ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions
An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water re...
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| Format: | Article |
| Language: | English |
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Elsevier
2018-08-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573318301645 |
| _version_ | 1818346701397688320 |
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| author | Takeshi Takeda |
| author_facet | Takeshi Takeda |
| author_sort | Takeshi Takeda |
| collection | DOAJ |
| description | An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water reactor. The relief valve of broken SG opened three times after the start of intact SG secondary-side depressurization as the recovery action. Multi-dimensional phenomena specific to the SGTR accident appeared such as significant thermal stratification in a cold leg in broken loop especially during the operation of high-pressure injection (HPI) system. The RELAP5/MOD3.3 code overpredicted the broken SG secondary-side pressure after the start of the intact SG secondary-side depressurization, and failed to calculate the cold leg fluid temperature in broken loop. The combination of the number of the ruptured SG tubes and the HPI system operation difference was found to significantly affect the primary and SG secondary-side pressures through sensitivity analyses with the RELAP5 code. Keywords: Pressurized water reactor, Large-scale test facility, Steam generator tube rupture, Recovery action, High-pressure injection system, RELAP5 code |
| first_indexed | 2024-12-13T17:22:27Z |
| format | Article |
| id | doaj.art-5fca71ef116249d1ae1e2aa0fe90b95c |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-13T17:22:27Z |
| publishDate | 2018-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-5fca71ef116249d1ae1e2aa0fe90b95c2022-12-21T23:37:17ZengElsevierNuclear Engineering and Technology1738-57332018-08-01506981988ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actionsTakeshi Takeda0Nuclear Regulation Authority, Roppongi, Minato-ku, Tokyo 106-8450, Japan; Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195, JapanAn experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water reactor. The relief valve of broken SG opened three times after the start of intact SG secondary-side depressurization as the recovery action. Multi-dimensional phenomena specific to the SGTR accident appeared such as significant thermal stratification in a cold leg in broken loop especially during the operation of high-pressure injection (HPI) system. The RELAP5/MOD3.3 code overpredicted the broken SG secondary-side pressure after the start of the intact SG secondary-side depressurization, and failed to calculate the cold leg fluid temperature in broken loop. The combination of the number of the ruptured SG tubes and the HPI system operation difference was found to significantly affect the primary and SG secondary-side pressures through sensitivity analyses with the RELAP5 code. Keywords: Pressurized water reactor, Large-scale test facility, Steam generator tube rupture, Recovery action, High-pressure injection system, RELAP5 codehttp://www.sciencedirect.com/science/article/pii/S1738573318301645 |
| spellingShingle | Takeshi Takeda ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions Nuclear Engineering and Technology |
| title | ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions |
| title_full | ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions |
| title_fullStr | ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions |
| title_full_unstemmed | ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions |
| title_short | ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions |
| title_sort | rosa lstf test and relap5 code analyses on pwr steam generator tube rupture accident with recovery actions |
| url | http://www.sciencedirect.com/science/article/pii/S1738573318301645 |
| work_keys_str_mv | AT takeshitakeda rosalstftestandrelap5codeanalysesonpwrsteamgeneratortuberuptureaccidentwithrecoveryactions |