LMBFR and LWR in-core thermal-hydraulic codes: the state-of-the-art and research and development needs

Conference · Wed Apr 01 00:00:00 EST 1981

OSTI ID:6170547

Khan, E U; Coomes, E P; Rowe, D S; Trent, D S

A review of analytical design methods used for predicting reactor core flow and temperature distributions is presented with emphasis on LMFBR's. The paper also briefly describes and contrasts the methods used for LWR's. These methods are global analysis, subchannel analysis, distributed parameter, and hybrid analysis. The evolution of the local and subchannel analysis methods is presented. Data used for code validation are also presented. Current research and development needs are identified and discussed. Areas identified for future research and development include methods and expermental data for analysis of distorted bundles and natural convection. Methods that have been developed for predicting the safety performance of LMFBR's and LWR's are not within the scope of this paper.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6170547
• Report Number(s): PNL-SA-9536; CONF-810804-12; ON: DE81028018; TRN: 81-016005
• Resource Relation: Conference: 20. national heat transfer conference, Milwaukee, WI, USA, 2 Aug 1981
• Country of Publication: United States
• Language: English

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