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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.
Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1459-1464
Safety and Environment | doi.org/10.13182/FST96-A11963154
Articles are hosted by Taylor and Francis Online.
As one of thermofluid safety studies in ITER, buoyancy-driven exchange flow behavior through breaches of the vacuum vessel was investigated quantitatively using a preliminary LOVA (Loss Of VAcuum event) apparatus which simulated the Tokamak vacuum vessel of a fusion reactor with a small-scaled model. Helium gas and air were used as the working fluids. Experimental parameters were breach position, breach number, breach length, breach diameter, breach combination and the wall temperature of the VV. The present study showed that the relationship between the exchange rate and time depended on the magnitude of the potential energy from the ground level to the breach position and the wall temperature of the vacuum vessel. The exchange rate decreased as the breach length increased and the breach diameter decreased.