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Fusion Science and Technology
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.
S.C. McCool, A.J. Wootton, R.V. Bravenec, P.H. Edmonds, K.W. Gentle, H. Huang, J.W. Jagger, B. Richards, David W. Ross, E.R. Solano, J. Uglum, P.M. Valanju
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 444-450
Advanced Tokamak And Steady-State Sustainment Systems | doi.org/10.13182/FST95-A11947125
Articles are hosted by Taylor and Francis Online.
Recent favorable results on START have caused renewed interest in low aspect ratio tokamaks. To design an economical next-step spherical tokamak to study confinement scaling and high beta plasmas, we have developed a transport scaling and device optimization code. This code OPT, benchmarked against START, includes 10 empirical confinement scaling laws and essential tokamak physics such as stability limits. Parameters are optimized separately for each scaling law and physics goal. Using OPT we find for R/a=1.2 to 2.0 one can achieve βN=5 and <β>=30% with just two neutral beams (PNB<3.5 MW) for Ip≥0.75 MA, and Ro≥0.6 m. In contrast, if one insists on using the nominal device parameters, Ip=1 MA and Ro=0.8 m, with each scaling law, achieving βN=5 requires typically PNB⋍7.5 MW.