Title of article :
Tritium processing system for the ITER Li/V Blanket Test Module
Author/Authors :
Sze، نويسنده , , Dai-Kai and Hua، نويسنده , , Thanh Q and Dagher، نويسنده , , Mohamad A and Waganer، نويسنده , , Lester M and Abdou، نويسنده , , Mohamed A، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1998
Pages :
6
From page :
859
To page :
864
Abstract :
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency, the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refuelling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.
Journal title :
Fusion Engineering and Design
Serial Year :
1998
Journal title :
Fusion Engineering and Design
Record number :
2364830
Link To Document :
بازگشت