Annealing of a VVER-440 reactor pressure vessel in Loviisa
Creators
- 1. IVO Power Engineering Ltd., (United Kingdom)
- 2. VTT Manufacturing Technology (Country Unknown)
Description
Loviisa 1 NPS is a VVER-440 unit of model B-213 of Soviet design. It was the 1. VVER-440 plant with a surveillance program to follow the neutron irradiation embrittlement of the RPV. The 1. surveillance test results in 1980 indicated that the embrittlement of the core weld was much faster than expected. Several mitigations were carried out during the years in Loviisa to ensure the integrity of the RPV and safe operation of the plant. The critical circumferential core weld of Loviisa 1 RPV was annealed during the refuelling and maintenance outage in August 1996. The annealing was carried out by Skoda Nuclear Machinery LTD in a joint consortium with Bohunice Nuclear Power Plant. Loviisa 1 was the 1. VVER-440 RPV of model B-213 that was annealed. VVER-440 RPV's that were earlier annealed in Eastern European Countries were of the older model B-230. The annealing parameters were established based on extensive material investigations and stress analysis. The target annealing temperature was 465 - 505 deg C and the heating/cooling rate less than 20 deg C/h. According to the results of the material investigations about 80% recovery could be expected. The re-embrittlement of the core weld is monitored by a new surveillance program. The life time of the RPV will be estimated later based on the results from the new surveillance program. (authors)
Additional details
Additional titles
- Original title (English)
- Fontevraud 4. Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
- Imprint Pagination
- (v.1) 730 p.
- Journal Page Range
- p. 75-88
Conference
- Title
- International symposium Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
- Dates
- 14-18 Sep 1998
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 31000447
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; CHARPY TEST; EMBRITTLEMENT; FINLAND; FRACTURE MECHANICS; IRRADIATION; LIFETIME; MECHANICAL PROPERTIES; NEUTRONS; PRESSURE VESSELS; RADIATION PROTECTION; RESEARCH PROGRAMS; TRANSITION TEMPERATURE; WWER TYPE REACTORS
- Descriptors DEC
- BARYONS; CONTAINERS; DESTRUCTIVE TESTING; DEVELOPED COUNTRIES; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EUROPE; FERMIONS; HADRONS; HEAT TREATMENTS; IMPACT TESTS; MATERIALS TESTING; MECHANICAL TESTS; MECHANICS; NUCLEONS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SCANDINAVIA; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- 3 refs. Imprint:Fontevraud 4. Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee