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

共 50 条

[31] Safeguards for the Advanced Fuel Cycle Facility
Thomas, Kenneth E.
Demuth, S.
Tobin, S.
Thomas, I. R.
ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 2007, 233
[32] THE FUEL-CYCLE OF FAST-NEUTRON REACTORS
BEKIARIAN, A
ANNALES DES MINES, 1984, 191 (01): : 55 - 62
[33] FUEL CYCLE ALTERNATIVES FOR NUCLEAR-POWER REACTORS
PIGFORD, TH
INDUSTRIAL & ENGINEERING CHEMISTRY FUNDAMENTALS, 1977, 16 (01): : 75 - 81
[34] A Once-Through Fuel Cycle for Fast Reactors
Weaver, Kevan D.
Gilleland, John
Ahlfeld, Charles
Whitmer, Charles
Zimmerman, George
JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2010, 132 (10): : 1 - 6
[35] Dynamic analysis of a thorium fuel cycle in CANDU reactors
Jeong, Chang Joon
Park, Chang Je
Ko, Won Il
ANNALS OF NUCLEAR ENERGY, 2008, 35 (10) : 1842 - 1848
[36] NUCLEAR-FUEL CYCLE .4. REACTORS
FARMER, AA
JOURNAL OF THE INSTITUTE OF FUEL, 1977, 50 (402): : 33 - 40
[37] The closed on-site fuel cycle of the BREST reactors
Orlov, VV
Filin, AI
Lopatkin, AV
Glazov, AG
Sukhanov, LP
Volk, VI
Poluektov, PP
Ustinov, OA
Vorontsov, MT
Leontiev, VF
Karimov, RS
PROGRESS IN NUCLEAR ENERGY, 2005, 47 (1-4) : 171 - 177
[38] Combined pyroprocessing fuel cycle for VVER and fast reactors
Petrov, AV
Usynin, GB
Usynina, SG
ATOMIC ENERGY, 1998, 85 (06) : 880 - 885
[39] Fuel Cycle Economy for Light Water Reactors.
Lepine, J.
Revue Generale Nucleaire, 1979, (02): : 168 - 175
[40] A ONCE-THROUGH FUEL CYCLE FOR FAST REACTORS
Weaver, Kevan D.
Gilleland, John
Ahlfeld, Charles
Whitmer, Charles
Zimmerman, George
ICONE 17: PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 1, 2009, : 845 - 851

← 1 2 3 4 5 →