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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.
G. H. Neilson
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 428-431
Advanced Tokamak And Steady-State Sustainment Systems | doi.org/10.13182/FST95-A11947121
Articles are hosted by Taylor and Francis Online.
The Tokamak Physics Experiment (TPX) is planned to develop the scientific basis for an economically competitive and continuously operating tokamak fusion power source. It has been designed to have steady-state operating capability, sufficient performance to produce reactor-like plasma configurations, and a flexible set of steady-state plasma controls. Active plasma control (e.g., current profile control, shape and position control, passive and active MHD mode stabilization, and toroidal rotation control) is a key to achieving steady stale tokamak operating conditions with enhanced beta and confinement, efficient current drive, high purity, and high reliability. Inductive scenarios and steady-state operating modes with current-drive have been studied to determine the system requirements for access and maintenance of advanced steady-state modes. Industry contractors have begun detailed engineering design of the superconducting magnets, vacuum vessel, and plasma-facing components.