Published June 1988
| Version v1
Journal article
SCTF-III test plan and recent SCTF-III test results
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
A test plan of the Slab Core Test Facility with Core-III (SCTF-III) has been clarified. The previous SCTF-III tests simulating PWRs with combined-injection-type ECCS indicated the following results on the thermal-hydraulics in the full-radius core: (1) two-region separation and multidimensional thermal-hydraulics both before and after reflood initiation, (2) practically no core cooling in the region far from the water downflow region before reflood initiation in spite of good core cooling in the water downflow region. (3) good core cooling even in the two-phase upflow region after bottom reflood initiation, (4) large fall-back flow rate in comparison with the prediction by a typical one-dimensional correlation. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 108
- Journal Issue
- 1/2
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 241-247
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19084547
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CORE FLOODING SYSTEMS; EFFICIENCY; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS