Benchmark analysis for the design of piping systems in advanced reactors
Conference
·
OSTI ID:6541138
- Brookhaven National Lab., Upton, NY (United States)
- 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:
- NRC; 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
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Boiling Water Cooled
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BENCHMARKS
BWR TYPE REACTORS
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210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
BENCHMARKS
BWR TYPE REACTORS
DESIGN
DYNAMIC LOADS
ENRICHED URANIUM REACTORS
FREQUENCY ANALYSIS
PIPES
POWER REACTORS
REACTOR SAFETY
REACTORS
SAFETY
SEISMIC EFFECTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS