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dc.rights.licenseRestricted to current Rensselaer faculty, staff and students. Access inquiries may be directed to the Rensselaer Libraries.
dc.contributorBecker, Martin, 1940-
dc.contributorBlock, Robert C., 1929-
dc.contributorLahey, Richard T.
dc.contributorRogers, Edwin H.
dc.contributor.authorAlvarez, Jose Maria Sierra
dc.date.accessioned2021-11-03T08:41:49Z
dc.date.available2021-11-03T08:41:49Z
dc.date.created2016-11-01T11:15:40Z
dc.date.issued1976-05
dc.identifier.urihttps://hdl.handle.net/20.500.13015/1803
dc.descriptionMay 1976
dc.descriptionSchool of Engineering
dc.description.abstractA dramatic reduction in computing effort was achieved as a result of the coupling of the analytical solution of the depletion equations and the analytical prediction through correlation of the spectrum-averaged cross sections. Furthermore, this coupling has been used in an analytical treatment of the sensitivity analysis of important nuclear characteristics of an LMFBR to initial compositions, to system components temperatures and to nuclear data. Another application found for this full analytical treatment of depletion is the prediction of the behavior, over cycle-life, of nuclear characteristics of an LMFBR considered as a perturbation of another LMFBR which is considered as the reference case. In general, excellent agreement with exact calculations is observed when the perturbations occur in nuclear data and/or fuel isotopic characteristics, whereas only fair results are obtained when the variations occur in system components other than fuel.
dc.description.abstractThe representation of the depletion process in a (U,Pu) fueled Liquid Metal Fast Breeder Reactor can be greatly simplified, without appreciable loss in accuracy, when assuming that the fissionable isotopes are restricted to those of U-235, U-236, U-238, Pu-239, Pu-240, Pu-24l and Pu-242, and the fission products are lumped into a pseudo-fission product. In the center- core region, where there are no significant spatial effects, space-independent continuous slowing down theory has been used for spectrum calculations whose most significant result is that spectrum-averaged cross sections vary very slightly and in a quasi-linear manner over the exposure ranges considered nowdays. It is also shown that the simplified depletion equations have an analytical solution for all fuel isotopes for the constant spectrum-averaged cross section case, while for the case in which they vary linearly, the analytical solution exists for only some of them. A quadratic correlation with composition, the correlation quantities being the fissile, fertile, pseudo-fission product, control, coolant and structure compositions, which also includes a fuel temperature correction factor, has been introduced and the errors in the spectrum-averaged cross sections are smaller than 3% against the numerical values, for all fuel elements and all cases considered.
dc.language.isoENG
dc.publisherRensselaer Polytechnic Institute, Troy, NY
dc.relation.ispartofRensselaer Theses and Dissertations Online Collection
dc.subjectNuclear engineering
dc.titleAn analytical approach to fast reactor fuel cycle analysis
dc.typeElectronic thesis
dc.typeThesis
dc.digitool.pid177650
dc.digitool.pid177651
dc.digitool.pid177653
dc.digitool.pid177652
dc.digitool.pid177654
dc.rights.holderThis electronic version is a licensed copy owned by Rensselaer Polytechnic Institute, Troy, NY. Copyright of original work retained by author.
dc.description.degreePhD
dc.relation.departmentDept. of Nuclear Engineering


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