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dc.contributor.authorSolan, George Michaelen_US
dc.contributor.authorLanning, David D.en_US
dc.contributor.authorMomsen, Bruce William Fosteren_US
dc.contributor.authorPilat, E. E., 1937-en_US
dc.contributor.otherMassachusetts Institute of Technology. Department of Nuclear Engineeringen_US
dc.date.accessioned2014-09-16T23:35:39Z
dc.date.available2014-09-16T23:35:39Z
dc.date.issued1975en_US
dc.identifier.urihttp://hdl.handle.net/1721.1/89726
dc.descriptionStatement of responsibility on title-page reads: George M. Solan David D. Lanning Bruce F. Momsen, and Edward E. Pilaten_US
dc.description"August 1975."en_US
dc.descriptionAlso issued as a Nucl. E. thesis, MIT Dept. of Nuclear Engineering, 1975en_US
dc.descriptionIncludes bibliographical references (pages 271-275)en_US
dc.description.abstractA method for the neutronic analysis of plutonium recycle assemblies has been developed with emphasis on relative power distribution prediction in the boundary area of vastly different spectral regions. Such regions are those of mixed oxide (Pu0 2 in natural U02 ) fuel pins relative to enriched uranium pins, or water regions relative to fuel pin regions. The basic analytical methods for determination of spectrum averaged constants are given in the following descriptions: (1) Generalized Mixed Number Density (GMND) group constants (based on Breen's Mixed Number Density Method) are generated by a modified version of the spectrum code LASER, called LASER-M. (2) THERMOS Corrected LASER-M (TCL) group constants are based on mixed oxide- uranium oxide and water region boundary modeling in one dimensional (slab) geometry with the integral transport code THERMOS.en_US
dc.description.abstractThe LASER-M model, as modified by addition of ENDF/B-II thermal cross sections for the plutonium isotopes, is used to predict the criticality of experimental lattices of U02 - 2 w/o Pu0 2, and fair agreement is shown. LASER-M unit cell depletion calculations with Yankee Core I data (3.4 w/o U-235) to 40,000 MWD/MT and Saxton Core II data (6.6 w/o Pu02 in natural U02) to 20,000 MWD/MT show good isotopic agreement. Saxton Critical Reactor Experiment (CRX) lattice cores (19 x 19 rod array) consisting of a single fuel type region (mixed oxide or uranium oxide) or multiregions of both pin types were analyzed for relative power distribution comparisons. Cores with water slot regions were included. LASER-M Normal, LASER-M GMND and TCL two group constants were used with PDQ-7 in the calculations. GMND results were in excellent agreement compared to the good agreement of TCL for these cases of isolated spectral disturbances in an asymptotic core region.en_US
dc.description.abstractThe methods were applied to a proposed plutonium recycle "island design" assembly in which a large control rod water region is in close proximity to a zoned mixed oxide region. The TCL method yielded significantly greater power peaking and mixed oxide region average power owing to the spectral influence of the water region explicitly accounted for in this method. Such a result is consistent with published calculations. It is concluded that infinite lattice spectrum calculations are insufficient to deal with spectrum effects more complex than those in the Saxton CRX experiments.en_US
dc.format.extent301 pagesen_US
dc.publisherCambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1975]en_US
dc.relation.ispartofseriesMITNE ; no. 175en_US
dc.subject.lccTK9008.M41 N96 no.175en_US
dc.titleNeutronic analysis of a proposed plutonium recycle assemblyen_US
dc.typeTechnical Reporten_US
dc.identifier.oclc857062859en_US


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