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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.
Takumi Hayashi, Masayuki Yamada, Takumi Suzuki, Yuji Matsuda, Kenji Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1503-1508
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30625
Articles are hosted by Taylor and Francis Online.
A new tritium removal system using gas separation membranes has been studied to develop more compact and cost-effective system for a fusion reactor. To obtain necessary parameters, which are directly scale able to the ITER Atmospheric Detritiation System, the basic tritium recovery performance was investigated with a scaled polyimide membrane module (hollow-filament type : 10 m3/hr ) loop. The result shows that the H2 recovery ratio from N2 or Air was more than 99 % or about 97 %, respectively, at flow rate ratio of permeated/feed =0.1, feed & permeated side pressures = 2580 & 80 torr, and module temp. = 293 K. Tritium (HT) recovery function was almost the same of H2 recovery, even though the total hydrogen concentration was a few ppm in the feed of module. H2O recovery performance was better than hydrogen recovery. These recovery functions were improved effectively decreasing the pressure ratio of permeated/feed of module.
