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Fusion Science and Technology
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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.
S. Morita, H. Yamada, R. Akiyama, A. Ando, H. Arimoto, K. Ida, H. Idei, H. Iguchi, O. Kaneko, S. Kubo, R. Kumazawa, K. Matsuoka, T. Minami, T. Morisaki, S. Muto, K. Narihara, K. Nishimura, S. Okamura, T. Ozaki, S. Sakakibara, C. Takahashi, K. Tanaka, J. Xu, I. Yamada
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 239-243
Helical Systems | doi.org/10.13182/FST95-A11947078
Articles are hosted by Taylor and Francis Online.
Particle confinement time τp has been obtained from measurements of poloidal and toroidal distributions of Ha and Lyman a emissions in CHS. These particle confinement times range between 1.5 and 4ms at a constant line-averaged density of 3×1013cm–3 for both cases of limiter- and divertor-dominated NBI plasmas with Ti-gettering. In these cases the energy confinement time τE were between 2 and 3ms. The density decay characteristic time τp* and global recycling coefficient R have been also measured for Ti-gettered plasmas and large τp* values were observed. As a result high recycling rates (R>0.92) are obtained for a wide density range. For a limiter-dominated case of boronized plasmas (Rax=92.1cm) values of τp were correlated with τE and a linear correlation between them was found for normalized τE to P-0.58 which is a power degradation term in LHD empirical scaling.