An overview of INEL fusion safety R&D facilities

被引:1
作者
McCarthy, KA
Smolik, GR
Anderl, RA
Carmack, WJ
Longhurst, GR
机构
[1] LMITCO, Idaho Falls, United States
关键词
Steam; Tritium; Fusion Reactor; Hydrogen Isotope; Experimental Facility;
D O I
10.1023/A:1022525315645
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 Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200 degrees C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200 degrees C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implantation/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.
引用
收藏
页码:113 / 118
页数:6
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