Published June 1979 | Version v1
Report Restricted

Thermal analysis of a one-element PWR spent fuel shipping cask

Creators

Description

The transient thermal behavior of a typical one-element PWR spent fuel shipping cask, following a hypothetical accident and fire, has been simulated. The objectives of the study were to determine the transient behavior of the cask and its spent fuel primary coolant through the pressure relief system and possible fuel pin clad failure due to overheating following loss of coolant. 15 figures, 7 tables

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01.

Files

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

Additional details

Publishing Information

Imprint Pagination
49 p.
Report number
HEDL-TME--78-105

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10494710
Subject category
S42: ENGINEERING;
Descriptors DEI
ACCIDENTS; CASKS; FIRES; PWR TYPE REACTORS; SIMULATION; TRANSIENTS
Descriptors DEC
CONTAINERS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS