Np, Am, Cm Transmutation in Different Types of Reactors


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Аннотация

Different approaches to the transmutation of Np, Am, and Cm in molten-salt reactors are compared: based on the eutectics LiF–NaF–KF (BZhSR), LiF–NaF–BeF2 (MOSART), and the salt LiF–BeF2 (ZhSR-S). In addition the efficiency of transmutation in a BREST-1200 type fast reactor is evaluated. It is shown that the highest possible transmutation efficiency can be realized in a reactor based on the salt LiF–NaF–KF (~306 kg/yr per 1 GW(t)). The results show that further study of the physical and chemical properties of LiF–NaF–KF is warranted, specifically, a study of the solubility of a fuel composition with fission products and an investigation of the possibility of developing a reactor with a fast neutron spectrum on the basis of this salt.

Авторлар туралы

L. Ponomarev

Bochvar High-Technology Research Institute of Inorganic Materials (VNIINM)

Email: m.n.belonogov@vniitf.ru
Ресей, Moscow

M. Belonogov

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Хат алмасуға жауапты Автор.
Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

I. Volkov

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

V. Simonenko

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

U. Sheremet’eva

Russian Federal Nuclear Center — Zababakhin All-Russia Research Institute of Technical Physics (VNIITF)

Email: m.n.belonogov@vniitf.ru
Ресей, Snezhinsk, Chelyabinsk, Oblast

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