Published September 1992 | Version v1
Report Metadata-only

Advanced properties of structural materials for nuclear equipment in Eastern countries

Creators

  • 1. Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren

Description

The paper gives a survey of material problems of key components of primary circuit of WWER (PWR) type of reactors as they arose during their development and operation. The paper also summarizes main parameters and material properties of these components together with research and development programmes that are in progress in this field in countries operating WWER type of reactors. (author). 2 refs, 6 figs, 8 tabs

Part of:
Materials for advanced water cooled reactors

Additional details

Publishing Information

Imprint Title
Materials for advanced water cooled reactors
Imprint Pagination
163 p.
Journal Page Range
p. 19-27.
ISSN
1011-4289
Report number
IAEA-TECDOC--665

Conference

Title
Technical committee meeting on materials for advanced water cooled reactors.
Dates
14-17 May 1991.
Place
Plzen (Czechoslovakia).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
24002491
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
PRIMARY COOLANT CIRCUITS; REACTOR COMPONENTS; REACTOR MATERIALS; RESEARCH PROGRAMS; REVIEWS; WWER TYPE REACTORS
Descriptors DEC
COOLING SYSTEMS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information