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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.
M. Fujiwara
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 58-70
Overview Paper | doi.org/10.13182/FST95-A11947047
Articles are hosted by Taylor and Francis Online.
Recent research has made significant progress for the plasma confinement in helical systems. Experiments have been carried out in W7AS, CHS, ATF, H-E and others. The plasmas, whose electron temperature is around 2–3keV, ion temperature is 1 keV and density is 2–3×1020 m-3, are well confined with the energy confinement time τ E =10–40ms and the stable beta value reaches at < β >> 2% (β (0)=7%)[1]. The obtained scalings for the global energy confinement time such as LHD, GRB(Gyro-Reduced Bohm), L-G(Lackner-Gottardi) scalings are comparable with the tokamak L-mode scaling in the above parameters' range. The improved confinement modes are also explored in helical systems as H mode or the control of plasma profile.
In this paper, firstly present experimental results are reviewed on the confinement, MHD equilibrium/stability beta limit, and secondly the outline of LHD and W7X program is described.
Finally, is discussed the feasibility of helical systems as a fusion reactor, based on the present experimental results.