Effects of subcooling and rod drop speed on the BWR rod drop accident
The techniques and models used in the analysis of the control rod drop accident (CRDA) in a BWR have ranged from approximate conservative methods with a simple feedback model to detailed representations of the thermal-hydraulic and neutronic mechanisms. In a recent paper Cheng and Diamond presented a detailed evaluation of the CRDA and the effects of varying a number of important accident parameters. Their calculations performed with the BNL-TWIGL core dynamics code, have shown that the effect of inlet subcooling and rod drop speed 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 dependence of the rod drop accident parameters on the (1) inlet subcooling; and (2) rod drop speed.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5338978
- Report Number(s):
- BNL-NUREG-30722; CONF-820609-10; ON: DE82010624; TRN: 82-015952
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Los Angeles, CA, USA, 6 Jun 1982
- Country of Publication:
- United States
- Language:
- English
Similar Records
Two-dimensional dynamic analysis of a BWR rod-drop accident
Analyzing the rod drop accident in a boiling water reactor
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ROD DROP ACCIDENTS
MATHEMATICAL MODELS
REACTOR KINETICS
ACCIDENTS
KINETICS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled