Published 1977 | Version v1
Book Metadata-only

Fuel rod cladding temperature during film boiling

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls

Description

A program for characterizing the behavior of PWR fuel rods during and after film boiling caused by a power-cooling-mismatch (PCM) accident is described. A brief description of the experimental hardware and test results, comparisons of experimental and analytical results of departure from nucleate boiling and film boiling during a PCM event, and the conclusions that can be drawn from the information obtained to date in the program are presented

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL
Imprint Title
Thermal reactor safety. Vol. II
Journal Page Range
p. 549-560.

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
10437396
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEPARTURE NUCLEATE BOILING; FILM BOILING; FUEL RODS; POWER-COOLING-MISMATCH ACCIDEN; PWR TYPE REACTORS; SPATIAL DISTRIBUTION
Descriptors DEC
ACCIDENTS; BOILING; DISTRIBUTION; FUEL ELEMENTS; NUCLEATE BOILING; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS