Literature survey of the mechanisms of neutron irradiation embrittlement of PWR pressure vessel steels
Description
In this note, the mechanisms of irradiation embrittlement in PWR pressure vessel steels is analysed and the influence of metallurgical and irradiation parameters are also discussed. The irradiation embrittlement of pressure vessel steels, as measured by transition temperature shifts, arises mainly from the formation of precipitates and clusters of point defects (dislocation loops, microvoids) within the grains. It is strongly dependent upon the chemical composition; the elements which cause the greatest embrittlement are copper, nickel and phosphorous. Embrittlement increases as the dose rate increases. This phenomenon seems to be related to the fact that the nature of damage depends on this dose rate. An increase in irradiation temperature of 1 deg C induces a decrease in the transition temperature shift of about 0.5 to 1.5 deg C
Additional details
Additional titles
- Original title (French)
- Etude bibliographique des mecanismes de fragilisation par irradiation aux neutrons des aciers de cuves REP
Publishing Information
- Publisher
- Electricite de France.
- Imprint Place
- Clamart (France)
- Imprint Pagination
- 86 p.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 24002530
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- EMBRITTLEMENT; IMPURITIES; MECHANICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; PWR TYPE REACTORS; REACTOR VESSELS; STEEL-MNNIMO; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LOW ALLOY STEELS; MANGANESE ALLOYS; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS