Dynamic behavior of a subcooled BWR core during a rod-drop accident

Conference · Tue Jun 01 04:00:00 EDT 1982

OSTI ID:6809730

Cokinos, D; Carew, J

The techniques and models used in the study of rapid reactivity insertion in a BWR have ranged from approximate conservative methods with simple feedback models to detailed representations of coupled neutronic thermal-hydraulic mechanisms. In a recent paper Cheng and Diamond presented a detailed evaluation of the control rod drop accident (CRDA). Their calculations suggested that the effect of inlet subcooling and rod drop speed may play an important role in determining the severity of the rod drop accident. The purpose of the work summarized in this paper has been to determine in detail the dynamic behavior of a BWR core as the inlet moderator temperature and the speed of the dropped rod are varied.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6809730
• Report Number(s): BNL-NUREG-31623; CONF-821103-21; ON: DE82020022
• Country of Publication: United States
• Language: English

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ENERGY TRANSFER
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REACTOR ACCIDENTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS