Show simple item record

dc.contributor.authorḴẖāṉ, Ahsānullāhen_US
dc.contributor.authorTodreas, Neil E.en_US
dc.contributor.authorRohsenow, Warren M.en_US
dc.contributor.authorSonin, A. A.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.other7102 Massachusetts Institute of Technology. Department of Mechanical Engineeringen_US
dc.contributor.otherU.S. Atomic Energy Commissionen_US
dc.contributor.otherUnited States. Department of Energyen_US
dc.date.accessioned2014-09-12T23:50:28Z
dc.date.available2014-09-12T23:50:28Z
dc.date.issued1974en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89486
dc.descriptionStatement of responsibility on title-page reads: E.U. Khan, N.E. Todreas, W.M. Rohsenow , and A.A. Soninen_US
dc.description"September 1974."en_US
dc.descriptionIncludes bibliographical referencesen_US
dc.description.abstractIn this report analysis of recent experimental data is presented using the ENERGY code. A comparison of the accuracy of three types of experiments is also presented along with a discussion of uncertainties in utilizing this data for various code calibration purposes. The existence of internal swirl is discussed. The two empirical coefficients in ENERGY are determined from the data within a certain range of accuracy. This range is dictated to a large extent by the accuracy of the experiments and to a smaller extent by the ability of the code to utilize all sets of data in each experiment. The effect of geometry and bundle size on mixing and swirl flow is discussed. A realistic estimate of the degree of accuracy within which we can predict temperature distribution within the bundle and along the duct of a 217-pin wire wrapped fuel assembly of an LMFBR is presented. Gaps in data which need to be filled in to enhance our confidence in predicting coolant te! mperature distributions in a 217-pin LMFBR fuel bundle, are given. A brief description of two experiments that would fill these data gaps is presented. A novel experiment which would be very useful for both fuel and poison assembly mixing studies is described. Conclusions drawn from this study are believed to be quite general in nature.en_US
dc.description.sponsorshipU.S. Atomic Energy Commission contract AT(11-1)-2245en_US
dc.format.extent[169] pages (unpaged)en_US
dc.publisherCambridge, Mass. : Departments of Mechanical Engineering and Nuclear Engineering, Massachusetts Institute of Technology [1974]en_US
dc.relation.ispartofseriesMITNE ; no. 165en_US
dc.relation.ispartofseriesAEC research and development reporten_US
dc.relation.ispartofseriesCOO ; 2245-12en_US
dc.subject.lccTK9008.M41 N96 no.165en_US
dc.subject.lcshNuclear fuel elementsen_US
dc.subject.lcshLiquid metal cooled reactorsen_US
dc.subject.lcshFast reactorsen_US
dc.subject.lcshBreeder reactorsen_US
dc.titleAnalysis of mixing data relevant to wire wrapped fuel assembly thermal-hydraulic designen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc02006814en_US


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record