dc.contributor.author | Fujita, Edward Kei | |
dc.contributor.author | Driscoll, Michael J. | |
dc.contributor.author | Lanning, David D. | |
dc.date.accessioned | 2006-03-06T17:53:40Z | |
dc.date.available | 2006-03-06T17:53:40Z | |
dc.date.issued | 1978-08 | |
dc.identifier.other | 04827465 | |
dc.identifier.uri | http://hdl.handle.net/1721.1/31307 | |
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 |