Analyses of a steel containment vessel with an outer contact structure under severe internal overpressurization conditions
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 (50--90mm) 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.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10185163
- Report Number(s):
- SAND--93-2698C; CONF-941011--5; ON: DE94019179; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SHELLS
CONTAINMENT SYSTEMS
DYNAMIC LOADS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
PRESSURE DEPENDENCE
PRESSURIZATION
REACTOR SAFETY
REACTOR VESSELS
SAFETY ANALYSIS
STRESS ANALYSIS