Preliminary structural analysis of PCRV for 300-MW(e) Gas Cooled Fast Breeder Reactor

Technical Report · Mon May 01 04:00:00 EDT 1978

DOI:https://doi.org/10.2172/6864957· OSTI ID:6864957

Young, G.; Cheung, K. C.

Preliminary elastic and thermal stress analyses were performed for the multicavity PCRV for the GCFR 300-MW(e) Nuclear Steam Supply System using three-dimensional finite-element computer codes. The report includes information on the finite-element model, material properties, and boundary and loading combinations and presents stress results, evaluations, and recommendations. In general, the stress levels were found to be acceptable. The stress levels in the concrete ligaments indicate that the existing PCRV configuration can be optimized by increasing the inner ligament and decreasing the outer ligament. For a more exacting optimization of the ligaments, use of a value of effective modulus of elasticity lower than 0.5 E/sub c/ in the thermal stress analysis should be justified. The two potential problem areas of the PCRV, the cross-duct region and the bottom head, should be further investigated by local analyses. The thermal stress analysis indicated that for normal operating conditions it is feasible to eliminate the peripheral tendons.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• DOE Contract Number: EY-76-C-03-0167-023
• OSTI ID: 6864957
• Report Number(s): GA-A-14857
• Country of Publication: United States
• Language: English

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BREEDER REACTORS
BUILDING MATERIALS
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EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FINITE ELEMENT METHOD
GAS COOLED REACTORS
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GCFR TYPE REACTORS
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REINFORCED CONCRETE
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STRESS ANALYSIS
STRESSES
THERMAL STRESSES
THREE-DIMENSIONAL CALCULATIONS