Westinghouse Nuclear Europe reactor vessel surveillance program
Creators
- 1. Westinghouse Electric Nuclear Energy Systems Europe (WENESE), Brussels (Belgium)
Description
Westinghouse's basic philosophy as to reactor vessel material radiation can be summarized as follows: a) Sufficient data are provided to assess the margin for continued safe operation of the plant. b) Sufficient data are provided to set the heatup-cooldown limitation curves. c) Data are provided to perform a quantitative assessment of reactor vessel integrity. d) Sufficient capsules are provided to develop trend in the irradiation damage and provide sufficient samples for annealing if required. The available data are evaluated in terms of current regulatory rules and guides, and copper-fluence trend curves. In addition, data from accelerated irradiation test programs are reviewed in terms of post-irradiation annealing parameters. The results to date indicate that after a fluence of 3x109 n/cm2 the reactor vessel materials studied exhibited fracture toughness sufficiently high for continued safe operation of the nuclear power plants. (author)
Additional details
Publishing Information
- Imprint Title
- Reactor pressure vessel surveillance
- Journal Page Range
- p. 47-60.
- Report number
- IAEA--202
Conference
- Title
- Technical committee meeting on reactor pressure vessel surveillance.
- Dates
- 17 - 18 May 1976.
- Place
- Plzen, Czechoslovakia.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 9376519
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- INFORMATION NEEDS; INSPECTION; IRRADIATION CAPSULES; PRESSURE VESSELS; SAFETY; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS