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Alternate fuel cycles

Fig. 1. Alternative fuel cycles for nuclear fuel, where (-) corresponds to the classical fuel cycle, (—) the throwaway fuel cycle, and (—) the recycle... Fig. 1. Alternative fuel cycles for nuclear fuel, where (-) corresponds to the classical fuel cycle, (—) the throwaway fuel cycle, and (—) the recycle...
Mendel, J. E., Palmer, C. R., and Eschback, E. A., "Preliminary Assessment of Potential Effects of Alternate Fuel Cycles on High-Level Waste Vitrification Processing," Symposium on Waste Management and Fuel Cycles 78," Edited by R.G. Post and M. E. Wacks, Tucson, AZ, March (1978). [Pg.147]

Transport of spent reactor fuel 21.4.2 Interim storage facilities Alternative fuel cycles... [Pg.583]

The plant is designed for on-load refuelling. The fuel is natural uranium. However, there are several options for alternative fuel cycles which improve the economy of the plant, e.g. slightly enriched uranium up to 1.2% enrichment, recycling of plutonium in the form of spiked-fuel elements or homogeneous mixed oxide fuel, tandem operation together with light water reactors etc.). [Pg.120]

Alternative fuel cycle options (specify once-through, closed etc. for alternative types of fuel)... [Pg.122]

A standard fuel cycle of high temperature gas cooled reactors could be used as basic option for the FBNR. A variety of alternative fuel cycle options could be used according to the demand. These include a plutonium burner mode using plutonium-thorium oxide fuel and a closed fuel cycle based on U-Th. [Pg.378]

The 4S can be configured for a variety of alternative fuel cycle options to meet actual demands of its users. These include a plutonium or TRU burner option using a metal fuel such as a U-Pu-Zr alloy or using inert materials to avoid further production of plutonium from the installed 238U [XIV-6, XIV-7]. [Pg.405]

CAREM can be adapted to use MOX fuel as an alternative fuel cycle option. In this case, advanced PUREX methods could be used to obtain higher purity levels, to avoid fissile material contamination and to have more time for material utilization. [Pg.146]

The reference fuel characteristics are similar to those of conventional French PWRs. The reduction of the average linear power density (by about 25 percent compared with current PWRs) improves the thermal margin and provides operational flexibility, enabling longer fuel cycles and increases in overall plant capacity. The low core power density may allow use of alternative fuel cycles, e g. MOX fuel, advanced fuels with increased burn-up, etc. [Pg.200]

The SCOR reactor design can also accommodate alternative fuel cycles with an adapted external infrastructure. For example, fuel reprocessing could be similar to that of current French PWRs. [Pg.200]

A closed fuel cycle is the alternative fuel cycle option. Aqueous reprocessing could be adopted to reprocess spent fuel from the CCR. Dry reprocessing, which is considered in application to the reduced moderation core [K-10], is also a candidate reprocessing option. An innovative fuel cycle system named BARS (BWR with an advanced recycle system) is proposed as a future fuel cycle option aimed at the enhanced utilization of uranium resources and reduction of radioactive wastes. In the BARS, the spent fuel from LWRs is recycled as a MOX fuel in BWR cores with the fast neutron spectrum, using dry reprocessing and vibro-packing for fabrication of the fuel. [Pg.317]

The alternative fuel cycle option is a once-through cycle with cermet fuel (micro-particles of fuel in a metallic matrix). [Pg.388]

The GT-MHR reactor design can accommodate alternative fuel cycles if supported by external infrastructure. A fuel cycle utilizing recycled water reactor plutonium can be accommodated, and will be effectively demonstrated by the GT-MHR plutonium consumption project in the Russian Federation. Thorium can be used as an alternative to natural uranium in the fertile particles. If reprocessing is supported in the future, fissile particles can incorporate recycled U from thorium fertile particles to reduce the separative work required to produce fissile particles. [Pg.460]

The VHTR has two typical reactor configurations, namely the pebble bed type and the prismatic block type. Although the shape of the fuel element for two configurations are different, the technical basis for both configuration is same, such as the TRISO-coated particle fuel in the graphite matrix, foil ceramic (graphite) core structure, helium coolant, and low power density, in order to achieve high outlet temperature and the retention of fission production inside the coated particle under normal operation condition and accident condition. The VHTR can support alternative fuel cycles such as U—Pu, Pu, mixed oxide (MOX), and U—thorium (Th). [Pg.42]


See other pages where Alternate fuel cycles is mentioned: [Pg.95]    [Pg.987]    [Pg.138]    [Pg.364]    [Pg.601]    [Pg.194]    [Pg.196]    [Pg.560]    [Pg.562]    [Pg.565]    [Pg.565]    [Pg.1269]   
See also in sourсe #XX -- [ Pg.194 ]




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