Effects of rod worth and drop speed on the BWR off-center rod drop accident
Conference
·
OSTI ID:6050293
The purpose of the present study was to determine the effect of increasing the control rod worth and the rod drop speed on the off-center RDA. An increase in either of these parameters results in an increase in peak core power and fuel enthalpy, and the objective of this study is to determine the margin to the fuel damage threshold.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6050293
- Report Number(s):
- BNL-NUREG-37612; CONF-860610-15; ON: TI86006883
- Resource Relation:
- Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ROD DROP ACCIDENTS
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
CONTROL ROD WORTHS
TWO-PHASE FLOW
ACCIDENTS
FLUID FLOW
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
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SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ROD DROP ACCIDENTS
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
CONTROL ROD WORTHS
TWO-PHASE FLOW
ACCIDENTS
FLUID FLOW
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled