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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.
Yoichi Sakuma, Toshiki Kabutomori, Haruo Obayashi, Yuichi Wakisaka, Keizo Ohnishi
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 91-94
doi.org/10.13182/FST95-A11963811
Articles are hosted by Taylor and Francis Online.
In order to separate and store tritium (T) in the nuclear fusion cycle, we investigated the use of a hydrogen storage alloy which is safer and more easily handled than other materials, especially uranium. The solid solution alloy TiCr0.4V1.2Fe0.4 was chosen for the investigation because it resists pulverization and is easily activated. Using this alloy, we measured the storage volume, the equilibrium pressure and the isotope effect of absorption and desorption reactions in a low (10−2 ~ 102 Pa) hydrogen atmosphere pressure. The alloy had an absorbing volume of H/M = 0.5 by atomic ratio and the equilibrium absorbing pressure was almost the same as uranium's at the same ambient temperature. The equilibrium reaction has no isotope effect, but the reaction velocity between H2 and the alloy was twice that between D2 and the alloy. Even after several hundred repetitions of hydrogen absorption and desorption, still no change in the alloy was observed.