Show simple item record

dc.contributor.authorSmith, Russell Charlesen_US
dc.contributor.authorRohsenow, Warren M.en_US
dc.contributor.authorKazimi, Mujid S.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.otherU.S. Nuclear Regulatory Commissionen_US
dc.date.accessioned2014-09-16T23:37:23Z
dc.date.available2014-09-16T23:37:23Z
dc.date.issued1980en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89739
dc.description"June 1980."en_US
dc.descriptionAlso issued as a Ph. D. thesis by the first author, MIT Dept. of Nuclear Engineering, 1980en_US
dc.descriptionIncludes bibliographical references (pages 110-111)en_US
dc.description.abstractA mathematical model for direct-contact boiling heat transfer between immiscible fluids was developed and tested experimentally. The model describes heat transfer from a hot fluid bath to an ensemble of droplets of a cooler fluid that boils as it passes through the hot fluid. The mathematical model is based on single bubble correlations for the heat transfer and a drift-flux model for the fluid dynamics. The model yields a volumetric heat transfer coefficient as a function of the initial diameter, velocity and volume fraction of the dispersed component. An experiment was constructed to boil cyclopentane droplets in water. The mathematical and experimental results agreed reasonably well. The results were applied to investigate the possibility of steel vaporization during a hypothetical core disruptive accident in a liquid metal fast breeder reactor. The model predicts that substantial steel vaporization may occur in core disruptive accidents, if the steel reaches its saturation temperature rapidly enough. The potential importance of steel vaporization is dependent on the accident scenario.en_US
dc.description.sponsorshipReport issued under contract with the U.S. Nuclear Regulatory Commission NRC-04-77-126en_US
dc.format.extent111 pagesen_US
dc.publisherCambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1980]en_US
dc.relation.ispartofseriesMITNE ; no. 233en_US
dc.subject.lccTK9008.M41 N96 no.233en_US
dc.subject.lcshLiquid metal fast breeder reactors -- Safety measuresen_US
dc.subject.lcshHeat -- Transmission -- Mathematical modelsen_US
dc.subject.lcshNuclear fuel elementsen_US
dc.titleModeling of fuel-to-steel heat transfer in core disruptive accidentsen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857463357en_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record