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ROSA-III is a 1/124 scaled down test facility with electrically heated core designed to study the response of engineered safety features to loss-of-coolant accidents in in commercial BWR. It consists of the following, fully instrumented subsystems:
(a) the pressure vessel with a core simulating four half-length fuel assemblies and control rod;
(b) steam line and feed water line, which are independent open loops;
(c) coolant recirculation system, which consists of two loops provided with a recirculation pump and two jet pumps in each loop;
(d) emergency cooling system, including HPCS, LPCS, LPCI, and ADS.
This is one of the small break LOCA/ECC test series to study the response of a BWR with ECC injection. Run 912 is a 5% split break test at the recirculation pump inlet. The test is initiated with the steam dome pressure at 7.30 MPa, the lower plenum subcooling at 10.8 K, a core inlet flow rate of 16.4 kg/s, and a core heat generation rate of 3.9 MW. The core is quenched after ECCS actuation and at a maximum fuel cladding temperature of 839 K.
Core thermal hydraulics; parallel channel effects and instabilities; void collapse and temperature distribution during pressurization; critical power ratio.
- Y. Anoda et al.:
Experiment Data of Rosa-III Integral Test Run 912 (5% Split Break Test
without HPCS Actuation), JAERI-M 82-010, March 1982
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4 (JAERI-M 9363, Feb. 1981)
- K. Tasaka et al.:
Comparison Report for CSNI International Standard Problem 12 (ROSA-III
Run 912), JAERI-M 82-120 (September 1982) also NEA/CSNI-100