Published June 1985 | Version v1
Journal article

Coolability study on two-bundle scale flow blockage in the reflood process

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki

Description

A two-bundle scale channel flow blockage in the eight-bundle slab core test facility (SCTF) was examined for core cooling capability study in the reflood phase of a PWR-LOCA. The coplanar blockage with 60% blockage fraction resulted in promotion of quench for the elevation immediately above the blockage in relatively high reflood velocity tests. Conversely, this blockage led to delay of quench in low reflood velocity tests. Peak clad temperature, however, was not affected much by the existence of the blockage. These results are examined in comparison with the results of similar small scale test facilities. This examination revealed that the promotion of quench above the blockage was confined to a shorter length but the quench delay time was slightly longer for a large partial blockage than for a small blockage. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
86
Journal Issue
3
Series
Nucl. Eng. Des.
Journal Page Range
345-355
ISSN
0029-5493
CODEN
NEDEA