Containment Performance of Prototypical Reactor Containments Subjected to Severe Accident Conditions
DIANE Publishing, Aug 1, 2000 - 230 pages
Addresses containment design practices and compares the 2 different material types (steel and concrete). Various failure modes are evaluated and computed in previous containment designs. Margin in steel and concrete containment was compared by designing and analyzing a set of surrogate containment. The containment chosen encompass the primary types of containment shapes and construction materials. For compatibility, each containment has an identical internal volume and design pressure and temperature. These containments are designed according to all applicable code requirements for nuclear reactor containment structures.
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accident pressure allowable stress analysis ASME ASME Code baseslab behavior bellows bending buckling CCFP compressive compressive stress computed Concrete Surrogate conditional containment failure containment failure probability Containment Pressure containment structures cylinder deformation design pressure determined deterministic dome elastomeric seal equipment hatch factor of safety failure modes failure strain finite element Free-Field Hoop Strain hoop stress hoop tendons in/in internal pressure capacity liner tear loading combinations material properties meridional Meridional Stresses modes of failure normally Nuclear Overpressure Fragility Curves personnel airlock Pressure Vessel prestressed concrete containments probabilistic probability of failure psig radial random variable rebar reinforced concrete containment reinforcing steel result review level pressures safety goal Sandia National Laboratories Section Service Level severe accident shell shown in Figure sleeve spherical steel and concrete Steel Surrogate stress-strain stress-strain curves surrogate containment designs surrogate steel containments tensile tensile stress thickness typical ultimate strength uncertainty weld yield strength yield stress
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Page 3-2 - Creek steel containment shell will be designed in accordance with the ASME Boiler and Pressure Vessel Code, Section...
Page xvi - Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements...
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