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THE COMPOSITE FUEL FOR BREST REACTOR (PREPRINT IBRAE-2015-05)

Language: Русский
Publish year: 2015
Pages: 20

Preprint IBRAE-2015-05

Bolshov L.A., Solodov A.A.

The revue is exposed on operational, technological and cost properties of the novel nuclear fuel for fast power reactor. The fuel element is made as a sandwich structure of thin oxides or nitridepellets and interposed molybdenum spacers. The molybdenum spacers are responsible for the high effective heat conduction constant of the fuel, typically in the range of 25 W/m·K or 40 W/m·K if oxide/nitride pellets are used. The startpoint  of the design is that molybdenum would be enriched in neutron – transparent isotopes 92,94Mo or 98,100Mo. The unique property of molybdenum from the viewpoint of recycling of that material is that its specific activity is low after postreactor storing ~ 1 year long, which enables recycling of molybdenum used after relatively short stay.  The estimate is performed on  the isotopes  92,94Mo and  98,100Mo mixtures cost.

By the virtue of specific structure of composite nitrides fuel as thin nitrides pellets and molybdenum spacers the blocking of pellets fragmentation is achieved. So the general degradation mechanism of fuel rods with nitrides pellets is turned off. The novel composite nitrides fuel should be regarded as reliable and safe candidate fuel for the BREST reactor.   

Bibliographical reference

Bolshov L.A., Solodov A.A. THE COMPOSITE FUEL FOR BREST REACTOR. Preprint № IBRAE-2015-05. Moscow Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN), 2015. – 20 p. – Refs.: 23 items 



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