Thermal fatigue in mixing tees: status and justification of French assessment method
Description
Following the CIVAUX-1 incident of a leak on the reactor heat removal system (RHR), EDF has developed a step by step procedure to screen and analyse similar locations: mixing tees with long duration at high ΔT between the 2 fluids. The paper presents the procedure, the background of the methodology and few development works that support this procedure. The procedure is based on: -) screening criteria on maximum ΔT and minimum duration, -) screening criteria without any duration consideration, only ΔT and material, -) a simplified and conservative estimation of a usage factor, and -) a detailed analysis of usage factor and crack growth rate, based on specific data collection of operating transients. Around that procedure EDF launched a research and development program on fatigue curves and fatigue reduction factors for high cycle fatigue. The procedure is compared with field experience and recent fatigue tests. (author)
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers - ASME
- Imprint Place
- New York (United States)
- ISBN
- 0-7918-4688-1
- Imprint Title
- Proceedings of the 12. international conference on nuclear engineering. Volume 2
- Imprint Pagination
- 864 p.
- Journal Page Range
- p. 197-204
Conference
- Title
- 12. international conference on nuclear engineering - ICONE 12
- Dates
- 25-29 Apr 2004
- Place
- Arlington - Virginia (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 38060066
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CIVAUX-1 REACTOR; CRACK PROPAGATION; LEAKS; PIPES; REACTOR MAINTENANCE; RHR SYSTEMS; RISK ASSESSMENT; THERMAL DEGRADATION; THERMAL FATIGUE
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FATIGUE; MAINTENANCE; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs.