Annealing for plant life management: hardness, tensile and Charpy toughness properties of irradiated, annealed and re-irradiated mock-up low alloy nuclear pressure vessel steel
Description
Hardness, tensile and Charpy properties of an irradiated (I) and irradiated-annealed-reirradiated (IAR) mock-up pressure vessel steel are presented. Spectrum tailored pressurized light water reactor (PWR) irradiation at 290oC by fast neutrons up to nominal fluences of 5 x 1019/cm2 (E ≥ 1 MeV) in a swimming pool type reactor caused the hardness, tensile yield stress and tensile strength to increase. Embrittlement also occurred as indicated by Charpy toughness tests. The optimum annealing heat treatment for the main program was determined using isochronal and isothermal runs on the material and measuring the Vickers microhardness. The response to an intermediate annealing treatment (460oC for 18 h), when 50% of the target fluence has been reached and then irradiating to the required end fluence (IAR condition) was then monitored further by Charpy and tensile mechanical properties. Annealing was beneficial in mitigating overall hardening or embrittlement effects. The rate of re-embrittlement after annealing and re-irradiating was no faster than when no annealing had been performed. Annealing temperatures below 440oC were indicated as requiring relatively long times, i.e. ≥ 168 h to achieve some reduction in radiation induced hardness for example. (Author)
Additional details
Publishing Information
- Journal Title
- International Journal of Pressure Vessels and Piping
- Journal Volume
- 60
- Journal Issue
- 3
- Journal Page Range
- p. 217-222.
- ISSN
- 0308-0161
- CODEN
- PRVPAS
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 26005033
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANNEALING; BENCH-SCALE EXPERIMENTS; CHARPY TEST; HARDNESS; IRRADIATION; MOCKUP; NEUTRON BEAMS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COMPONENTS; STEELS; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BEAMS; CARBON ADDITIONS; CONTAINERS; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NUCLEON BEAMS; PARTICLE BEAMS; POWER REACTORS; REACTORS; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS