Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants
During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical...
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| Format: | Article |
| Language: | English |
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Elsevier
2021-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S173857332100406X |
| _version_ | 1818358292628373504 |
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| author | Yong Jae Song Dong Seok Lim Min Beom Heo Beom Kyu Kim Doo Yong Lee Daeseong Jo |
| author_facet | Yong Jae Song Dong Seok Lim Min Beom Heo Beom Kyu Kim Doo Yong Lee Daeseong Jo |
| author_sort | Yong Jae Song |
| collection | DOAJ |
| description | During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical efforts for resolving GSI-191 [( Reid and Crytzer, May. 2007) 1, consideration is needed for the consequences of debris penetrating the sump screen and propagating downstream into the RV. Injection of debris (fiberglass) into the RV during the LTC recirculation phase needs special attention to assure that reactor core cooling is maintained. The point of concern is the potential for debris to adversely affect the reactor core flow paths or heat transfer [2]. However, all the experiments for proving the coolability of RV have been done with the assumption of the most of debris would be transferred to the RV and the bottom nozzle of the FAs.The purpose of the tests is to quantify the amount of the debris that would be accumulated at the lower plenum and the debris that passes through the FAs since non-conservatism of other researches assumptions that have been used in the past experimental or analytical programs. |
| first_indexed | 2024-12-13T20:26:41Z |
| format | Article |
| id | doaj.art-a9a738d78d374e439c0daf6725a19598 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-13T20:26:41Z |
| publishDate | 2021-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-a9a738d78d374e439c0daf6725a195982022-12-21T23:32:33ZengElsevierNuclear Engineering and Technology1738-57332021-12-01531240034013Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plantsYong Jae Song0Dong Seok Lim1Min Beom Heo2Beom Kyu Kim3Doo Yong Lee4Daeseong Jo5FNC Technology Co. Ltd., 44 Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, Republic of Korea; Corresponding author.FNC Technology Co. Ltd., 44 Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, Republic of KoreaFNC Technology Co. Ltd., 44 Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, Republic of KoreaFNC Technology Co. Ltd., 44 Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, Republic of KoreaFNC Technology Co. Ltd., 44 Tapsil-ro, Giheung-gu, Yongin-si, Gyeonggi-do, Republic of KoreaSchool of Mechanical Engineering, Kyungpook National University, 80 Daehak-ro, Buk-gu, Daegu, 702-701, Republic of KoreaDuring the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical efforts for resolving GSI-191 [( Reid and Crytzer, May. 2007) 1, consideration is needed for the consequences of debris penetrating the sump screen and propagating downstream into the RV. Injection of debris (fiberglass) into the RV during the LTC recirculation phase needs special attention to assure that reactor core cooling is maintained. The point of concern is the potential for debris to adversely affect the reactor core flow paths or heat transfer [2]. However, all the experiments for proving the coolability of RV have been done with the assumption of the most of debris would be transferred to the RV and the bottom nozzle of the FAs.The purpose of the tests is to quantify the amount of the debris that would be accumulated at the lower plenum and the debris that passes through the FAs since non-conservatism of other researches assumptions that have been used in the past experimental or analytical programs.http://www.sciencedirect.com/science/article/pii/S173857332100406XDebrisGSI-191Licensing issueNuclear power plantsInsulationFiberglass |
| spellingShingle | Yong Jae Song Dong Seok Lim Min Beom Heo Beom Kyu Kim Doo Yong Lee Daeseong Jo Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants Nuclear Engineering and Technology Debris GSI-191 Licensing issue Nuclear power plants Insulation Fiberglass |
| title | Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| title_full | Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| title_fullStr | Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| title_full_unstemmed | Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| title_short | Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| title_sort | debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants |
| topic | Debris GSI-191 Licensing issue Nuclear power plants Insulation Fiberglass |
| url | http://www.sciencedirect.com/science/article/pii/S173857332100406X |
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