Investigation of the applicability and limitations of the ROSA Large-Scale Test Facility for AP600 safety assessment

Technical Report · Tue Dec 01 04:00:00 EST 1992

OSTI ID:10116898

Ortiz, M G; Fisher, J E; Cozzuol, J M; Boucher, T J; Sloan, S M; Modro, S M ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

A comparison of the thermal hydraulic behavior of the Advanced Passive 600 MW(e) (AP600) and the Rig of Safety Assessment (ROSA) Large-Scale Test Facility (LSTF), under similar initial and boundary conditions, was developed through computer simulations of selected accident scenarios for the Nuclear Regulatory Commission. The purpose of the comparison was to develop criteria to evaluate the capability of a scaled integral facility to perform an AP600 safety assessment. It was concluded that ROSA LSTF, with a minimum of required modifications, is capable of reproducing most of the phenomena and behavior expected of AP600; distortions become important for slow transients and cases in which the nonsymmetric behavior of AP600 is relevant.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 10116898
• Report Number(s): NUREG/CR--5853; EGG--2670; ON: TI93005664
• Country of Publication: United States
• Language: English

Related Subjects

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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
R CODES
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAFETY ANALYSIS
TRANSIENTS