Title of article :
Integrated experiment of blanket in-pile mockup with Li2TiO3 pebbles
Author/Authors :
Tsuchiya، نويسنده , , K and Nakamichi، نويسنده , , M and Nagao، نويسنده , , Y and Fujita، نويسنده , , J and Sagawa، نويسنده , , H and Tanaka، نويسنده , , S and Kawamura، نويسنده , , H، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2000
Pages :
6
From page :
887
To page :
892
Abstract :
Lithium titanate (Li2TiO3) is one of the candidate tritium breeding materials for breeding blanket of the fusion reactor. Therefore, tritium release experiments from Li2TiO3 packing region were carried out to evaluate the effects of various parameters, i.e. sweep gas flow rate, irradiation temperature, and hydrogen content in sweep gas, etc. on tritium release. As for the shape of the Li2TiO3, a small spherical form (pebbles) is preferred to reduce the induced thermal stress in the breeding material. The diameter and total weight of Li2TiO3 pebbles were 1 mm and ∼135 g, respectively. And the integrated experiment of blanket in-pile mockup with Li2TiO3 pebble bed was carried out at the Japan Materials Testing Reactor (JMTR). The tritium released from Li2TiO3 pebble bed was swept by the helium gas with hydrogen. The total tritium concentration (HT+HTO) and gaseous tritium concentration (HT) of tritium released from Li2TiO3 pebbles were measured, and HT/(HT+HTO) ratio was evaluated under various conditions.
Keywords :
Lithium titanate , Integrated experiment , Tritium breeding materials , Blanket in-pile mockup
Journal title :
Fusion Engineering and Design
Serial Year :
2000
Journal title :
Fusion Engineering and Design
Record number :
2366435
Link To Document :
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