Impact of large forging macro-segregations on the reactor pressure vessel surveillance program
Creators
- 1. R and D Division, EDF, 6 quai Watier, 78401 Chatou Cedex (France)
- 2. EDF, CEIDRE, 2 rue Ampere, F- 93206 Saint-Denis (France)
- 3. AREVA NP, Technical Centre, BP 13, 71380 Saint-Marcel (France)
Description
The monitoring of the reactor vessels depends to some extent on the use of the specimens contained in the irradiation capsules of the Pressure Vessel Surveillance Program (PVSP). One of the objectives of the PVSP is the validation of the formulas used to predict irradiation embrittlement. Certain results of the PVSP show atypical kinetics, which extreme cases correspond to over or under embrittlement. The assessment of the tested samples (methodical sampling) made it possible to explain these singularities by an azimuthal variability of the mechanical properties in the unirradiated state linked to the existence of metallurgical heterogeneities: macro-segregations. The presence and distribution of these macro-segregations in the forged shells were explained and quantified within the framework of a vast program of metallurgical description and characterization named 'Large Forging' program. Secondly, the presence of these macro-segregations raises the question of the representative nature of the PVSP. In fact, following the 'Large Forging' program, it appears that zones affected by positive segregation can locally be present at the internal skin of the core shells, the quarter-thickness of the acceptance ring, where the PVSP specimens come from, being for its part a zone with zero or negative segregation. An experimental action based on carrying out toughness tests in strongly and slightly segregated zones, located at the internal skin and at the quarter-thickness of a nozzle shell, made it possible to show that the representative nature of the PVSP is not affected by the presence of the macro-segregations. Finally, it appears that the existence of macro-segregations in the core shells may complicate the analysis of the PVSP results by the scattering it adds to the radiation induced embrittlement itself; but the PVSP representative nature is not challenged. (authors)
Availability note (English)
Available from: SFEN, French Nuclear Energy Society, 5 rue des Morillons, F75015 Paris (France)Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- INIS-FR--08-0342
Conference
- Title
- Fontevraud 6. Contribution of materials investigations to improve the safety and performance of LWRs
- Original Conference Title
- Fontevraud 6. Contribution des expertises sur materiaux a l'amelioration de la surete et des performances des reacteurs a eau legere
- Dates
- 18-22 Sep 2006
- Place
- Fontevraud (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 39034057
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- EMBRITTLEMENT; FORGING; FRACTURE PROPERTIES; INSPECTION; METALLURGICAL EFFECTS; MONITORING; PRESSURE VESSELS; RADIATION EFFECTS; REACTOR VESSELS; SEGREGATION
- Descriptors DEC
- CONTAINERS; FABRICATION; MATERIALS WORKING; MECHANICAL PROPERTIES