Published 1977 | Version v1
Book Metadata-only

Containment ice-condenser analysis using the COMPARE code

Creators

  • 1. Los Alamos Scientific Lab., NM

Description

Modifications to the COMPARE code, which calculates a transient subcompartment pressure response, are described for an ice-condenser nuclear power plant. Results are compared with RELAP4/MOD5 and with test data. Parameter variations studied include heat transfer coefficient, entrainment factor and initial ice-compartment temperature

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL
Imprint Title
Thermal reactor safety. Vol. III
Journal Page Range
p. 719-732.

Conference

Title
Thermal reactor safety meeting.
Dates
31 Jul - 5 Aug 1977.
Place
Sun Valley, ID, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10437318
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; COMPUTER CALCULATIONS; CONTAINMENT SYSTEMS; HEAT TRANSFER; HYDRODYNAMICS; ICE CONDENSERS; PWR TYPE REACTORS
Descriptors DEC
COMPUTER CODES; CONTAINMENT; ENERGY TRANSFER; FLUID MECHANICS; MECHANICS; REACTORS; STEAM CONDENSERS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS