Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified ba...
Main Authors: | , , , , |
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Format: | Article |
Language: | English |
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Elsevier
2019-06-01
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Series: | Nuclear Engineering and Technology |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573318306119 |
_version_ | 1819086959919759360 |
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author | Jin Gwan Son Jae Han Lee Hoe Woong Kim Sung Kyun Kim Jong Bum Kim |
author_facet | Jin Gwan Son Jae Han Lee Hoe Woong Kim Sung Kyun Kim Jong Bum Kim |
author_sort | Jin Gwan Son |
collection | DOAJ |
description | This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified based on the drop analysis results was newly fabricated, and several free drop tests under different flow rate conditions were carried out. Then the results were compared with those obtained from the previous tests conducted on the conceptually designed control rod assembly to demonstrate the improvement in performance. Moreover, the drop performance tests under several types and magnitudes of seismic loadings were also conducted to investigate the effect of the seismic loading on the drop performance of the modified control rod assembly. The results showed that the effects of the type and magnitude of the seismic loading on the drop performance of the modified control rod assembly were not significant. Also, the drop time requirement was successfully satisfied, even under the seismic loading conditions. Keywords: Sodium-cooled fast reactor, Control rod assembly, Drop performance test, Seismic loading, Drop time |
first_indexed | 2024-12-21T21:28:32Z |
format | Article |
id | doaj.art-0ffbd576135b4a989bbcc65d09c7a736 |
institution | Directory Open Access Journal |
issn | 1738-5733 |
language | English |
last_indexed | 2024-12-21T21:28:32Z |
publishDate | 2019-06-01 |
publisher | Elsevier |
record_format | Article |
series | Nuclear Engineering and Technology |
spelling | doaj.art-0ffbd576135b4a989bbcc65d09c7a7362022-12-21T18:49:42ZengElsevierNuclear Engineering and Technology1738-57332019-06-01513922929Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performanceJin Gwan Son0Jae Han Lee1Hoe Woong Kim2Sung Kyun Kim3Jong Bum Kim4Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of KoreaSodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of KoreaCorresponding author.; Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of KoreaSodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of KoreaSodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of KoreaThis paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified based on the drop analysis results was newly fabricated, and several free drop tests under different flow rate conditions were carried out. Then the results were compared with those obtained from the previous tests conducted on the conceptually designed control rod assembly to demonstrate the improvement in performance. Moreover, the drop performance tests under several types and magnitudes of seismic loadings were also conducted to investigate the effect of the seismic loading on the drop performance of the modified control rod assembly. The results showed that the effects of the type and magnitude of the seismic loading on the drop performance of the modified control rod assembly were not significant. Also, the drop time requirement was successfully satisfied, even under the seismic loading conditions. Keywords: Sodium-cooled fast reactor, Control rod assembly, Drop performance test, Seismic loading, Drop timehttp://www.sciencedirect.com/science/article/pii/S1738573318306119 |
spellingShingle | Jin Gwan Son Jae Han Lee Hoe Woong Kim Sung Kyun Kim Jong Bum Kim Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance Nuclear Engineering and Technology |
title | Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance |
title_full | Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance |
title_fullStr | Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance |
title_full_unstemmed | Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance |
title_short | Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance |
title_sort | influence of design modification of control rod assembly for prototype generation iv sodium cooled fast reactor on drop performance |
url | http://www.sciencedirect.com/science/article/pii/S1738573318306119 |
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