Published January 1979 | Version v1
Report Restricted

Experiment requirements for the study of anticipated transients with and without scram

Creators

Description

Characteristics of anticipated transients with and without scram in light water reactors are reviewed. Fuel rod behavior during the most significant events is typified by pellet-cladding-interaction and cladding collapse. A program to simulate selected transients in the Power Burst Facility (PBF) so as to evaluate and understand the fuel behavior in light water reactors is proposed. Experiment requirements are set forth and the capabilities and limitations of the PBF to perform these tests are outlined

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
BWR; PWR

Publishing Information

Imprint Pagination
89 p.
Report number
TFBP-TR--308

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10461194
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; BWR TYPE REACTORS; PBF REACTOR; PWR TYPE REACTORS; REACTOR EXPERIMENTAL FACILITIE; SIMULATION; TRANSIENTS
Descriptors DEC
ACCIDENTS; DESIGN BASIS ACCIDENTS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TANK TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS