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NEA irradiation system ready to deploy at MITR
A new irradiation experimental system is ready for deployment. The rig, which is the focus of In-Core Real-Time Mechanical Testing of Structural Materials (INCREASE-I), an OECD Nuclear Energy Agency project, will be used to conduct stress-relaxation tests of stainless steel at the Massachusetts Institute of Technology Reactor (MITR), according to the OECD NEA.
Jonathan B. Lister, Ferdinand Hofmann, Jean-Marc Moret, Felix Bühlmann, Michael J. Dutch, Damien Fasel, Alain Favre, Pierre-Francois Isoz, Blaise Marletaz, Philippe Marmillod, Yves Martin, Albert Perez, David J. Ward
Fusion Science and Technology | Volume 32 | Number 3 | November 1997 | Pages 321-373
Technical Paper | Plasma Control Issues for Tokamaks | doi.org/10.13182/FST97-A1
Articles are hosted by Taylor and Francis Online.
The general control of tokamak plasmas has evolved considerably over the past few years with an increase in the plasma pulse length, an increase in the control of additional heating and fueling, and an increase in the degree to which the shape of the plasma can be varied. The Tokamak Configuration Variable (TCV) is specifically designed to explore the operational benefits of plasma shaping over a wide variety of plasma shapes. Consequently, considerable attention has been given to the control of the poloidal field coil currents that impose the desired shape. All aspects of the control of TCV plasmas, from the diagnostic measurements to the power supplies, via particular control algorithms and overall supervision are discussed.