Core subchannel thermal-hydraulic analysis methods and critical heat-flux margin in a light-water breeder reactor

Technical Report · Sun May 01 04:00:00 EDT 1983

OSTI ID:5626200

Misiewicz, R; Kast, S J; Wunderlich, L H

Analyis methods and results are described for critical heat flux (CHF) performance margin in the core of an advanced light water moderated breeder reactor design concept. The 1000 MWe breeder reactor is basically like a large commercial pressurized water reactor (PWR); however, a number of core design features require special consideration with regard to predicting margin to CHF design limits. Three notable features are: (1) fuel rods closely spaced in a triangular pitch lattice; (2) high power seed fuel regions adjacent to low power blanket regions in an open lattice; and (3) power producing thoria shim rods enclosed in individual guide tubes. CHF performance of the breeder core was analyzed with the HOTROD and COBRA computer codes.

• Research Organization: Knolls Atomic Power Lab., Schenectady, NY (USA)
• DOE Contract Number: AC12-76SN00052
• OSTI ID: 5626200
• Report Number(s): KAPL-4158; ON: DE84000818
• Country of Publication: United States
• Language: English

Related Subjects

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LWBR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
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