Results of the ROSA-IV LSTF small-break LOCA experiments
Creators
- 1. Japan Atomic Energy Research Institute, Ibaraki
Description
The test results are reported on three small-break LOCA experiments recently conducted at the Large Scale Test Facility (LSTF) of the ROSA-IV program. In all of these tests, a break was located horizontally at the side of the cold leg piping (207 mm in diameter). The break sizes tested were equal to 10.0 %, 5.0 % and 2.5 % of the scaled (1/48) flow area of the reference PWR's cold leg. In both the 10 % and 5 % break tests, HPIS was activated early in the transient and the rest of ECCS operated satisfactorily to prevent the major uncovery of the core. However, partial and temporary core dryout was observed early in the 5 % break test, because of the core liquid level depression due to liquid holdup in the SG U-tubes. In the 2.5 % break test, major core uncovery occurred due to boiloff, because of the assumption that HPIS remains inoperative for 1200 s after break
Additional details
Publishing Information
- Imprint Title
- Thirteenth water reactor safety research information meetings proceedings. Volume 4
- Journal Page Range
- p. 157-172.
- Report number
- NUREG/CP--0072-Vol.4
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18002642
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DRYOUT; ECCS; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; PIPES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RUPTURES; TESTING; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS