Published February 1976 | Version v1
Report Restricted

Appendix H to RESAR-3S containment functional design

Creators

Description

Following a design basis accident, a pressure is built up in the containment as a result of steam and hot water being spilled on the containment floor. This material is presented in order that the containment functional design may be verified as safe. Also included in this material is a method to verify the adequacy of the internal structures within the containment

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
v p.
Report number
WCAP--8669

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
7268757
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CONTAINMENT SYSTEMS; DESIGN BASIS ACCIDENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPECIFICATIONS; WESTINGHOUSE STANDARD REACTOR
Descriptors DEC
ACCIDENTS; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Westinghouse Electric Corp., Pittsburgh, PA.