Verification of PCM Nuclear Design Code for Whole Core Calculations

Lu Gaoqi; Ding Ming; Lan Bing; Pan Xinyi; Li Chun; Wang Chao; Ma Yunfan

doi:10.13832/j.jnpe.2024.04.0017

Volume 45 Issue 4

Aug. 2024

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Lu Gaoqi, Ding Ming, Lan Bing, Pan Xinyi, Li Chun, Wang Chao, Ma Yunfan. Verification of PCM Nuclear Design Code for Whole Core Calculations[J]. Nuclear Power Engineering, 2024, 45(4): 17-23. doi: 10.13832/j.jnpe.2024.04.0017

Citation:

Lu Gaoqi, Ding Ming, Lan Bing, Pan Xinyi, Li Chun, Wang Chao, Ma Yunfan. Verification of PCM Nuclear Design Code for Whole Core Calculations[J]. Nuclear Power Engineering, 2024, 45(4): 17-23. doi: 10.13832/j.jnpe.2024.04.0017

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Verification of PCM Nuclear Design Code for Whole Core Calculations

doi: 10.13832/j.jnpe.2024.04.0017

Lu Gaoqi^1
,,
Ding Ming^{1
,
,},
Lan Bing²,
Pan Xinyi²,
Li Chun²,
Wang Chao³,
Ma Yunfan³

1.
Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, Harbin Engineering University, Harbin, 150001, China
2.
Nuclear and Radiation Safety Center, MEE, Beijing, 100082, China
3.
China Nuclear Power Technology Research Institute Co. Ltd.,Shenzhen, Guangdong, 518031, China

Received Date: 2023-08-09
Rev Recd Date: 2023-09-20
Publish Date: 2024-08-12

Abstract

Abstract

PCM software package, independently developed by China Nuclear Power Technology Research Institute Co. Ltd., is a nuclear design code consisting of assembly section calculation code PINE and 3D core design code COCO. To validate the whole core calculation capability and accuracy of the PCM nuclear design code, this study conducted verification using internationally recognized benchmark problems such as BIBLIS, IAEA, and LRA, as well as a self-made whole-core problem for the COCO code and the “assembly-core” two-step method within the PCM nuclear design code. The verification results indicated that in the calculations of the light-water reactor core benchmark problems, the average error of the effective multiplication factor (k_eff) for all cases was 6.4pcm, with a maximum error of only 28.2pcm. In all the cases, the deviation of the normalized power distribution of the core fuel assemblies did not exceed 1%. The verification results show that the whole core calculation function of the PCM nuclear design code exhibits high computational accuracy, and the overall calculation accuracy can meet the engineering requirements.
- Core nuclear design,
- Core benchmark,
- PCM software package

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References(11)

References

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