Use of Recovered Uranium and Plutonium in Thermal Reactors

被引：0

作者：

Yu. S. Fedorov

B. A. Bibichev

B. Ya. Zil'berman

E. G. Kudryavtsev

机构：

[1] V. G. Khlopin Radium Institute,

[2] Federal Atomic Energy Agency,undefined

来源：

Atomic Energy | 2005年 / 99卷

关键词：

Uranium; Lower Risk; Plutonium; Fission Product; Thermal Reactor;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

A possible version of the VVER-1000 fuel cycle without separation of uranium and plutonium during reprocessing of spent fuel is examined. In this fuel cycle, the uranium-plutonium regenerate obtained, from which other actinides and fission products have been removed, is used after enriched natural uranium is added for preparing VVER fuel. The results of a calculation of the content of uranium and plutonium isotopes in the spent uranium-plutonium fuel after one and two recycles in VVER-1000 are presented. The main advantages of the fuel cycle are discussed: lower risk of plutonium proliferation, savings of natural uranium, and less spent fuel as compared with an open uranium fuel cycle.

引用

页码：572 / 576

页数：4

共 14 条

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