Automated Validation of CGN Nuclear Software Package PCM

Wang Chao; Yang Shuoyan; Peng Sitao; Li Guoren; Ma Yunfan; Chen Jun; Wang Junling; Lu Haoliang

doi:10.13832/j.jnpe.2018.S2.0043

Volume 39 Issue S2

Dec. 2018

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Wang Chao, Yang Shuoyan, Peng Sitao, Li Guoren, Ma Yunfan, Chen Jun, Wang Junling, Lu Haoliang. Automated Validation of CGN Nuclear Software Package PCM[J]. Nuclear Power Engineering, 2018, 39(S2): 43-46. doi: 10.13832/j.jnpe.2018.S2.0043

Citation:

Wang Chao, Yang Shuoyan, Peng Sitao, Li Guoren, Ma Yunfan, Chen Jun, Wang Junling, Lu Haoliang. Automated Validation of CGN Nuclear Software Package PCM[J]. Nuclear Power Engineering, 2018, 39(S2): 43-46. doi: 10.13832/j.jnpe.2018.S2.0043

Citation:

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Automated Validation of CGN Nuclear Software Package PCM

doi: 10.13832/j.jnpe.2018.S2.0043

1. China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, 518026, China;
2. Guangxi Fangchenggang Nuclear Power Co. Ltd., Fangchenggang, Guangxi, 538000, China

Received Date: 2018-10-10
Rev Recd Date: 2018-10-17

Available Online: 2025-02-09

Abstract

Abstract

The software package PCM, consisted of lattice code PINE, core physics code COCO and flux mapping code MAPLE, has been used in the design of HPR1000. The Validation of PCM used power plant data, experimental data, benchmarks, and similar software’s results. To complete the iterative validation more efficiently, an automated validation platform YAM was developed. The YAM automates the validation process and computational procedure of the software package PCM. The validation shows that the results of PCM match well with the references. The uncertainty of PCM package is less than that assumed in the reactor safety analysis.
- YAM,
- Automated,
- PCM,
- Validation