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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Gilbert Bellanger, Jean Jacques Rameau
Fusion Science and Technology | Volume 36 | Number 3 | November 1999 | Pages 296-308
Technical Paper | doi.org/10.13182/FST99-A110
Articles are hosted by Taylor and Francis Online.
In addition to the tritiated water produced by the Commissariat à l'Energie Atomique, large quantities result from the development of controlled fusion reactors for power generation (International Thermonuclear Experimental Reactor). To obtain a new industrial method of reducing tritiated water, an electrolytic rather than a chemical process was developed. A prototype electrolyzer is described and the results obtained are given. In this process, the tritium recovery system is based on the principle of a gas diffusion Pd-Ag electrode incorporating a tritium charging cathode, which produces very pure hydrogen isotope gases. This is for converting 3H2O to high-purity 3H2 and its isotopes from tritiated water with >30 TBq/cm3 radioactivity (>50% 3H2O). The prototype module has been tested in a hot laboratory. The overall operating time exceeded 1500 h, and 6 g of gaseous tritium were produced without difficulty.