Summary: Fusion Engineering and Design 39­40 (1998) 859­864
Tritium processing system for the ITER Li/V Blanket
Test Module
Dai-Kai Sze a,
*, Thanh Q. Hua a
, Mohamad A. Dagher b
, Lester M. Waganer c
,
Mohamed A. Abdou d
a
Argonne National Laboratory, Building 207, 9700 South Cass Laboratory, Argonne, IL 60439, USA
b
Boeing North American Rocketdyne Di6ision, USA
c
McDonnell Douglas Aerospace, USA
d
Uni6ersity of California, Los Angeles, USA
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

Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles

Collections: Plasma Physics and Fusion