The Nuclear Fuel Cycle Dr. Okan Zabunoğlu Hacettepe University Department of Nuclear Engineering.

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Presentation transcript:

The Nuclear Fuel Cycle Dr. Okan Zabunoğlu Hacettepe University Department of Nuclear Engineering

Uranium in Nature Exploration Mining (remove ores) Milling (concentrate ores) Refining (purify and convert to uranium hexafluoride) Enrichment Fabrication (produce fuel elements and assemblies) Nuclear Reactor (LWR) Front End of the NFC (before the reactor)

Back End of the NFC (after the reactor) LWR Temporary storage of spent fuel (in pool, on-site) Reprocessing (recovery of valuable materials) Off-site storage Preparation Packaging Final disposal of SF HLWRecovered products Solidification Preparation Final disposal of HLW Reuse

Fresh Fuel ~27 tons U per yr A 1000-MWe LWR thermal efficiency: exposure time: 1100 days capacity factor: 0.80 burnup: MWd/ton Spent Fuel ~27 tons per yr Fresh and Spent LWR Fuels U-235: 3.3 w/o U: 95.5 w/o U-238: 96.7 w/o U-235: 0.83 w/o Pu: 0.9 w/o Fissile Pu: 70 w/o FPs: 3.5 w/o Other Actinides: 0.1 w/o

The Standard Reprocessing PUREX: Solvent extraction with tri-butyl phosphate Co-decontamination of U+Pu from FPs (producing a HLW solution) and partitioning of U and Pu. Products: a pure U and a pure Pu solution. Recovered U (sufficiently decontaminated from fission products to be handled by direct-contact): Enrich and fabricate. Recovered Pu (highly pure): Blend it with a fertile makeup (depleted U, natural U, or recovered U from reprocessing) to adjust its fissile content and fabricate into mixed-oxide (MOX) fuel.

Requirements in a civilized LWR cycle Contradiction : Plutonium product of reprocessing is to be blended with a fertile makeup (depleted, natural, or recovered U) before being loaded into a reactor. Then, why in the first place separate Pu in a highly pure form?! It is not necessary to produce pure Pu in reprocessing. About % U in Pu is an appropriate fraction for MOX fuel. In addition, since Pu has an inherent beta (and gamma) activity, it is not required to decontaminate Pu from the fission products by a great extent.

Alternative Reprocessing Schemes Modified Purex Partial co-processing (Products: U+Pu and U) Complete co-processing (Product: U+Pu) Several options regarding separation of other actinides (Np, Am, Cm) and certain fission products DUPIC (Direct Use of spent PWR fuel in CANDU reactors): Direct fabrication of CANDU fuel from spent PWR fuel materials by thermal and mechanical processes (no aqueous processing like in Purex).

Pyro-processing : Pyrometallurgical and pyrochemical (electrorefining) processing to obtain (1) pure U, (2) Pu and other actinides (together with some U), and (3) fission products. Originally planned to be part of the IFR (Integral Fast Reactor) concept. Spent LWR fuels can also be pyroprocessed after an initial reduction-to-metal step, leading to a combined IFR-LWR system. In any case, Pu and other actinides recovered by pyroprocessing can be burned in a fast-neutron spectrum, thus leaving fission-products waste only.

Concluding remarks Whether or not to close the nuclear fuel cycle and how to close it... Burdens of the standard reprocessing economic uncertainties safeguardability considerations Utilization of resources Effects on waste disposal