The toughness of irradiated pressure water reactor (PWR) vessel shell rings and the effect of segregation zones
- Electricite de France, Moret-sur-Loing (France)
- Framatome, Paris La Defense (France). Materials and Technology Dept.
- Commissariat a l`Energie Atomique, Gif-sur-Yvette (France)
To establish the integrity of pressure water reactor (PWR) vessels it is necessary to determine the toughness of A508Cl.3 steel at the end of its life, that is after thermal aging and irradiation embrittlement. In safety analyses the toughness can be deduced from a reference curve set forth in the code (ASME or RCC-M). The validity of the reference curve has been verified for several years for unirradiated French reactor vessels. Tests were performed on specimens taken from materials having heterogeneities in chemical composition. For most of the test results the reference curve is a lower bound. To solve te problem of determining the toughness of SA 508 Cl.3 steel after irradiation and in the presence of possible heterogeneities, the toughness results were gathered. The synthesis shows that the RCC-M code curve is conservative.
- OSTI ID:
- 524808
- Report Number(s):
- CONF-940657-; TRN: 97:016790
- Resource Relation:
- Conference: 17. symposium on effects of radiation on materials, Sun Valley, ID (United States), 20-23 Jun 1994; Other Information: PBD: 1996; Related Information: Is Part Of Effects of radiation on materials: 17. international symposium; Gelles, D.S. [ed.] [Pacific Northwest National Lab., Richland, WA (United States)]; Nanstad, R.K. [ed.] [Oak Ridge National Lab., TN (United States)]; Kumar, A.S. [ed.] [Univ. of Missouri, Rolla, MO (United States)]; Little, E.A. [ed.] [University College of Swansea (United Kingdom)]; PB: [1175] p.; ASTM special technical publication, 1270
- Country of Publication:
- United States
- Language:
- English
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