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Steam generator tube rupture study

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dc.contributor.author Free, Scott Thomas en_US
dc.contributor.author Schor, Andrei L. en_US
dc.contributor.other Massachusetts Institute of Technology. Energy Laboratory. en_US
dc.date.accessioned 2011-08-05T19:55:39Z
dc.date.available 2011-08-05T19:55:39Z
dc.date.issued 1986 en_US
dc.identifier.uri http://hdl.handle.net/1721.1/65100
dc.description.abstract This report describes our investigation of steam generator behavior during a postulated tube rupture accident. Our study was performed using the steam generator, thermal-hydraulic analysis code THERMIT-UTSG. The purpose of our work was to provide an independent assessment of the Los Alamos National Laboratory system code TRAC-PF1 with respect to steam generator tube rupture analysis. Results of our work are presented and compared with previous TRAC-PF1 results. There are substantial differences in the results of the two codes. These discrepancies are discussed and deficiencies in both codes are noted. Our results lead us to believe that further investigation and code development are necessary to gain more than a basic understanding of steam generator behavior during such accidents and to provide a simulation capability that is acceptable. en_US
dc.format.extent vi, 89 leaves en_US
dc.publisher Cambridge, Mass. : Energy Laboratory, Massachusetts Institute of Technology, 1986 en_US
dc.relation.ispartofseries Working paper (Massachusetts Institute of Technology. Energy Laboratory) ; MIT-EL 86-006WP. en_US
dc.title Steam generator tube rupture study en_US
dc.identifier.oclc 25207879 en_US


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