Experimental Study on the Performance of IIST Passive Core Cooling System
Conference
·
OSTI ID:21072847
- Institute of Nuclear Energy Research P.O. Box 3-3, Longtan, 32500, Taiwan (China)
- Gengood Engineering Corporation, No. 36, Lane 362, Ming-Sheng W. Road, Taipei, Taiwan (China)
- Taiwan Power Company, 62, Yeh-Hai St, Kung-Liao, Taipei County, 238, Taiwan (China)
The purpose of this study is to conduct the experiments at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility for evaluation of the performance of the passive core cooling system (PCCS) during the cold-leg small break loss-of-coolant accidents (SBLOCAs). Five experiments were performed with (1) three different break sizes, 2%, 0.5%, and 0.2% (approximately corresponding to 1 1/4'', 2'', and 4'' breaks for Maanshan nuclear power plant), and (2) 0.2% and 0.5% without actuation of the first-stage and third-stage automatic depressurization valve (ADS-1 and ADS-3) to initiate PCCS for assessing its capacity in accident management. The detailed descriptions of general system response and the interactions of core makeup tanks (CMTs), accumulators (ACCs), automatic depressurization system (ADS), passive residual heat Removal (PRHR), and in-containment refueling water storage tank (IRWST) on the core heat removal are included. The results show: (1) core long term cooling can be maintained for all cases following the PCCS procedures, (2) the core can be covered for the cases of the 0.2% and 0.5% breaks without actuation of ADS-1 and ADS-3. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 21072847
- Country of Publication:
- United States
- Language:
- English
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