Published 1989 | Version v1
Book Metadata-only

Corrosion fatigue strength of VVER-440 RPV steel base and weld metal

Creators

  • 1. TZNII KM Prometei, Leningrad (USSR)
  • 2. Imartran Volma Oy, Vantaa (Finland)
  • 3. Technical Research Centre of Finland, Espoo (Finland)

Description

This paper investigates fatigue crack resistance in high temperature water environment of structure materials used for reactor case production and determination of temperature and previous neutron irradiation effect on a crack growth rate in water environment

Additional details

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structural mechanics in reactor technology
Imprint Pagination
257 p.
Series
LWR pressure components.
Journal Page Range
p. 177-182.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21075941
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION FATIGUE; CRACK PROPAGATION; FRACTURE MECHANICS; POWER REACTORS; REACTOR SAFETY; STEELS; WELDED JOINTS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; FATIGUE; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICAL PROPERTIES; MECHANICS; REACTORS; SAFETY

Optional Information

Secondary number(s)
CONF-890855--.