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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.
Osamu Mitarai, Sigeru Sudo
Fusion Science and Technology | Volume 27 | Number 4 | July 1995 | Pages 377-388
Technical Paper | Plasma Engineering | doi.org/10.13182/FST95-A30358
Articles are hosted by Taylor and Francis Online.
Ignition characteristics in deuterium-tritium helical (stellarator) reactors of various sizes are studied with the operation path method on the plane and the POPCON method. Based on empirical large helical device scaling, confinement must be improved by a factor > 1.5 for reaching ignition and a factor >γH = 2 for optimum fusion power in a helical reactor with R > 8 m, ā = 2 m, and B0 > 6 T. The density limit and the confinement time saturation effect with respect to the density degrade the favorable density scaling of the confinement time (τE ∝ n0.69) and are found to be important limiting factors for ignition characteristics. For a reactor with R = 10 m, ā = 2 m, γH = 2, and B0 = 7 T and with an excess heating power Pex = 100 MW, the minimum auxiliary heating power is ∼55 MW at an operating density 40% below the density limit, and ignition can be reached in a finite time. The ignition characteristics for larger size reactors (R = 15 and 20 m) and gyro-reduced Bohm scaling are also studied.