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Design and fuel management of PWR cores to optimize the once-through fuel cycle

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Show simple item record Fujita, Edward Kei Driscoll, Michael J. Lanning, David D. 2006-03-06T17:53:40Z 2006-03-06T17:53:40Z 1978-08
dc.identifier.other 04827465
dc.description Originally presented as the first author's thesis, (Sc.D.) in the M.I.T. Dept. of Nuclear Engineering, 1978. en
dc.description.abstract The once-through fuel cycle has been analyzed to see if there are substantial prospects for improved uranium ore utilization in current light water reactors, with a specific focus on pressurized water reactors. The types of changes which have been examined are: (1) re-optimization of fuel pin diameter and lattice pitch, (2) Axial power shaping by enrichment gradation in fresh fuel, (3) Use of 6-batch cores with semi-annual refueling, (4) Use of 6-batch cores with annual refueling, hence greater extended (.doubled) burnup, (5) Use of radial reflector assemblies, (6) Use of internally heterogeneous cores (simple seed/blanket configurations), (7) Use of power/temperature coastdown at the end of life to extend burnup, (8) Use of metal or diluted oxide fuel, (9) Use of thorium, and (10) Use of isotopically separated low a cladding material. a State-of-the-art LWR computational methods, LEOPARD/PDQ-7/FLARE-G, were used to investigate these modifications. The most effective way found to improve uranium ore utilization is to increase the discharge burnup. Ore savings on the order of 20% can be realized if greatly extended burnup (- double that of current practice) is combined with an increase in the number of batches in the core from 3 to 6. The major conclusion of this study is that cumulative reductions in ore usage of on the order of 30% are fore- seeable relative to a current PWR operating on the once-through fuel cycle, which is comparable to that expected for the same cores operated in the recycle mode. en
dc.description.sponsorship DOE Contract no. EN-77-S-02-4570. en
dc.format.extent 11277096 bytes
dc.format.mimetype application/pdf
dc.language.iso en_US en
dc.publisher MIT Energy Laboratory en
dc.relation.ispartofseries MIT-EL en
dc.relation.ispartofseries 78-017 en
dc.subject Nuclear fuel elements. en
dc.subject Pressurized water reactors. en
dc.subject Nuclear reactors |x Mathematical models. en
dc.title Design and fuel management of PWR cores to optimize the once-through fuel cycle en
dc.type Technical Report en

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