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
Pages
4
From page
679
To page
682
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
Serial Year
2001
Journal title
Fusion Engineering and Design
Record number
2367394
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