Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP
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 vibrat...
Saved in:
Main Authors: | , , , |
---|---|
Format: | Article |
Language: | English |
Published: |
Elsevier
2025-02-01
|
Series: | Nuclear Engineering and Technology |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573324004406 |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
_version_ | 1832576490222387200 |
---|---|
author | Giwon La Kunwoo Yi Doyoung Ko Kyuhyung Kim |
author_facet | Giwon La Kunwoo Yi Doyoung Ko Kyuhyung Kim |
author_sort | Giwon La |
collection | DOAJ |
description | 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. |
format | Article |
id | doaj-art-8b2c454729614bff8b8a6a79ef629fb6 |
institution | Kabale University |
issn | 1738-5733 |
language | English |
publishDate | 2025-02-01 |
publisher | Elsevier |
record_format | Article |
series | Nuclear Engineering and Technology |
spelling | doaj-art-8b2c454729614bff8b8a6a79ef629fb62025-01-31T05:11:04ZengElsevierNuclear Engineering and Technology1738-57332025-02-01572103192Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAPGiwon La0Kunwoo Yi1Doyoung Ko2Kyuhyung Kim3KEPCO E&C (Korea Electric Power Corporation Engineering & Construction), 989-111 Daedeok-daero, Yuseong-gu, Daejeon, Republic of Korea; Corresponding author.KEPCO E&C (Korea Electric Power Corporation Engineering & Construction), 989-111 Daedeok-daero, Yuseong-gu, Daejeon, Republic of KoreaKHNP (Korea Hydro & Nuclear Power Co., Ltd), 1312-70 Yuseong-daero, Yuseong-gu, Daejeon, Republic of KoreaKHNP (Korea Hydro & Nuclear Power Co., Ltd), 1312-70 Yuseong-daero, Yuseong-gu, Daejeon, Republic of KoreaThis 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.http://www.sciencedirect.com/science/article/pii/S1738573324004406APR1400CFDCVAPGrid Convergence IndexVerificationValidation |
spellingShingle | Giwon La Kunwoo Yi Doyoung Ko Kyuhyung Kim Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP Nuclear Engineering and Technology APR1400 CFD CVAP Grid Convergence Index Verification Validation |
title | Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP |
title_full | Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP |
title_fullStr | Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP |
title_full_unstemmed | Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP |
title_short | Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP |
title_sort | verification and validation of cfd analysis for 1 7th scale model of apr1400 for cvap |
topic | APR1400 CFD CVAP Grid Convergence Index Verification Validation |
url | http://www.sciencedirect.com/science/article/pii/S1738573324004406 |
work_keys_str_mv | AT giwonla verificationandvalidationofcfdanalysisfor17thscalemodelofapr1400forcvap AT kunwooyi verificationandvalidationofcfdanalysisfor17thscalemodelofapr1400forcvap AT doyoungko verificationandvalidationofcfdanalysisfor17thscalemodelofapr1400forcvap AT kyuhyungkim verificationandvalidationofcfdanalysisfor17thscalemodelofapr1400forcvap |