Published May 1980 | Version v1
Journal article Metadata-only

Review and comparison among the different models for rewetting in LWR's

Creators

  • 1. Illinois Univ., Urbana (USA). Nuclear Engineering Program

Description

Rewetting of light water reactor fuel rods after a loss of coolant accident corresponds to the re-establishment of water contact with the hot surfaces. A considerable number of analytical and numerical models have been developed in order to solve the heat conditions problem in the fuel pin and predict the rewetting velocity. A comparison among the existing models has been performed. Recommendations and suggestions are outlined. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
58
Journal Issue
1
Series
Nucl. Eng. Des.
Journal Page Range
33-44
ISSN
0029-5493

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
11554991
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
BWR TYPE REACTORS; CLADDING; ECCS; FUEL CANS; FUEL RODS; FUNCTIONAL MODELS; LOSS OF COOLANT; PWR TYPE REACTORS; REWETTING
Descriptors DEC
ACCIDENTS; DEPOSITION; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SURFACE COATING; WATER COOLED REACTORS; WATER MODERATED REACTORS