Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor

被引:0
|
作者
Nguyen, T. Sinh [1 ]
Wang, Xiaolin [1 ]
Bromley, Blair P. [1 ]
机构
[1] Canadian Nucl Laboratorie, 286 Plant Rd, Chalk River, ON K0J 1J0, Canada
关键词
IMPLEMENTATION; CORES;
D O I
10.1115/1.4053691
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 development of advanced fuels and fuel cycles for conventional Generation III+ reactors, advanced reactors (such as Generation IV), and small modular reactors will help ensure the long-term sustainability and safety of the use of nuclear energy. Thorium-based fuels are an example of an advanced fuel that could augment and extend uranium resources. As part of previous efforts in Canada to investigate the use of thorium-based fuels for potential use in pressure-tube heavy-water reactors and other technologies, irradiation experiments with various thorium-containing fuels had been conducted in the National Research Universal (NRU) reactor at the Chalk River Laboratories. The NRU reactor physics computational tools and methods, developed initially for conventional enriched uranium fuel, had also been extended for analysis of thorium-based fuel experiments, with most satisfactory results. In this study, a number of physics and operation factors have been analyzed to quantify their effects on the production and burnup of U-233 in thorium-based fuel, as well as to improve both the analysis and the use of thorium fuels and fuel cycles.
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页数:12
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