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U.S. PARTICIPATION IN THE ITER TEST BLANKET MODULE (TBM) PROGRAM
 

Summary: U.S. PARTICIPATION IN THE ITER
TEST BLANKET MODULE (TBM) PROGRAM
M. Abdou (UCLA), C. Wong (GA), D. Sze (UCSD), A. Ying (UCLA),
M. Sawan (UW), N. Morley (UCLA), S. Willms (LANL),
R. Nygren (SNL), B. Merrill (INEEL), B. Nelson(ORNL)
A critical element in the ITER mission since its inception has been testing integrated blanket
modules in special ports. Among the principal objectives of the ITER Test Blanket Module
(TBM) Program are:
1) demonstrate the principles of tritium self-sufficiency in practical systems,
2) develop the technology necessary to install breeding capabilities to supply ITER with the
tritium necessary for operation in its extended phase of operation, and
3) provide experimental data vital to evaluating the feasibility, constraints, and potential of
the DT cycle for fusion systems (including limitations on options for improving plasma
physics performance, e.g. conducting shells, passive coils, thick armors/first wall)
Adequate tritium supply is a central issue for the operation of ITER and the development of
fusion energy. TBMs will be inserted in ITER from "Day 1" of its operation and will provide the
first EXPERIMENTAL data on the feasibility of the DT cycle for fusion. A decision on the
types of TBMs allowed in ITER is scheduled in 2005. The US has been a leader in the science
and engineering of technology testing on ITER and other fusion devices and has many unique
capabilities to contribute to the ITER TBM program. But owing to the time lost following the

  

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

 

Collections: Plasma Physics and Fusion