Published 1977 | Version v1
Report

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