Structural integrity assessment for internal crack in RPV shell
- 1. Toshiba Energy Systems & Solutions Corporation, Yokohama, Kanagawa (Japan)
- 2. Toshiba Energy Systems & Solutions Corporation, Kawasaki, Kanagawa (Japan)
- 3. Tokyo Electric Power Company Holdings, Inc., Tokyo (Japan)
Description
When quasi-laminar defects are detected in the RPV shell, these defects are modeled to single circular crack with a diameter of 2α and an angle of β from RPV wall enveloping these micro-defects like as the model used in the structural integrity assessment for Doel-3. An acceptable crack size is investigated for fracture assessment and initial crack size considering the fatigue crack growth by 60 years operation due to the JSME Fitness-for-Service (FFS) code. It was found that the initial crack with 2α of 4% smaller than the acceptance crack for fracture at the same location is accepted to exist. Although some discrepancies between Appendices E-1 and E-5 of the JSME FFS code exist for the treatment of internal crack, the structural integrity assessment can be performed for internal crack with some conservative assumptions. (author)
Additional details
Additional titles
- Original title (Japanese)
- RPV銅板の内部亀裂に対する構造健全性評価
Publishing Information
- Imprint Title
- Proceedings of the 15th annual meeting of Japan Society of Maintenology
- Imprint Pagination
- [516 p.]
- Journal Page Range
- p. 215-218
Conference
- Title
- 15. annual meeting of Japan Society of Maintenology
- Dates
- 10-12 Jul 2018
- Place
- Fukuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51102290
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ASPECT RATIO; CORROSION FATIGUE; CRACK PROPAGATION; CRACKS; FERRITIC STEELS; FINITE ELEMENT METHOD; IN-SERVICE INSPECTION; NUCLEAR POWER PLANTS; REACTOR MAINTENANCE; REACTOR VESSELS; STRESS INTENSITY FACTORS
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CONTAINERS; DIMENSIONLESS NUMBERS; FATIGUE; INSPECTION; IRON ALLOYS; IRON BASE ALLOYS; MAINTENANCE; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL SOLUTION; OPERATION; POWER PLANTS; REACTOR LIFE CYCLE; REACTOR OPERATION; STEELS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 2 refs., 7 figs. Imprint:#65E5##672C##4FDD##5168##5B66##4F1A##7B2C#15#56DE##5B66##8853##8B1B##6F14##4F1A##8981##65E8##96C6#