RAMONA-3B calculations for Browns Ferry ATWS (Anticipated Transient Without Scram) study

Technical Report · Sun Feb 01 04:00:00 EST 1987

DOI:https://doi.org/10.2172/6614081· OSTI ID:6614081

Saha, P; Slovik, G C; Neymotin, L Y

Several aspects of the Anticipated Transient Without Scram (ATWS) initiated by an inadvertent closure of all Main Steam Isolation Valves (MSIV) in a typical BWR/4 are analyzed in the report. The analysis is performed using the Brookhaven National Laboratory code, RAMONA-3B, which employs a three-dimensional neutron kinetics model coupled with a parallel-channel thermal hydraulics in representing a Boiling Water Reactor (BWR) Core. Four different transient scenarios have been investigated: (a) downcomer water level and reactor pressure control, (b) manual control rod insertion transient, (c) high pressure boil-off, and (d) recirculation pump trip failure. Results of these calculations should provide better understanding of mitigative effects of operator actions during ATWS, thus helping in the development of adequate Emergency Procedure Guidelines (EPG) required for the BWR plant safety. A few unresolved questions subject to future investigations are also discussed.

• Research Organization: Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6614081
• Report Number(s): NUREG/CR-4739; BNL-NUREG-52021; ON: TI87007547
• Country of Publication: United States
• Language: English

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