Radiochemical characteristics of tritium to be considered in fusion reactor facility design

被引:0
作者
S. O’hira
T. Hayashi
W. Shu
T. Yamanishi
机构
[1] Japan Atomic Energy Agency,Division of ITER Project
[2] Japan Atomic Energy Agency,Division of Fusion Energy Technology
来源
Journal of Radioanalytical and Nuclear Chemistry | 2007年 / 272卷
关键词
Tritium; Vacuum Vessel; Tritiated Water; Tritium Concentration; Decay Heat;
D O I
暂无
中图分类号
学科分类号
摘要
The results of research and development related to radiochemical characteristics of tritium to be considered in a fusion reactor facility design are summarized. Reactions induced by tritium beta-decay under presence of high purity tritium, which might give an impact to tritium inventory control and safety, have been identified and investigated. Results of researches of radiolysis of tritiated water implied necessity of some measures to prevent hydrogen explosion and avoid a corrosive condition. A calorimetric method to measure tritium decay heat has been applied successfully to accountancy of the ITER fuel storage system with satisfaction of the required specification.
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页码:575 / 581
页数:6
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共 160 条
[1]  
Yamanishi T.(2000)undefined Nucl. Fusion 40 515-undefined
[2]  
Kawamura Y.(1995)undefined Fusion Technol. 28 1327-undefined
[3]  
Iwai Y.(1999)undefined Fusion. Eng. Des. 47 173-undefined
[4]  
Arita T.(2005)undefined Fusion Sci. Technol. 48 3-undefined
[5]  
Maruyama T.(2002)undefined Fusion. Eng. Des. 61–62 513-undefined
[6]  
Kakuta T.(1991)undefined Fusion Technol. 21 457-undefined
[7]  
Konishi S.(1992)undefined Radiochim. Acta 56 209-undefined
[8]  
Enoeda M.(1992)undefined J. Radioanal. Nucl. Chem. 159 145-undefined
[9]  
O’hira S.(1995)undefined Fusion Technol. 28 1239-undefined
[10]  
Hayashi T.(2000)undefined Fusion Eng. Des. 49–50 905-undefined