Published 1977 | Version v1
Report Metadata-only

Reactor vessel surveillance present practice and future trends in Switzerland

Creators

  • 1. Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)
  • 2. Sulzer Bros. Ltd., Winterthur (Switzerland)
  • 3. Nuclear Safety Div. (ASK), Federal Office of Energy, Wuerenlingen, Switzerland

Description

Surveillance program for the existing LWR-plants. Problems arising from the use of conventional impact test specimens (V-notch). Attempt, to replace these by improved specimens, modelling actual flaws more closely. Choice of specimens in order to get material data, enabling the application of elastic and eventually elastic-plastic fracture mechanics methods. (precracked ISO-V; three point bend specimens) Withdrawal schedule tailored to the individual conditions in a LWR-vessel. (accelerated irradiation of the specimens with respect to the wall, projected properties of material over the life of the reactor). (author)

Additional details

Publishing Information

Imprint Title
Reactor pressure vessel surveillance
Journal Page Range
p. 61-69.
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
9376474
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; FRACTURES; IMPACT STRENGTH; INSPECTION; IRRADIATION; IRRADIATION CAPSULES; NOTCHES; PWR TYPE REACTORS; REACTOR VESSELS; SWITZERLAND; THERMAL FATIGUE
Descriptors DEC
CONTAINERS; EUROPE; FAILURES; FATIGUE; MECHANICAL PROPERTIES; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS