Published 1976 | Version v1
Report Restricted

Studies associated with the LWR LOCA-ECC thermal shock

Creators

Description

Thermal shock studies on test specimens fabricated from PWR pressure vessel material are described. The studies are aimed at understanding crack propagation and growth during ECCS quenching following a loss-of-coolant accident

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS. $3.50.

Files

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Additional details

Publishing Information

Imprint Pagination
17 p.
Report number
CONF-760954--4

Conference

Title
4. water reactor safety research information meeting.
Dates
27 - 30 Sep 1976.
Place
Washington, District of Columbia, United States of America (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8321766
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; DEFECTS; ECCS; LOSS OF COOLANT; PRESSURE VESSELS; PWR TYPE REACTORS; THERMAL SHOCK; THERMAL STRESSES
Descriptors DEC
ACCIDENTS; CONTAINERS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS