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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.
G. Modica, R.A.H. Edwards
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 75-78
doi.org/10.13182/FST95-A11963808
Articles are hosted by Taylor and Francis Online.
Tritiated water (Q2O) is produced during fusion fuel purification or air detritiation. Before recovering the tritium by isotope separation, the Q2O needs to be reduced to form Q2 gas. The reduction of tritiated water on iron is an alternative to electrolysis and gas-shift reactors. It allows a simple, compact, configuration with low tritium inventory. The reactor design incorporates a palladium alloy permeator which extracts the Q2.
Tests on a commercial iron-based catalyst showed a high reactivity and no degradation with repeated cycling. The optimum temperature for water reduction was 375–395 C, and for iron regeneration using hydrogen, 470–495 C. The first prototype reactor-permeator decomposed 9.5 g water in 8 hrs using 210 g iron. The time needed for iron regeneration was reduced to 16 hrs by recirculating the hydrogen. A pilot-scale reactor permeator is now under development: it should be capable of reducing 35 kg of water per year, operating at 1 bar. Attention to the choice of structural materials will minimise tritium carryover into the water produced during regeneration.