Coolability study on two-bundle scale flow blockage in the reflood process
Creators
- 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17019760
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ECCS; FLOW BLOCKAGE; FUEL ASSEMBLIES; HEAT TRANSFER; LOSS OF FLOW; PWR TYPE REACTORS; QUENCHING; REACTOR CORES; SCALE MODELS; SIMULATION; TEMPERATURE DEPENDENCE; TESTING
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS