Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings

被引：79
|
作者：
Wagih, Malik [1 ]
Spencer, Benjamin [2 ]
Hales, Jason [2 ]
Shirvan, Koroush [1 ]
机构：
[1] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[2] Idaho Natl Lab, Fuel Modeling & Simulat, POB 1625, Idaho Falls, ID 83415 USA
来源：
ANNALS OF NUCLEAR ENERGY | 2018年 / 120卷
关键词：
Accident tolerant fuel; Chromium; Silicon carbide; Cladding; Nuclear fuel; BISON; HIGH-TEMPERATURE OXIDATION; SIC-SIC COMPOSITES; NUCLEAR-FUEL; MECHANICAL-PROPERTIES; NEUTRON-IRRADIATION; FUKUSHIMA; FIBER;
D O I：
10.1016/j.anucene.2018.06.001
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 U.S. Department of Energy's Accident Tolerant Fuel program is focused on extending the time for fuel failure during postulated severe accidents compared to the standard UO2-Zr alloy fuel system. This paper investigates the feasibility of two different chromium-coated cladding concepts, one of which is zirconium-alloy based and the other is composite-SiC based. Both claddings had 50 mu m coatings, deducted from the base layer thicknesses. The claddings were studied, using the multi-physics fuel performance tool BISON, under steady-state PWR operating conditions as well as under two transients: a power ramp and a loss-of-coolant accident (LOCA). The chromium-coated claddings showed comparable thermo-mechanical performance to the reference Zircaloy-4 cladding. As chromium is reported to provide an order of magnitude improvement in oxidation resistance, it is expected to be a better alternative in accident scenarios. Simulation results for both concepts show that further experimental investigation as well as modeling of beyond design-basis accidents is warranted. (C) 2018 Elsevier Ltd. All rights reserved.
引用
收藏
页码：304 / 318
页数：15
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