Core configuration of a gas-cooled reactor as a tritium production device for fusion reactor

被引:15
|
作者
Nakaya, H. [1 ]
Matsuura, H. [1 ]
Nakao, Y. [1 ]
Shimakawa, S. [2 ]
Goto, M. [2 ]
Nakagawa, S. [2 ]
Nishikawa, M. [3 ]
机构
[1] Kyushu Univ, Dept Appl Quantum Phys & Nucl Engn, Fukuoka 8190395, Japan
[2] Japan Atom Energy Agcy, Oarai, Ibaraki 4002, Japan
[3] UTM, Malaysia Japan Int Inst Technol, Kuala Lumpur 54100, Malaysia
关键词
PERFORMANCE;
D O I
10.1016/j.nucengdes.2013.12.023
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 performance of a high-temperature gas-cooled reactor as a tritium production device is examined, assuming the compound LiAlO2 as the tritium-producing material. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations are carried out. To load sufficient Li into the core, LiAlO2 is loaded into the removable reflectors that surround the ring-shaped fuel blocks in addition to the burnable poison insertion holes. It is shown that module high-temperature gas-cooled reactors with a total thermal output power of 3 GW can produce almost 8 kg of tritium in a year. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:505 / 509
页数:5
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