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Fujita, E.K.; Driscoll, M.J.; Lanning, D.D.
Massachusetts Inst. of Tech., Cambridge (USA). Energy Lab1978
Massachusetts Inst. of Tech., Cambridge (USA). Energy Lab1978
AbstractAbstract
[en] 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 (approximately 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 sigma/sub a/ cladding material. State-of-the-art LWR computational methods, LEOPARD/PDQ-7/FLARE-G, were used to investigate these modifications
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Aug 1978; 249 p; MITNE--215; MIT-EL--78-017; Available from NTIS., PC A11/MF A01
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