Microstructure of the WWER-440 dissimilar weld joints
Description
The basic metallographic microstructures occurring in the welds of the WWER-440 reactor pressure vessel nozzle to the primary safe end are described and documented, and the mechanisms of in-service thermal degradation are briefly discussed. Particular attention is paid to the ferrite-austenite transition region, containing microstructural elements which can cause embrittlement of the material during a NPP operation. The potentially critical places with respect to thermal degradation during reactor operation are: the steep carbon gradient at the fusion boundary of dissimilar welds; the high-density particle cores of segregated zones in the 1st buttering layer; the δ-ferrite containing carbide precipitates as well as the σ-phase particles in the 2nd buttering layer and the spinodal decomposition of δ-ferrite and precipitation of G-phase in the filler metal. (Z.S.) 3 tabs., 18 figs., 11 refs
Additional details
Publishing Information
- Journal Title
- Nucleon
- Journal Issue
- no.3
- Journal Page Range
- p. 31-38.
- CODEN
- NLEQEM
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 26032463
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AGING; AUSTENITE; EMBRITTLEMENT; FERRITES; MICROSTRUCTURE; NOZZLES; PIPES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; THERMAL DEGRADATION; WELDED JOINTS; WWER TYPE REACTORS
- Descriptors DEC
- CARBON ADDITIONS; CONTAINERS; COOLING SYSTEMS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; FERRIMAGNETIC MATERIALS; IRON ALLOYS; JOINTS; MAGNETIC MATERIALS; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS