Published 2003 | Version v1
Book Metadata-only

Effect of technological tempering and neutron irradiation on degradation of anticorrosive cladding metal properties of water-moderated reactor pressure vessels

Creators

  • 1. FGUP TsNII KM Prometej, Sankt-Peterburg (Russian Federation)

Description

no abstract available

Part of:
VII Russian conference on reactor material science. Abstracts

Additional details

Additional titles

Original title (Russian)
Влияние технологического отпуска и нейтронного облучения на деградацию свойств металла антикоррозионной наплавки корпусов реакторов водо-водяного типа

Publishing Information

Publisher
FGUP GNTs RF NIIAR
Imprint Place
Dimitrovgrad (Russian Federation)
ISBN
5-94831-020-5
Imprint Title
VII Russian conference on reactor material science. Abstracts
Imprint Pagination
424 p.
Journal Page Range
p. 217, 218

Conference

Title
7. Russian conference on reactor material science
Original Conference Title
VII Rossijskaya konferentsiya po reaktornomu materialovedeniyu
Dates
8-12 Sep 2003
Place
Dimitrovgrad (Russian Federation)

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
35079210
Subject category
S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
No Abstract, Conference
Descriptors DEI
CLADDING; CORROSION RESISTANT ALLOYS; EMBRITTLEMENT; NEUTRON FLUENCE; PRESSURE VESSELS; TEMPERING; TIME DEPENDENCE; WWER TYPE REACTORS
Descriptors DEC
ALLOYS; CONTAINERS; DEPOSITION; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:VII Rossijskaya konferentsiya po reaktornomu materialovedeniyu. Tezisy dokladov