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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.
J. D. Baker, D. H. Meikrantz, R. J. Pawelko, R. A. Anderl, D. G. Tuggle
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 8-13
doi.org/10.13182/FST95-A11963798
Articles are hosted by Taylor and Francis Online.
A zirconium-manganese-iron alloy, St 909, was evaluated as a purifier in tritium handling, transport, and storage applications. High efficiency removal of CH4, CO, CO2, NH3, and O2 was observed at concentrations of 0.1 to 1% in helium. Gas streams at 100 to 5000 sccm were passed through getters operated at 600–800°C. On-getter residence times of two seconds were required to achieve >99% removal of these reactive impurities. At this removal efficiency level, the individual impurity capacity of 100 g of St 909 purifier at 800°C was 0.59, 0.28, 0.19, 0.14 and 0.12 moles of CH4, CO, CO2, O2 and NH3, respectively. Hydrogen containing gasses; CH4 and NH3; were cracked on the purifier and the resultant elemental hydrogen was released. Only 8 ± 2 scc of H2 were retained on 100 g of St 909 at 800°C. These features suggest that this alloy can be employed as an efficient purifier for hydrogen isotopes in inert gas, nitrogen, or perhaps even H, D, or T streams.