THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING
The pressurized thermal shock（ PTS） event poses a potentially significant challenge to the structural integrity of the reactor pressure vessel（ RPV） during the long time operation. In most countries（ with exception of the USA）,proving RPV integrity under the PTS load is based on the deterministic fr...
| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | zho |
| Published: |
Editorial Office of Journal of Mechanical Strength
2016-01-01
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| Series: | Jixie qiangdu |
| Subjects: | |
| Online Access: | http://www.jxqd.net.cn/thesisDetails#10.16579/j.issn.1001.9669.2016.04.031 |
| _version_ | 1797767915823431680 |
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| author | WANG RongShan CHEN MingYa LU Feng ZHENG WeiDong WANG DongHui ZHANG YaPing FAN Zhao |
| author_facet | WANG RongShan CHEN MingYa LU Feng ZHENG WeiDong WANG DongHui ZHANG YaPing FAN Zhao |
| author_sort | WANG RongShan |
| collection | DOAJ |
| description | The pressurized thermal shock（ PTS） event poses a potentially significant challenge to the structural integrity of the reactor pressure vessel（ RPV） during the long time operation. In most countries（ with exception of the USA）,proving RPV integrity under the PTS load is based on the deterministic fracture mechanics（ DFM）. In the USA,the "screening criteria"for maximum allowable embrittlement of RPV material,which form part of the USA regulations,are based on the probabilistic fracture mechanics（ PFM）. In this paper,the FAVOR software of Oka Ridge National Laboratory is used to compare the difference between PFM and DFM analysis of the PTS even. The analysis method of FAVOR is shown through case study of the benchmark transient in the IAEA-TECDOC-1627 report. Finally,the limit of the current FAVOR（ Version6. 1） is shown. |
| first_indexed | 2024-03-12T20:45:53Z |
| format | Article |
| id | doaj.art-2f18278913284d98b842af7f8b44f901 |
| institution | Directory Open Access Journal |
| issn | 1001-9669 |
| language | zho |
| last_indexed | 2024-03-12T20:45:53Z |
| publishDate | 2016-01-01 |
| publisher | Editorial Office of Journal of Mechanical Strength |
| record_format | Article |
| series | Jixie qiangdu |
| spelling | doaj.art-2f18278913284d98b842af7f8b44f9012023-08-01T07:42:51ZzhoEditorial Office of Journal of Mechanical StrengthJixie qiangdu1001-96692016-01-013883884330596133THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADINGWANG RongShanCHEN MingYaLU FengZHENG WeiDongWANG DongHuiZHANG YaPingFAN ZhaoThe pressurized thermal shock（ PTS） event poses a potentially significant challenge to the structural integrity of the reactor pressure vessel（ RPV） during the long time operation. In most countries（ with exception of the USA）,proving RPV integrity under the PTS load is based on the deterministic fracture mechanics（ DFM）. In the USA,the "screening criteria"for maximum allowable embrittlement of RPV material,which form part of the USA regulations,are based on the probabilistic fracture mechanics（ PFM）. In this paper,the FAVOR software of Oka Ridge National Laboratory is used to compare the difference between PFM and DFM analysis of the PTS even. The analysis method of FAVOR is shown through case study of the benchmark transient in the IAEA-TECDOC-1627 report. Finally,the limit of the current FAVOR（ Version6. 1） is shown.http://www.jxqd.net.cn/thesisDetails#10.16579/j.issn.1001.9669.2016.04.031Reactor pressure vessel;Pressure thermal shock;Probabilistic fracture mechanical;FAVOR;Long time operation |
| spellingShingle | WANG RongShan CHEN MingYa LU Feng ZHENG WeiDong WANG DongHui ZHANG YaPing FAN Zhao THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING Jixie qiangdu Reactor pressure vessel;Pressure thermal shock;Probabilistic fracture mechanical;FAVOR;Long time operation |
| title | THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING |
| title_full | THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING |
| title_fullStr | THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING |
| title_full_unstemmed | THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING |
| title_short | THE PROBABILISTIC STRUCTURAL INTEGRITY ASSESSMENT OF REACTOR PRESSURE VESSELS UNDER PRESSURIZED THERMAL SHOCK LOADING |
| title_sort | probabilistic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading |
| topic | Reactor pressure vessel;Pressure thermal shock;Probabilistic fracture mechanical;FAVOR;Long time operation |
| url | http://www.jxqd.net.cn/thesisDetails#10.16579/j.issn.1001.9669.2016.04.031 |
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