Published September 1977 | Version v1
Report Metadata-only

Structural integrity of water reactor pressure boundary components. Progress report ending 31 May 1977

Creators

Description

This report describes research progress in a continuing program to characterize materials properties performance with respect to structural integrity of light water reactor pressure boundary components. Progress for this reporting period is summarized in the following areas: (a) evaluation of critical factors in fatigue crack growth rate studies in a pressurized water reactor environment; (b) fractographic observations of fatigue crack propagation; (c) the IARAR program and its objectives; (d) the effect of submerged arc welding on the notch toughness of low upper shelf A302-B plate exhibiting a low upper shelf and its weld HAZ, and (e) surveys of foreign research related to the safety of light water reactors in Japan, United Kingdom, France, and Germany

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS.

Additional details

Publishing Information

Imprint Pagination
49 p.
Report number
NRL/NUREG/MR--3600

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9365864
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Progress Report
Descriptors DEI
CRACKS; FATIGUE; MATERIALS TESTING; MECHANICAL PROPERTIES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STEELS; WATER COOLED REACTORS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; COOLING SYSTEMS; IRON ALLOYS; IRON BASE ALLOYS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; TRANSITION ELEMENT ALLOYS; WATER MODERATED REACTORS