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AbstractAbstract
[en] Many Mark-I and Mark-II BWR plants are designed with a steel vessel as the primary containment. Typically, the steel containment vessel (SCV) is enclosed within a reinforced concrete shield building with only a small gap (74-90 mm) separating the two structures. This paper describes finite element analyses performed to evaluate the effects of contact and friction between a steel containment vessel and an outer contact structure when the containment vessel is subjected to large internal pressures. These computations were motivated by a joint program on containment integrity involving the Nuclear Power Engineering Corporation (NUPEC) of Japan, the US Nuclear Regulatory Commission (NRC), and Sandia National Laboratories for testing model containments. Under severe accident loading conditions, the steel containment vessel in a typical Mark-I or Mark-II plant may deform under internal pressurization such that it contacts the inner surface of a shield building wall. (Thermal expansion from increasing accident temperatures would also close the gap between the SCV and the shield building, but temperature effects are not considered in these analyses.) The amount and location of contact and the pressure at which it occurs all affect how the combined structure behaves. A preliminary finite element model has been developed to analyze a model of a typical steel containment vessel con-ling into contact with an outer structure. Both the steel containment vessel and the outer contact structure were modelled with axisymmetric shell finite elements. Of particular interest are the influence that the contact structure has on deformation and potential failure modes of the containment vessel. Furthermore, the coefficient of friction between the two structures was varied to study its effects on the behavior of the containment vessel and on the uplift loads transmitted to the contact structure. These analyses show that the material properties of an outer contact structure and the amount of friction between the two structures can have a significant effect on their behavior. (author). 2 refs., 20 figs
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Source
Canadian Nuclear Society, Toronto, ON (Canada); 560 p; ISBN 0-919784-39-0;
; 1994; (v.1) [20 p.]; 3. International conference on containment design and operation; Toronto, ON (Canada); 19-21 Oct 1994

Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACCIDENTS, ALLOYS, BUILDING MATERIALS, CALCULATION METHODS, CARBON ADDITIONS, COMPOSITE MATERIALS, CONCRETES, CONTAINERS, CONTAINMENT, DATA, ENRICHED URANIUM REACTORS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, NUMERICAL DATA, NUMERICAL SOLUTION, POWER REACTORS, REACTORS, REINFORCED MATERIALS, SAFETY, STEELS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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