Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants
There have been incidents recently where stress corrosion cracking (SCC) observed in the dissimilar metal weld (DMW) joints connecting the reactor pressure vessel (RPV) nozzle with the hot leg pipe. Due to the complex microstructure and mechanical heterogeneity in the weld region, dissimilar metal w...
Saved in:
| Main Authors: | , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
Gruppo Italiano Frattura
2014-07-01
|
| Series: | Fracture and Structural Integrity |
| Subjects: | |
| Online Access: | https://www.fracturae.com/index.php/fis/article/view/1260 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| _version_ | 1841562308788092928 |
|---|---|
| author | Lingyan Zhao He Xue Fuqiang Yang Yaohong Suo |
| author_facet | Lingyan Zhao He Xue Fuqiang Yang Yaohong Suo |
| author_sort | Lingyan Zhao |
| collection | DOAJ |
| description | There have been incidents recently where stress corrosion cracking (SCC) observed in the dissimilar metal weld (DMW) joints connecting the reactor pressure vessel (RPV) nozzle with the hot leg pipe. Due to the complex microstructure and mechanical heterogeneity in the weld region, dissimilar metal weld joints are more susceptible to SCC than the bulk steels in the simulated high temperature water environment of pressurized water reactor (PWR). Tensile residual stress (RS), in addition to operating loads, has a great contribution to SCC crack growth. Limited experimental conditions, varied influence factors and diverging experimental data make it difficult to accurately predict the SCC behavior of DMW joints with complex geometry, material configuration, operating loads and crack shape. Based on the film slip/dissolution oxidation model and elastic-plastic finite element method (EPFEM), an approach is developed to quantitatively predict the SCC growth rate of a RPV outlet nozzle DMW joint. Moreover, this approach is expected to be a pre-analytical tool for SCC experiment of DMW joints in PWR primary water environment. |
| format | Article |
| id | doaj-art-5029e64c7c164dc69862c1c90ee746d0 |
| institution | Kabale University |
| issn | 1971-8993 |
| language | English |
| publishDate | 2014-07-01 |
| publisher | Gruppo Italiano Frattura |
| record_format | Article |
| series | Fracture and Structural Integrity |
| spelling | doaj-art-5029e64c7c164dc69862c1c90ee746d02025-01-03T01:03:08ZengGruppo Italiano FratturaFracture and Structural Integrity1971-89932014-07-01829Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plantsLingyan ZhaoHe XueFuqiang YangYaohong SuoThere have been incidents recently where stress corrosion cracking (SCC) observed in the dissimilar metal weld (DMW) joints connecting the reactor pressure vessel (RPV) nozzle with the hot leg pipe. Due to the complex microstructure and mechanical heterogeneity in the weld region, dissimilar metal weld joints are more susceptible to SCC than the bulk steels in the simulated high temperature water environment of pressurized water reactor (PWR). Tensile residual stress (RS), in addition to operating loads, has a great contribution to SCC crack growth. Limited experimental conditions, varied influence factors and diverging experimental data make it difficult to accurately predict the SCC behavior of DMW joints with complex geometry, material configuration, operating loads and crack shape. Based on the film slip/dissolution oxidation model and elastic-plastic finite element method (EPFEM), an approach is developed to quantitatively predict the SCC growth rate of a RPV outlet nozzle DMW joint. Moreover, this approach is expected to be a pre-analytical tool for SCC experiment of DMW joints in PWR primary water environment.https://www.fracturae.com/index.php/fis/article/view/1260Stress corrosion cracking |
| spellingShingle | Lingyan Zhao He Xue Fuqiang Yang Yaohong Suo Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants Fracture and Structural Integrity Stress corrosion cracking |
| title | Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| title_full | Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| title_fullStr | Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| title_full_unstemmed | Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| title_short | Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| title_sort | numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants |
| topic | Stress corrosion cracking |
| url | https://www.fracturae.com/index.php/fis/article/view/1260 |
| work_keys_str_mv | AT lingyanzhao numericalinvestigationonstresscorrosioncrackingbehaviorofdissimilarweldjointsinpressurizedwaterreactorplants AT hexue numericalinvestigationonstresscorrosioncrackingbehaviorofdissimilarweldjointsinpressurizedwaterreactorplants AT fuqiangyang numericalinvestigationonstresscorrosioncrackingbehaviorofdissimilarweldjointsinpressurizedwaterreactorplants AT yaohongsuo numericalinvestigationonstresscorrosioncrackingbehaviorofdissimilarweldjointsinpressurizedwaterreactorplants |