hot zero power (HZP) condition. Finally, calculated results were compared and analyzed.ResultsUnder the HZP condition, the effective multiplication factor deviation between NECP-X and OpenMC is less than 1.40×10-3. The effective multiplication factor deviation of different control rod assemblies inserted is less than 5.9×10-4, and the deviation of control rod worth is less than 4.9×10-4. The average relative deviations of the reactor power distribution between NECP-X and OpenMC are less than 0.6%.ConclusionsNumerical results calculated by two different codes are in good agreement with each other. The feasibility and accuracy of NECP-X and OpenMC in high-fidelity reactor core modeling are preliminarily verified in this study, which lays a foundation for future applications and improvements.

Published in He jishu

ISSN: 0253-3219 (Print)
Publisher: Science Press
Country of publisher: China
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: https://www.hjs.sinap.ac.cn/

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