Verification and Validation of NECP-Bamboo Based on Measurement Data from Nuclear Power Plants

Liang Yilin; Li Yunzhao; Zhou Yuancheng; Li Yisong; Zhang Hengrui; Zhou Shilong; Wang Weiguo; Ou Yuxiang; Wang Songzhe; Qin Junwei; Shao Ruizhi

doi:10.13832/j.jnpe.2024.02.0024

Volume 45 Issue 2

Apr. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(2): 24-34

Liang Yilin, Li Yunzhao, Zhou Yuancheng, Li Yisong, Zhang Hengrui, Zhou Shilong, Wang Weiguo, Ou Yuxiang, Wang Songzhe, Qin Junwei, Shao Ruizhi. Verification and Validation of NECP-Bamboo Based on Measurement Data from Nuclear Power Plants[J]. Nuclear Power Engineering, 2024, 45(2): 24-34. doi: 10.13832/j.jnpe.2024.02.0024

Citation:

Liang Yilin, Li Yunzhao, Zhou Yuancheng, Li Yisong, Zhang Hengrui, Zhou Shilong, Wang Weiguo, Ou Yuxiang, Wang Songzhe, Qin Junwei, Shao Ruizhi. Verification and Validation of NECP-Bamboo Based on Measurement Data from Nuclear Power Plants[J]. Nuclear Power Engineering, 2024, 45(2): 24-34. doi: 10.13832/j.jnpe.2024.02.0024

Citation:

Liang Yilin, Li Yunzhao, Zhou Yuancheng, Li Yisong, Zhang Hengrui, Zhou Shilong, Wang Weiguo, Ou Yuxiang, Wang Songzhe, Qin Junwei, Shao Ruizhi. Verification and Validation of NECP-Bamboo Based on Measurement Data from Nuclear Power Plants[J]. Nuclear Power Engineering, 2024, 45(2): 24-34. doi: 10.13832/j.jnpe.2024.02.0024

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Verification and Validation of NECP-Bamboo Based on Measurement Data from Nuclear Power Plants

doi: 10.13832/j.jnpe.2024.02.0024

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

Received Date: 2023-05-29
Rev Recd Date: 2023-07-10
Publish Date: 2024-04-12

Abstract

Abstract

The verification and validation (V&V) are important aspects in the life cycle of engineering software, and reflect the process of software development to practical application. They are also significant symbols of software from "bookshelf" to "goods shelf". In this paper, V&V for the software NECP-Bamboo were carried out based on the actual measurement data of five types of commercial pressurized water reactors, including CNP300, M310, CNP650, BEAVRS and HPR1000, for a total of 48 operation cycles. The results show that the errors between the calculated values and the measured values of the key reactor parameters, such as control rod worth, temperature coefficient, critical boron concentration and assembly power distribution, obtained by using NECP-Bamboo can meet the requirements of industrial limits. The 95% confidence interval range of the corresponding key parameter errors of various types of reactors is summarized as follows: [−37.80, 35.39]ppm for critical boron concentration, [−6.18%, 3.68%] for control rod worth, [−3.27, 2.99] pcm/K for the reactivity coefficient of temperature, [−0.64%, −0.12%] for the assembly power distribution when the relative power is greater than 0.9, and [1.18%, 2.94%] for that when the relative power is less than 0.9.
- NECP-Bamboo,
- CNP300,
- M310,
- CNP650,
- BEAVRS,
- HPR1000,
- Verification and validation

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References(18)

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