Topical report on dynamic analysis of reactor vessel internals under loss- of-coolant accident conditions with application of analysis to CE MWe class reactors
In the design process of nuclear reactor vessel internals, hypothetical accidents are postulated and the dynamic response of the reactor vessel internals to these accidents is examined. The incident considered is the loss-of-coolant accident resulting from a double-ended pipe rupture in the primary coolant system. A safe shutdown earthquake is assumed to occur simultaneously. The methodology that is used to analyze the dynamic response of reactor vessel internals under these accident conditions is described. The dynamic analysis computer programs utilized are discussed, together with their verification. The dynamic analysis methods are applied to C-E pressurized water reactors of the 800 MW(e) class. Results are obtained in terms of stresses and displacements and compared to allowables. These results obtained for the 800 MW(e) class reactors show that at no time during or after the above postulated incidents do the displacements or stresses exceed the established allowables. (auth)
- Research Organization:
- Combustion Engineering, Inc., Windsor, Conn. (USA). Nuclear Power Dept.
- NSA Number:
- NSA-29-020214
- OSTI ID:
- 4330356
- Report Number(s):
- CENPD-42(Rev.1-1)
- Resource Relation:
- Other Information: Orig. Receipt Date: 30-JUN-74
- Country of Publication:
- United States
- Language:
- English
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