PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

BURNING OF MINOR ACTINIDES IN A BN-1200 REACTOR USING FUEL ASSEMBLIES WITH INTRA-CASSETTE HETEROGENEITY

EDN: DRXUTG

Authors & Affiliations

Kotov Ya.A., Nevinitsa V.A., Fomichenko P.A.
National Research Center “Kurchatov Institute”, Moscow, Russia

Kotov Ya.A. – Senior Researcher. Contacts: 1, pl. Kurchatov, Moscow, 123183. E-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nevinitsa V.A. – Head of Division, Cand. Sci. (Tech.).
Fomichenko P.A. – Deputy Head of Complex.

Abstract

Heterogeneous fuel assemblies can be one of the promising options for fast reactor fuel. It consists of two fuel pin types: fueling rods (consists of MOX fuel) and breeding rods (contains depleted uranium oxide or doped metallic uranium alloy). This fast reactor fuel design allows to achieve higher breeding in core due to higher fuel density and properties in breeding rods and gives possibility to reprocess different fuel pins separately. Also it creates opportunities for further closed fuel cycles optimization due to different holding time before reprocessing, usage of different reprocessing technologies for each rod types and so on.
Considering the problem of minor actinides transmutation in fast reactors two approaches can be distinguished: homogeneous and heterogeneous. Heterogeneous fuel assemblies can also be used for minor actinides burning by adding them into fueling or breeding rods. This approach make it possible to combine the advantages of heterogeneous and homogeneous minor actinides placement for their burning in fast reactor core. This work is devoted to the study of minor actinides (Np and Am) transmutation by adding them to breeding (fertile) rods of BN-1200 heterogeneous fuel assemblies which will provide a number of advantages.

Keywords
heterogeneous fuel assemblies, BN-1200, closed fuel cycle, minor actinide transmutation, uranium-plutonium fuel, metallic fuel, borosilicate glass, reactivity margin

Article Text (PDF, in Russian)

References

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:8