Considerations of the manner of accounting for fast fracture risk in the design of PWR vessels
Creators
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)
Description
The French approach to the prevention of fast fracture in PWR vessels is to consider it as a whole and to choose the most convenient way to meet this general goal from an economic and technical point of view. According to this approach, there are no specific limits imposed on such factors as end of life RTsub(NDT) or neutron fluence, which are taken as criteria in other countries. The RCCM design and construction code specifications on chemical content and RTsub(NDT) for beltline and non-irradiated parts establish a sound basis for safety. However, for the most critical parts, the existence of large margins with respect to fast fracture is demonstrated by analysis for all second, third and fourth category design transients. To this aim, the RCCM code needs to demonstrate specified safety margins, depending on the transient category, for reference defects defined in kind and size, in order to bound realistically any defects which have a chance of occurring in the part during manufacture. This approach, which enables the disclosure of the influence of all significant design factors on fracture risk, ensures the most consistent way to improve design safety. (author)
Additional details
Publishing Information
- Journal Title
- Int. J. Press. Vessels Piping
- Journal Volume
- 25
- Journal Issue
- 1-4
- Series
- Int. J. Press. Vessels Piping.
- Journal Page Range
- 217-229
- ISSN
- 0308-0161
- CODEN
- PRVPA
Conference
- Title
- 4. International Seminar on Assuring Structural Integrity of Steel Reactor Pressure Boundary Components.
- Dates
- 26-27 Aug 1985.
- Place
- Ispra (Italy).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 18065905
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; DEFECTS; FRACTURE MECHANICS; FRACTURES; PRESSURE VESSELS; PWR TYPE REACTORS; SAFETY ANALYSIS; SPECIFICATIONS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS