Evaluation of the influence of seismic restraint characteristics on LMFBR piping

Conference · Mon Jan 01 04:00:00 EST 1979

OSTI ID:6169348

Mallett, R. H.

For the Clinch River Breeder Reactor Plant (CRBRP) heat transport system piping within the reactor containment building, dynamic analyses of the piping loops have been performed to study the effect of restraint stiffness on the dynamic behavior of the piping, i.e., changes in frequencies, mode shapes, loads, stresses, and displacements. In addition, analysis and testing of typical CRBRP restraint system components have been performed for the purpose of quantifying and verifying the basic characteristics of the restraints used in the piping system dynamic analysis. The results are presented of the analysis and testing described above. In particular, it is shown that piping restraint effects on breeder reactor piping response are important considerations in the design/analysis process.

• Research Organization: Westinghouse Electric Corp., Madison, PA (USA). Advanced Reactors Div.
• DOE Contract Number: EY-76-C-15-2395
• OSTI ID: 6169348
• Report Number(s): CONF-790363-2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
PERFORMANCE TESTING
PIPES
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESTRAINTS
SEISMIC EFFECTS
SODIUM COOLED REACTORS
STRESS ANALYSIS
TESTING