Comparison of REMIX vs. MOX fuel characteristics in multiple recycling in VVER reactor

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22257875

Dekusar, V. M.; Kalashnikov, A. G.; Kapranova, E. N.; Korobitsyn, V. E.; Puzakov, A. Y. ^[1]

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1. State Scientific Centre of Russian Federation, Institute for Physics and Power Engineering, Obninsk (Russian Federation)

Multiple recycling of regenerated uranium-plutonium fuel in thermal reactors of VVER-1000 type with high enriched uranium feeding (REMIX-fuel) gives a possibility to terminate the accumulation of spent nuclear fuels (SNF) and Pu and decrease the accumulation of irradiated uranium by an order of magnitude. Results of comparison of VVER-1000 nuclear fuel cycle characteristics vs different fuel types such as UOX, MOX and REMIX-fuel have been presented. REMIX fuel (Regenerated Mixture of U-, Pu oxides) is the mixture of plutonium and uranium extracted from SNF and refined from other actinides and fission products with the addition of enriched uranium to provide the power potential necessary. The savings in terms of uranium quantities and separation works in the nuclear energy system (NES) with reactors using REMIX-fuel compared to the NES with uranium-fuelled reactors are shown to be of about 30% and 8%, respectively. For the NES with thermal reactors partially loaded with MOX-fuel, the uranium and separation works saving of about 14% would be obtained. Production of neptunium and americium in reactors with REMIX-fuel in steady state increases by a factor 3, and production of curium - by 10 compared to the reactors with UOX-fuel. This increase of minor actinide buildup is owed to the multiple recycling of plutonium. It should be noted that in this case all fuel assemblies contain high-background plutonium, and their manufacturing involves an expensive technology. Besides, management of REMIX-fuel will require special protection measures even during the fresh fuel manufacturing phase. The above-said gives ground to state that the use of REMIX fuel would be questionable in economic aspect.

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22257875
• Resource Relation: Conference: GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads, Salt Lake City, UT (United States), 29 Sep - 3 Oct 2013; Other Information: Country of input: France; 9 refs.; Related Information: In: Proceedings of GLOBAL 2013: International Nuclear Fuel Cycle Conference - Nuclear Energy at a Crossroads| 1633 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AMERICIUM
BUILDUP
COMPARATIVE EVALUATIONS
CURIUM
FEEDING
FISSION PRODUCTS
FUEL ASSEMBLIES
HIGHLY ENRICHED URANIUM
IRRADIATION
MANUFACTURING
MIXED OXIDE FUELS
MIXTURES
NEPTUNIUM
NUCLEAR ENERGY
PLUTONIUM
POWER POTENTIAL
RECYCLING
SPENT FUELS
STEADY-STATE CONDITIONS
WWER TYPE REACTORS