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Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP

고도영|이근우|김규형|라기원
한국원자력학회 (Korean Nuclear Society)|2025.02|Nuclear Engineering and Technology|제57권 제2호|pp. 1-8|DOI 10.1016/j.net.2024.08.061

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키워드

ValidationVerificationCFDAPR1400CVAPGrid Convergence Index
주제분류원자력공학

초록

This paper presents a methodology for analyzing the internal flow of the APR1400 Reactor Vessel Internals (RVI) using Computational Fluid Dynamics (CFD). The Comprehensive Vibration Assessment Program (CVAP) is performed to verify the structural integrity of reactor internals for flow-induced vibrations prior to the commercial operation of nuclear power plants. To classify the APR1400 as a valid prototype, it is necessary to demonstrate through successful CVAP that there are no adverse effects. In this study, CFD is used to calculate the local velocity and flow distribution to generate the forcing functions caused by turbulent flow for analysis programs in the CVAP. The Verification &Validation (V&V) procedure recommended by the American Society of Mechanical Engineers (ASME) is performed to verify the accuracy of CFD based on reliability, and it is compared with tests on a scale model. This paper provides valuable insights into the analysis and V&V process for CVAP using CFD, which can help ensure the safe and reliable operation of nuclear power plants

Abstract

This paper presents a methodology for analyzing the internal flow of the APR1400 Reactor Vessel Internals (RVI) using Computational Fluid Dynamics (CFD). The Comprehensive Vibration Assessment Program (CVAP) is performed to verify the structural integrity of reactor internals for flow-induced vibrations prior to the commercial operation of nuclear power plants. To classify the APR1400 as a valid prototype, it is necessary to demonstrate through successful CVAP that there are no adverse effects. In this study, CFD is used to calculate the local velocity and flow distribution to generate the forcing functions caused by turbulent flow for analysis programs in the CVAP. The Verification &Validation (V&V) procedure recommended by the American Society of Mechanical Engineers (ASME) is performed to verify the accuracy of CFD based on reliability, and it is compared with tests on a scale model. This paper provides valuable insights into the analysis and V&V process for CVAP using CFD, which can help ensure the safe and reliable operation of nuclear power plants

관련 논문AI추천

Development of a new CVAP structural analysis methodology of APR1400 reactor internals using scaled model tests고도영, 김규형, 문종성, 진인성한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제1호Experimental investigation of the effect of operating conditions on internal flow behavior in APR1000김기환, 김요한, 김우식, 설효성, 어동진, 임병준, 최해섭한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제9호Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate김응수, 박일웅, 송민섭, 이연건한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제1호Research on the construction of power spectral density function on the core barrel surface of pressurized water reactorLai Jiang, Ma Jianzhong, Qiao Hongwei, Tan Tiancai, Xi Zhide한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제10호Numerical study of turbulent flow under different flow mixing devices in a scaled-down reactor pressure vessel modelChen Chong, Deng Jian, Lu Qi, Qu Wenhai, Shen Danhong, Wang Hanyu, Xie Hao한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제12호Analysis of LBLOCA of APR1400 with 3D RPV model using TRACE김태완, 이영재, 이윤석, 정애주한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제5호

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