Vessel annealing
Creators
Description
In Finland the reactor pressure vessel at Loviisa-1 is to be annealed to remedy the embrittlement caused by neutron irradiation. The embrittlement can be detected by monitoring changes in the mechanical properties of the pressure vessel steel and welds from tensile test data, hardness and Charpy V-notch transition curves and fracture toughness results. Copper and phosphorus impurities may be the cause of the sensitivity to the neutron irradiation. The annealing programme - a week of heat treatment at 450oC - reduces the effect of irradiation on the shift of the brittle-ductile transition temperature. Other annealing programmes have taken place at the Bohunice and Marble Hill reactors and this may become a routine way of prolonging the life of the reactor. (UK)
Additional details
Additional titles
- Subtitle (English)
- Will it become a routine procedure?
Publishing Information
- Journal Title
- Nuclear Engineering International
- Journal Volume
- 39
- Journal Issue
- 479
- Journal Page Range
- p. 45-48.
- ISSN
- 0029-5507
- CODEN
- NEINBF
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 25052661
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANNEALING; CHARPY TEST; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; LOVIISA-1 REACTOR; NEUTRONS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; REACTOR MAINTENANCE; REACTOR VESSELS; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- BARYONS; CONTAINERS; DESTRUCTIVE TESTING; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT TREATMENTS; IMPACT TESTS; MAINTENANCE; MATERIALS TESTING; MECHANICAL TESTS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS