Np, Am, Cm utilization in a nuclear power reactor

被引：0

作者：

B. R. Bergelson

V. V. Belonog

A. S. Gerasimov

G. V. Tikhomirov

机构：

[1] State Science Center of the Russian Federation – Alikhanov Institute for Theoretical and Experimental Physics (GNTs RF – ITEF),

[2] Moscow Engineering Physics Institute (MIFI),undefined

来源：

Atomic Energy | 2009年 / 107卷

关键词：

Uranium; Fuel Element; Fuel Assembly; 237Np; Uranium Dioxide;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The utilization (transmutation using the released energy) of Np, Am, and Cm in a specialized VVER-type reactor operating power 1000 MW(e) is studied by computational means. Five successive reactor runs, where the fuel elements contain Np, Am, Cm, and enriched uranium, are studied. It is shown that Np, Am, and Cm produced by several VVER-1000 reactors can be utilized in one run (900 days) of a specialized reactor without any technological and structural changes. Up to 4% of the reactor power comes from the fission of these radionuclides.

引用

页码：103 / 109

页数：6

共 9 条

[1]

Bergel’son BR(2003)Transmutation of long-lived actinides in power reactors At. Énerg. 95 295-301

[2]

Gerasimov AS(2000)Homogeneous transmutation of Am, Cm, Np in the BREST reactor core At. Énerg. 89 355-361

[3]

Tikhomirov GV(2000)Heterogeneous transmutation of Am, Cm, Np in the BREST reactor core At. Énerg. 89 362-365

[4]

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