본문 바로가기
KERD
논문KCI 등재

The application of Kriging model for three-dimensional core power distribution calibration

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

The safety operation of a nuclear reactor relies on knowing the core power distributions as accurately as possible. PWR adapt the calculated power distributions to obtain accurate power distributions, which requires knowing the calibration factors for the calculated powers of each fuel bundle in the core. The calibration factors are obtained by comparing the measured reaction rates and the calculated reaction rates at the instrumented locations in the core. For the fuel bundles position that do not have measurement data, their calibration factors shall be inferred by using the calibration factor of the instrumented bundles nearby. In this study, we propose using Kriging model to fit the calibration factors of the instrumented bundles and then predict the calibration factors for the un-instrumented bundles. To verify the correctness of the model, we employed a method of repeated random sampling from the dataset to validate the model. After expanding the samples in each group, which originally contained only one plane, to include two or three planes, it was observed that the average RMSE value, as defined by cross-validation, not only significantly decreased but also showed a marked improvement in the predicted calibration factor for most of the validated samples.

Abstract

The safety operation of a nuclear reactor relies on knowing the core power distributions as accurately as possible. PWR adapt the calculated power distributions to obtain accurate power distributions, which requires knowing the calibration factors for the calculated powers of each fuel bundle in the core. The calibration factors are obtained by comparing the measured reaction rates and the calculated reaction rates at the instrumented locations in the core. For the fuel bundles position that do not have measurement data, their calibration factors shall be inferred by using the calibration factor of the instrumented bundles nearby. In this study, we propose using Kriging model to fit the calibration factors of the instrumented bundles and then predict the calibration factors for the un-instrumented bundles. To verify the correctness of the model, we employed a method of repeated random sampling from the dataset to validate the model. After expanding the samples in each group, which originally contained only one plane, to include two or three planes, it was observed that the average RMSE value, as defined by cross-validation, not only significantly decreased but also showed a marked improvement in the predicted calibration factor for most of the validated samples.

관련 논문AI추천

Artificial neural network reconstructs core power distributionChen Chen, Chengjie Duan, Dawei Cui, Fengwan Yu, Peng Ding, Shu Chen, Wenhuai Li, Wenqing Xia한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제2호Continuous mapping of nuclear reactor core power using artificial neural network even in the presence of inactive detectorsGonçalves Alessandro C., Martinez Aquilino S., Talon João D.한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제12호Reactor physics fast calculation method based on model order reduction and machine learningChai Xiaoming, Liu Jiayi, Peng Xingjie, Wang Jiangyu, Wang Lianjie, Xia Bangyang, Zhang Bin, Zhang Qinyi, Zhao Chen한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제10호A new surrogate method for the neutron kinetics calculation of nuclear reactor core transientsDu Xianan, Li Xiaoqi, Xiao Bowen, Zheng Youqi한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제9호Uncertainty quantification of steady state depeltion solution using multi-physics coupling code system based on nodal diffusion code RAST-K강영석, 박진수, 이덕중한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제11호PWR core calculation based on pin-cell homogenization in three-dimensional pin-by-pin geometryChai Xiaoming, Fang Chao, Gong Zhaohu, Li Qing, Li Yunzhao, Wu Hongchun, Yu Junchong, Zhang Bin, Zhao Wenbo한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제6호

이 간행물의 다른 논문 (59건)