Experimental Study on the Performance of the Passive Safety Injection for Pressure Balance Line Break and Direct Vessel Injection Line Break

Conference · Mon Jul 01 04:00:00 EDT 2002

OSTI ID:21167862

Chang, Chin-Jang ^[1]; Lee, Chien-Hsiung; Hong, Wen-Tang ^[2]; Wang, Lance L.C. ^[3]

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1. Gengood Engineering Corporation, 36, Lane 362, Min Sheng W. Road, Taipei, Taiwan 104 (China)
2. Nuclear Engineering Division, Institute of Nuclear Energy Research, P.O. Box 3-3, Lung-Tan, Taiwan 325 (China)
3. Power Research Institute, Taiwan Power Company, 84, Ta An Road, Shulin, Taipei County, Taiwan 238 (China)

A passive core cooling system (PCCS) has been installed at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility. It includes three core makeup tanks (CMTs), three accumulators (ACCs), a-four stage automatic depressurization system (ADS), a passive residual heat removal (PRHR) heat exchanger submerged into an in-containment refueling water storage tank (IRWST). The purpose of this research is to study the performance of the PCCS with passive injection during either a pressure balance line (PBL) break or a direct vessel injection (DVI) line break. Five experiments were performed simulating break area ratios of 0.5% to 2.0% (1.88 mm to 3.77 mm) at either a PBL or at a DVI-line. The general system response and the interactions of CMT, ACC, PRHR, and IRWST to the effect of core heat removal are observed and discussed. The experimental results show long term core cooling can be reached for the cases of the PBL break and the DVI-line break following the PCCS actuation procedures. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21167862
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
AFTER-HEAT REMOVAL
DEPRESSURIZATION SYSTEMS
HEAT EXCHANGERS
NUCLEAR ENERGY
PERFORMANCE
RHR SYSTEMS
SAFETY INJECTION
TANKS