Assessment of TRAC-BD1 amd RAMONA-3B codes fpr BWR ATWS application
Conference
·
OSTI ID:6026726
Based on comparisons between the TRAC-BD1 power imposed calculation and the RAMONA-3B results, it can be said that the thermal-hydraulic models of both RAMONA-3B and TRAC-BD1 provide adequate representation of an ATWS event in a BWR. However, for the reactor power calculation, RAMONA-3B with space-time neutron kinetics is a superior and preferable tool to the TRAC-BD1 with point kinetics for ATWS type events where the spatial core power distribution varies with time. Also, the computer running time for RAMONA-3B (with 115 hydraulic cells and 192 neutronic cells has been found to be about four times lower than TRAC-BD1 (with 63 hydraulic cells and point kinetics). Therefore, it is recommended that RAMONA-3B be further used for best-estimate analysis of BWR ATWS-type events.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6026726
- Report Number(s):
- BNL-NUREG-35582; CONF-8410142-82; ON: TI85006563
- Country of Publication:
- United States
- Language:
- English
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Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
CLOSURES
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
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FLOW REGULATORS
R CODES
REACTOR ACCIDENTS
REACTORS
T CODES
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS