Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors

被引:8
|
作者
Forsberg, Charles W. [1 ]
Carpenter, David M. [2 ]
Whyte, Dennis G. [3 ]
Scarlat, Raluca [4 ]
Wei, Liu [3 ]
机构
[1] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[2] MIT, Nucl Reactor Lab, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[3] MIT, Plasma Sci & Fus Ctr, 77 Massachusetts Ave, Cambridge, MA 02139 USA
[4] Univ Wisconsin, Madison, WI 53706 USA
关键词
Tritium; salt coolants; carbon;
D O I
10.1080/15361055.2017.1289450
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
Three advanced power systems use liquid salt coolants that generate tritium and thus face common challenges to prevent release of the tritium to the environment. The Fluoride-salt-cooled High-temperature Reactor (FHR) uses the same graphite-matrix coated-particle fuel as High-Temperature Gas-cooled Reactors (HTGRs) and clean fluoride salt coolants. Molten salt reactors (MSRs) dissolve the fuel in a fluoride or chloride salt and release the fission product tritium to the salt. High-magnetic-field fusion machines may use liquid salt cooling and blankets because of the very high power densities of this new class of fusion machine. The three technologies can be coupled to a Nuclear Air-Brayton Combined Cycle (NACC) enabling variable electricity with base-load reactor operation. Converging requirements for tritium control in 700 degrees C liquid salts are leading to cooperative programs across technologies; tritium models that combined generation, chemistry, metal corrosion and transport; and new tritium control technologies using advanced carbon forms, metals produced by additive manufacturing and other technologies.
引用
收藏
页码:584 / 589
页数:6
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