Benchmark analysis for the design of piping systems in advanced reactors

Conference · Fri Jan 01 00:00:00 EST 1993

OSTI ID:6541138

Bezler, P; DeGrassi, G; Braverman, J ^[1]; Hou, Shounien ^[2]

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1. Brookhaven National Lab., Upton, NY (United States)
2. Nuclear Regulatory Commission, Washington, DC (United States)

To satisfy the need for the verification of the computer programs and modeling techniques that will be used to perform the final piping analyses for an advanced boding water reactor standard design, three piping benchmark problems were developed. The problems are representative piping systems subjected to representative dynamic loads with solutions developed using the methods being proposed for analysis for the advanced reactor standard design. It will be required that the combined license holders demonstrate that their solutions to these problems are in agreement with the benchmark problem set. A summary description of each problem and some sample results are included.

• Research Organization: Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6541138
• Report Number(s): BNL-NUREG-48448; CONF-9303103-1; ON: DE93008053
• Resource Relation: Conference: American Society of Mechanical Engineers (ASME) conference on seismic analysis, San Francisco, CA (United States), 22-24 Mar 1993
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
PIPES
DESIGN
BENCHMARKS
DYNAMIC LOADS
FREQUENCY ANALYSIS
REACTOR SAFETY
SEISMIC EFFECTS
ENRICHED URANIUM REACTORS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety