Non-condensable gas effects in ROSA/AP600 small-break LOCA experiments

Book · Sat Jun 01 04:00:00 EDT 1996

OSTI ID:234279

Nakamura, Hideo; Kukita, Yutaka ^[1]; Shaw, R A; Schultz, R R ^[2]

---

1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
2. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

Integral experiments simulating the postulated accidents in the Westinghouse AP600 reactor have been conducted using the ROSA-V Large Scale Test Facility (LSTF). These experiments allowed the N{sub 2} gas for the pressurization of accumulator tanks to enter the primary system after the depletion of the tank water inventory. The gas migrated into the Passive Residual Heat Removal (PRHR) system heat exchanger tubes and into the Core Makeup Tanks (CMTs), and influenced the performance of these components which are unique to the AP600 reactor. Specifically, the PRHR was disabled soon after the N{sub 2} gas discharge in most of the experiments, although the core decay power was removed well by the steam discharge through the Automatic Depressurization System (ADS) after the PRHR was disabled. The N{sub 2} gas ingress into the CMTs occurred in the experiments with relatively large breaks ({ge} 2 inch in equivalent diameter), and contributed to a smooth draindown of the CMT inventory into the primary system.

• OSTI ID: 234279
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL DATA
GAS FLOW
LOSS OF COOLANT
NITROGEN
PERFORMANCE
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR SAFETY EXPERIMENTS
TEST FACILITIES