Published 1978 | Version v1
Journal article Metadata-only

Studies on Zircaloy fuel clad ballooning in a loss-of-coolant accident--results of burst tests with indirectly heated fuel rod simulators

Creators

  • 1. Kernforschungszent Karlsruhe, Ger

Description

Burst tests with indirectly heated fuel rod simulators were performed under cooling and temperature conditions postulated for a loss-of-coolant accident (LOCA) of a pressurized water reactor (PWR). The tests were designed to investigate the ballooning behavior of Zircaloy fuel rod claddings and to determine the resulting coolant channel blockage in a rod bundle. The deformation behavior of the Zircaloy cladding tubes was found to be influenced mainly by local effects due to nonuniform temperature distributions. Single rod and bundle tests exhibited large azimuthal and axial temperature differences. This resulted in relatively small and axially limited strains of the Zircaloy cladding tubes and a tolerable coolant channel blockage in the rod bundle. 4 refs

Additional details

Publishing Information

Journal Title
Am. Soc. Test. Mater., Spec. Tech. Publ.
Journal Issue
no.681
Series
Am. Soc. Test. Mater., Spec. Tech. Publ.
ISSN
0066-0558

Conference

Title
4. symposium on zirconium in the nuclear industry.
Dates
27 - 29 Jun 1978.
Place
Stratford-on-Avon, UK.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11558779
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFORMATION; FUEL CANS; LOSS OF COOLANT; PWR TYPE REACTORS; SIMULATION; ZIRCALOY
Descriptors DEC
ACCIDENTS; ALLOYS; REACTOR ACCIDENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Secondary number(s)
CONF-780637--.