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IAEA-CN-33/G 3-3 ENGINEERING DESIGN OF A
 

Summary:  IAEA-CN-33/G 3-3
ENGINEERING DESIGN OF A
FUSION TEST REACTOR (FTR) AND
FUSION ENGINEERING RESEARCH FACILITY
(FERF) BASED ON A TOROIDAL THETA PINCH
M. ABDOU, R.J. BURKE, P.V. DAUZVARDIS, M. FOSS,
S.A.W. GERSTL, V.A. MARONI, A.W. PIERCE, A.F. TURNER
Argonne National Laboratory, 111.
R.A. KRAKOWSKI, R.K. LINFORD, T.A. OLIPHANT,
F.L. RIBE, K.I. THOMASSEN
Los Alamos Scientific Laboratory, Los Alamos, N. Mex.,
United States of America
Abstract
ENGINEERING DESIGN OF A FUSION TEST REACTOR (FTR) AND FUSION ENGINEERING RESEARCH FACILITY
(FERF) BASED ON A TOROIDAL THETA PINCH.
This paper describes two advanced toroidal theta-pinch devices which are being proposed for future
construction. The Fusion Test Reactor (FTR) is being designed to produce thermonuclear energy (at 20 MeV/
neutron) equal to the maximum plasma energy (Q = 1) and to demonstrate a-particle heating. The Fusion
Engineering and Research Facility (FERF) is being designed to test materials in a fusion environment where the
average 14-MeV neutron flux from the plasma is . 5 x 1013

  

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

 

Collections: Plasma Physics and Fusion