Analysis of high pressure boil-off situation during MSIV closure ATWS in a typical BWR/4
Conference
·
OSTI ID:7242988
The objective of this paper is to provide a best-estimate analysis of the MSIV Closure ATWS in the Browns Ferry Unit 1 BWR with Mark 1 containment. The calculations have been performed using the RAMONA-3B code which has a three-dimensional neutron kinetics model coupled with one-dimensional (multi-channel core representation), four-equation, nonhomogeneous, nonequilibrium thermal hydraulics. The code also allows for one-dimensional neutronic core representation. The 1-D capability of the code has been employed in this calculation since a thorough sensitivity study showed that for a full ATWS, a one-dimensional (axial) neutron kinetics adequately describes the core behavior. (Note that the core steady-state symmetry in this case was preserved throughout the transient so that radial effects could be neglected.) The calculation described in the paper was started from a steady-state fuel condition corresponding to the end of Cycle 5 of the Browns Ferry reactor.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 7242988
- Report Number(s):
- BNL-NUREG-38266; CONF-860610-13; ON: TI86013916
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
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MIXED SPECTRUM REACTORS
ONE-DIMENSIONAL CALCULATIONS
POWER REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
KINETICS
MIXED SPECTRUM REACTORS
ONE-DIMENSIONAL CALCULATIONS
POWER REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS