Title of article :
In-situ tritium release behavior from Li2TiO3 pebble-bed
Author/Authors :
Tsuchiya، نويسنده , , K and Kikukawa، نويسنده , , A and Yamaki، نويسنده , , D and Nakamichi، نويسنده , , M and Enoeda، نويسنده , , M and Kawamura، نويسنده , , H، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2001
Abstract :
The engineering data on neutron irradiation performance of fusion blanket are indispensable to design the fusion blanket. In this study, an in-situ irradiation test of the Li2TiO3 pebble bed was carried out at the Japan Materials Testing Reactor (JMTR), and the effects of various parameters, i.e. sweep gas flow rate, irradiation temperature and hydrogen content in sweep gas on tritium release were evaluated.
Keywords :
Fusion reactor , Japan Materials Testing Reactor (JMTR) , Li2TiO3 pebble bed , tritium
Journal title :
Fusion Engineering and Design
Journal title :
Fusion Engineering and Design
