Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant

Fang Yonggang; Tong Zhenfeng; Chu Qibao; Zeng Zhen; Shen Yingcai

doi:10.13832/j.jnpe.2023.04.0192

Volume 44 Issue 4

Aug. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(4): 192-197

Fang Yonggang, Tong Zhenfeng, Chu Qibao, Zeng Zhen, Shen Yingcai. Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(4): 192-197. doi: 10.13832/j.jnpe.2023.04.0192

Citation:

Fang Yonggang, Tong Zhenfeng, Chu Qibao, Zeng Zhen, Shen Yingcai. Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(4): 192-197. doi: 10.13832/j.jnpe.2023.04.0192

Citation:

Fang Yonggang, Tong Zhenfeng, Chu Qibao, Zeng Zhen, Shen Yingcai. Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(4): 192-197. doi: 10.13832/j.jnpe.2023.04.0192

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Prediction of RPV Irradiation Embrittlement Performance and Life Evaluation of Extended Operation in a Nuclear Power Plant

doi: 10.13832/j.jnpe.2023.04.0192

1.
Nuclear and Radiation Safety Center, MEE, Beijing, 100082, China
2.
North China Electric Power University, Beijing, 102206, China

Received Date: 2022-11-21
Rev Recd Date: 2023-05-08
Publish Date: 2023-08-15

Abstract

Abstract

A domestic self-designed and built nuclear power plant has entered the stage of extended operation. A foreign prediction model was adopted for the irradiation embrittlement evaluation of the reactor pressure vessel, however, the irradiation data on which the foreign prediction model was based cannot effectively represent the irradiation embrittlement performance of domestic RPV materials, especially for the extended operation stage. Based on the radiation embrittlement prediction models of RPV at home and abroad and their development mechanisms, an independent low-Cu RPV radiation embrittlement prediction model suitable for domestic engineering applications has been formed, which considers the key factors of irradiation embrittlement such as stable matrix defects and alloy element precipitation. According to the irradiation embrittlement data of domestic low-Cu RPV materials, the standard deviation and margin analysis of the independent model were carried out, and the results indicated a high level of confidence in prediction. Based on the model, the irradiation performance of the RPV was evaluated, and the feasibility of extended operation to 60 equivalent full power years (EFPY) was demonstrated.
- Reactor pressure vessel,
- Irradiation embrittlement,
- Prediction model,
- Extended operation

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References(12)

References

[1]	杨文斗. 反应堆材料学[M]. 北京: 原子能出版社, 2006: 328.
[2]	American Society for Testing and Materials. Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels: ASTM E185[S]. USA: ASTM Committee, 1982: 1-8.
[3]	U. S. Nuclear Regulatory Commission. Radiation embrittlement of reactor vessel materials, regulatory guide 1.99 revision 2: TASK ME 305-4[R]. Washington: U. S. Nuclear Regulatory Commission, 1988.
[4]	日本原子力规则委员会. 核反应堆压力容器材料监督试验方法: JEAC 4201[S]. 日本: 日本电气协会, 1991:12-58.
[5]	TANON A P, GRANDEMANGE J, HOUSSIN B, et al. French verification of PWR vessel integrity: EPRI-NP--6713[R]. Palo Alto: Research Reports Center, 1990.
[6]	EASON E D, WRIGHT J E, ODETTE G R. Improved embrittlement correlations for reactor pressure vessel steels: NUREG/CR-6551[R]. Washington: U. S. Nuclear Regulatory Commission, 1998.
[7]	SERVER W L, ENGLISH C A, NAIMAN D Q, et al. Charpy embrittlement correlations – status of combined mechanistic and statistical bases for U. S. RPV steels: EPRIMRP-45[R]. Palo Alto: Electric Power Research Institute, 2001.
[8]	EASON E D, ODETTE G R, NANSTAD R K. A Physically based correlation of irradiation-induced transition temperature shifts for RPV steels: ORNL/TM-2006/530[R]. Tennessee: Oak Ridge National Laboratory, 2006
[9]	ERICKSONKIRK M. A review of ∆T30 data for reactor pressure vessel steels obtained at high fluence[J]. J ASTM Intl., 2009: JAI102000-8.
[10]	佟振峰,林虎,宁广胜,等. 低铜合金反应堆压力容器钢辐照脆化预测评估模型[J]. 原子能科学技术,2009, 43(S1): 103-108.
[11]	American Society for Testing and Materials. Standard practice for extrapolating reactor vessel surveillance dosimetry results: ASTM E560[S]. USA: ASTM Committee, 2001: 1-5
[12]	U. S. Nuclear Regulatory Commission. 10CFR Part50 domestic licensing of production and utilization facilities, appendix A[Z]. USA: Nuclear Regulatory Commission, 2021.

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