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dc.contributor.authorForbes, Ian Alexanderen_US
dc.contributor.authorDriscoll, Michael J.en_US
dc.contributor.authorThompson, Theos Jardin, 1918-1970en_US
dc.contributor.authorKaplan, Irving, 1912-en_US
dc.contributor.authorManning, David D.en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.contributor.otherU.S. Atomic Energy Commissionen_US
dc.date.accessioned2014-09-15T17:55:50Z
dc.date.available2014-09-15T17:55:50Z
dc.date.issued1970en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89562
dc.description"February 1970."en_US
dc.descriptionStatement of responsibility on title-page reads: I.A. Forbes, M.J. Driscoll, T.J. Thompson, I.Kaplan and D.D. Lanningen_US
dc.descriptionAlso issued as a Ph. D. thesis in the Dept. of Nuclear Engineering, MIT,1970en_US
dc.description"MIT-4105-2."en_US
dc.descriptionBibliography: leaves 123-125en_US
dc.description.abstractA facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by a 17.5-cm-thick U0 2 fuel region, is used to convert thermal neutrons into fast neutrons to drive a blanket mockup. Operating at 55 watts, the converter generates blanket fluxes at an equivalent LMFBR core power of about 350 watts, with as little as one tenth of the blanket material required for a critical assembly. Calculations show that the converter leakage spectrum is a close approximation to the core leakage spectrum from reference LMFBR designs, and that the axial distribution of the neutron flux in the blanket assembly simulates that in the radial blanket of a large LMFBR when the effective height and width of the blanket assembly are correctly chosen. Testing of the completed facility with a blanket composed of 50 v/o iron and ! 50 v/o borax showed that the lateral flux distributions were cosine-shaped, and that lateral spectral equilibrium was achieved in a large central volume of the blanket. Backscattering from concrete shielding surrounding the experiment was found to affect no more than the outer 30 cm of the blanket assembly, confirming the results of two-dimensional multigroup calculations. Measurements of the axial activity of gold and indium show good agreement with 16- group, S8 ANISN calculations.en_US
dc.description.sponsorshipU.S. Atomic Energy Commission contract AT(30-1)4105en_US
dc.format.extent125 leavesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology,  Dept. of Nuclear Engineering, [1970]en_US
dc.relation.ispartofseriesMIT-4105-2en_US
dc.relation.ispartofseriesMITNE ; no. 110en_US
dc.relation.ispartofseriesAEC research and development reporten_US
dc.subject.lccTK9008.M41 N96 no.110en_US
dc.subject.lcshBreeder reactorsen_US
dc.subject.lcshNuclear fuel elementsen_US
dc.subject.lcshNuclear reactors -- Tablesen_US
dc.subject.lcshFast reactorsen_US
dc.titleDesign, construction and evaluation of a facility for the simulation of fast reactor blanketsen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc09825439en_US


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