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Latest News
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.
N. Ohyabu, A. Komori, A. Sagara, H. Suzuki, T. Morisaki, S. Masuzaki, T. Watanabe, N. Noda, O. Motojima
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 699-705
Divertor Design and Experiments | doi.org/10.13182/FST96-A11963018
Articles are hosted by Taylor and Francis Online.
LHD divertor development program has generated various innovative divertor concepts and technologies which will help to improve the plasma performance in both helical and tokamak devices. They are two divertor operational scenarios (confinement improvement by generating high temperature divertor plasma and simultaneous achievement of radiative cooling and H-mode-like confinement improvement). Local island divertor geometry has also been proposed. This new divertor has been successfully tested in the CHS device and is planned to be installed in the LHD device. In addition, technological development of new efficient hydrogen pumping schemes (carbon sheet pump and membrane pump) are being pursued for enhancement of the divertor control capability.