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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.
A.B. Antoniazzi, W.T. Shmayda
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 879-884
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963048
Articles are hosted by Taylor and Francis Online.
Tritiated waste and glovebox cleanup systems contain significant levels of trititated methane impurities which require reducing and processing to recover the tritium. A viable approach to the recovery of tritium is the conversion of tritiated methane into elemental tritium and carbon by thermal cracking on a heated metal matrix.
Through the conversion reaction of HTO/H2O with hot Al4C3 powder, tritiated methane concentrations in the 0.4 to 0.9 mCi/m3 range are achievable. The HTO/H2O ratio is ~10-7.
Conversion efficiencies for the decomposition of methane are measured for Zr-Fe-Mn alloy, iron oxide and supported nickel catalyst. HT and HTO are created by decomposing methane. Zr-Fe-Mn alloy achieved a maximum conversion efficiency of ~70% at 700°C. Iron oxide thermally cracked methane at 36% at a temperature of 700°C. Supported nickel operating at 450°C achieved conversion efficiencies ranging from 65 to 100%.