Preliminary results of steel containment vessel model test

Conference · Wed Apr 01 00:00:00 EST 1998

OSTI ID:305924

Luk, V K; Hessheimer, M F ^[1]; Matsumoto, T; Komine, K; Arai, S ^[2]; Costello, J F ^[3]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Nuclear Power Engineering Corp., Tokyo (Japan)
3. Nuclear Regulatory Commission, Washington, DC (United States)

A high pressure test of a mixed-scaled model (1:10 in geometry and 1:4 in shell thickness) of a steel containment vessel (SCV), representing an improved boiling water reactor (BWR) Mark II containment, was conducted on December 11--12, 1996 at Sandia National Laboratories. This paper describes the preliminary results of the high pressure test. In addition, the preliminary post-test measurement data and the preliminary comparison of test data with pretest analysis predictions are also presented.

• Research Organization: Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 305924
• Report Number(s): NUREG/CP-0162-Vol.3; CONF-9710101-Vol.3; ON: TI98007505; TRN: IM9906%%176
• Resource Relation: Conference: 25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997; Other Information: PBD: Apr 1998; Related Information: Is Part Of Twenty-fifth water reactor safety information meeting: Proceedings. Volume 3: Thermal hydraulic research and codes; Digital instrumentation and control; Structural performance; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 365 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
SCALE MODELS
CONTAINMENT SHELLS
BWR TYPE REACTORS
REACTOR SAFETY EXPERIMENTS
PRESSURIZATION