Published 1997 | Version v1
Book Metadata-only

Brittleness mechanisms of pressure vessels steels under irradiation

Creators

  • 1. Electricite de France, 77 - Moret sur Loing (France). Dept. EMA
  • 2. Ecole Polytechnique, 91 - Palaiseau (France). CEREM, Commission d'Etudes et de Recherches pour les Economies de Matieres Premieres
  • 3. Universite des Sciences et technologies de Lille, 59 - Villeneuve d'Ascq (France)

Description

In this article is recalled the experiment feedback concerning the irradiation effects on ferritic steels. Is given too some historical aspects of the proposed ideas to explain these effects. The current knowledge on the irradiation damage is described. At last, is introduced the model generally retained to explain the increase of ductile-fragile transition temperature of steels from this damage. (O.M.)

Part of:
Materials damage in PWR nuclear power plants

Additional details

Additional titles

Original title (French)
Mecanismes de fragilisation des aciers de cuve sous irradiation

Publishing Information

Publisher
Editions Eyrolles
Imprint Place
Paris (France)
Imprint Title
Materials damage in PWR nuclear power plants
Imprint Pagination
206 p.
Journal Page Range
p. 173-181

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
30003374
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Descriptors DEI
ATOMIC CLUSTERS; EMBRITTLEMENT; FERRITIC STEELS; IRRADIATION; LOW ALLOY STEELS; POINT DEFECTS; PRESSURE VESSELS; PWR TYPE REACTORS; SEGREGATION
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
8 refs. Imprint:Endommagement des materiaux dans les centrales nucleaires a eau pressurisee