Published October 1995
| Version v1
Miscellaneous
Management of reactor pressure vessel irradiation embrittlement at the Loviisa nuclear power plant
- 1. Imatran Voima Oy (IVO), Helsinki (Finland)
- 2. Technical Research Centre of Finland, Espoo (Finland)
Description
At the Loviisa nuclear power plant, irradiation embrittlement of the reactor pressure vessel was found to be much higher than expected. Most of the measures available to reduce the neutron dose to the reactor pressure vessel and to soften thermal shock transients were taken. A utility has been prepared for the annealing of the RPV of Unit 1 in 1996. The new research programmes to support the annealing processes are focused on consistent and improved neutron dose estimates and on creation of annealing and re-embrittlement databases. The amount of the original surveillance material, especially of welds, being limited, every effort was made to utilize the available material as effectively as possible. 4 refs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international topical meeting on VVER safety
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 66-69.
- Report number
- INIS-mf--14715
Conference
- Title
- International topical meeting on VVER safety.
- Dates
- 21-23 Sep 1995.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27022809
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; LOVIISA-1 REACTOR; LOVIISA-2 REACTOR; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; SAFETY ANALYSIS; THERMAL SHOCK
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; POWER REACTORS; PWR TYPE REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS