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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.
Y. Fuji, K. Itoh, A. Fukuyama, S.-I. Itoh
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 485-488
Confinement and Transport Studies | doi.org/10.13182/FST95-A11947134
Articles are hosted by Taylor and Francis Online.
In order to study the particle transport and the mechanism of the L/H transition in tokamaks, a one-dimensional transport code which describes the toroidal and poloidal plasma rotation as well as the radial electric field has been developed. The neoclassical transport, turbulent transport, and ion orbit loss are included. Using a a turbulent transport, model based on the current, diffusive high-n ballooning mode and a fixed temperature profile, the density profile in a steady state and the dependence on the edge temperature are studied. With high edge temperature, the density gradient near the edge becomes steep and a H-mode like density profile is obtained. The preliminary calculation including heat, transport is also presented.