ROSA-AP600 characterization tests and analysis of 1-inch cold leg break test

Conference · Sat Oct 01 00:00:00 EDT 1994

OSTI ID:54604

Schultz, R R; Cozzuol, J M; Shaw, R A ^[1]; Yonomoto, T; Kukita, Y ^[2]

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1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
2. Japan Atomic Energy Research Institute, Ibaraki (Japan)

The ROSA-AP600 facility was built using 1/30.5 power and volume scaling relationships to the Westinghouse AP600 advanced power plant design. The facility, located on the Japan Atomic Energy Research Institute (JAERI) campus in Tokai, Japan, is being used by the U.S. Nuclear Regulatory Commission: (i) to generate data to assess advanced thermal-hydraulic codes (RELAP5/MOD3) and (ii) to study phenomena likely to occur in the AP600 advanced reactor system under selected transient conditions.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
• OSTI ID: 54604
• Report Number(s): NUREG/CP--0139; CONF-9410216--; ON: TI95001469
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTERIZED SIMULATION
HYDRAULICS
JAERI
NUCLEAR POWER PLANTS
REACTOR SAFETY
SAFETY ANALYSIS
TECHNOLOGY ASSESSMENT
THERMAL ANALYSIS
WATER COOLED REACTORS