RAMONA-3B/MINET composite representation of BWR thermal-hydraulic systems

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:6496019

Van Tuyle, G J; Slovik, G; Cazzoli, E G; Nepsee, T C; Guppy, J G

The modification and interfacing of two computer codes, RAMONA-3B and MINET, for the thermal hydraulic transient analysis of a Boiling Water Reactor nuclear steam supply system, is described. The RAMONA-3B code provides for multi-channel thermal hydraulics and three-dimensional (or one-dimensional) neutron kinetics analysis of a boiling water reactor core. The RAMONA-3B system representation terminates at the end of the steam line and at the junction of the feedwater line at the vessel inlet. By interfacing RAMONA-3B with MINET, a generic balance-of-plant systems analysis code, a complete BWR systems code with detailed core modeling was obtained. The result is a code of particular importance to the analysis of transients such as ATWS. A comparison between the 3-D and 1-D neutronics representation is provided, along with a test case utilizing the composite RAMONA-3B/MINET code.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6496019
• Report Number(s): BNL-NUREG-37132; CONF-851007-15; ON: TI86002928
• Country of Publication: United States
• Language: English

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