Peculiarities of fuel cycle with advanced composite fuel for thermal reactors

被引：4

作者：

Savchenko, A. M. ^{[1
]}

Vatulin, A. V. ^{[1
]}

Kulakov, G. V. ^{[1
]}

Lipkina, K. V. ^{[1
]}

Sorokin, V. I. ^{[1
]}

Morozov, A. V. ^{[1
]}

Ershov, S. A. ^{[1
]}

Uferov, O. I. ^{[1
]}

Mainikov, E. V. ^{[1
]}

Kozlov, A. ^{[1
]}

机构：

[1] AA Bochvar Inst Inorgan Mat VNIINM, Moscow 123060, Russia

来源：

PROGRESS IN NUCLEAR ENERGY | 2014年 / 72卷

关键词：

Composite fuel; Fuel cycle; Zr matrix; INERT MATRIX FUEL; WATER REACTORS; NUCLEAR-FUEL; ALLOYS;

D O I：

10.1016/j.pnucene.2013.10.007

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The use of dispersion type fuel elements, with high uranium content such as, U-Mo, U-Nb-Zr, U3Si, with a Zr alloy matrix ("advanced metmet"), is considered instead of a UO2 base type fuel for thermal reactors. Such fuels were fabricated and post-preparation analysed. In addition, composite, (U,Th)-PuO2 fuels were considered based on depleted uranium (or uranium, thorium alloy) and dioxide plutonium powder as the dispersion phases (a "cermet" analogue of heterogeneous MOX). Such fuel elements could be used in thermal reactors as low temperature fuels. Subsequently, a novel reprocessing strategy for composite fuel is proposed. This would allow the separation of uranium from burnt plutonium as well as the newly generated fissile plutonium from the burnt portion without chemical processes, with repeated use in CANDU/RBMK reactors. This would simplify the closure of the nuclear fuel cycle. By sequential use of the composite fuel, the generated Pu in spent fuel could be recycled in a more pragmatic way, reducing drastically the waste flow. (C) 2013 Elsevier Ltd. All rights reserved.

引用

页码：119 / 125

页数：7

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