Published 1997 | Version v1
Book Metadata-only

Aging by irradiation of stainless steel components

Creators

  • 1. FRAMATOME, 92 - Paris-La-Defence (France)
  • 2. Electricite de France, 77 - Moret sur Loing (France). Dept. EMA

Description

The aim of this article is to summarize the current knowledge of all the aging phenomena under irradiation of austenitic stainless steels (304L, 316L) internal components of PWR pressure vessel. The embrittlement and cracks mechanisms are identified and discussed as well as the possible improvements of nowadays. (O.M.)

Part of:
Materials damage in PWR nuclear power plants

Additional details

Additional titles

Original title (French)
Vieillissement par irradiation des pieces en aciers inoxydables

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. 107-120

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
30003371
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
AGING; AUSTENITIC STEELS; CRACKS; CREEP; HARDENING; HELIUM EMBRITTLEMENT; HYDROGEN EMBRITTLEMENT; IRRADIATION; PRESSURE VESSELS; PWR TYPE REACTORS; STAINLESS STEELS; STRESS CORROSION; SWELLING
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CONTAINERS; CORROSION; DEFORMATION; EMBRITTLEMENT; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

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