Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant

Radchenko, M. V.; Shadrin, A. Yu.; Poluéktov, P. P.; Shmidt, O. V.; Tuzov, A. A.

doi:10.1007/s10512-013-9752-5

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2018

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“…This paper presents a brief description of the "BREST" fast reactor closed fuel cycle concept from the viewpoint of its specifics and ability to meet the requirements for efficiency, non-proliferation of nuclear materials and to establish a balance between generated RW and mined natural uranium [1], [2], [3], [4], [5].…”

Section: Introductionmentioning

confidence: 99%

On-Site Nuclear Fuel Cycle of “BREST” Reactors

Glazov¹

2018

IJEPE

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Dynamic developing of modern nuclear industry demands meeting the following requirements: improved safety, reduced capital costs, radioactive waste (RW) management issues, independence of limited resources. Efficiency of uranium resources used in "BREST" reactors based on a closed fuel cycle is about 160 times higher than for VVER, RBMK reactors [1], which makes it possible to stop searching for new deposits and uranium mining. The need for periodical fuel regeneration and fabrication in a closed cycle includes reproduction of plutonium in the core without the uranium containing screens (breeding ratio is approximately 1,05, ensuring a high level of safety and support of the non-proliferation regime) and transmutation of the most dangerous long-lived actinides and high refining of RW, achieving the radiation balance of buried RW and extracted uranium ore. The manufacturing is located directly at the NPP to avoid transportation of fissile materials. This approach provides economic efficiency of the entire complex.

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Section: Introductionmentioning

confidence: 99%

On-Site Nuclear Fuel Cycle of “BREST” Reactors

Glazov¹

2018

IJEPE

View full text Add to dashboard Cite

show abstract

Assimilation of a Closed Uranium-Plutonium Nuclear Fuel Cycle Based on Fast Reactors With Liquid-Metal Coolant

Cited by 1 publication

References 1 publication

On-Site Nuclear Fuel Cycle of “BREST” Reactors

On-Site Nuclear Fuel Cycle of “BREST” Reactors

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