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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.
Kenji Takeshita, Yuezhou Wei, Mikio Kumagai, Yoichi Takashima, Masami Shimizu
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1572-1578
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-A30636
Articles are hosted by Taylor and Francis Online.
The application of H2/HTO isotopic exchange method to the tritium recovery at reprocessing plants was investigated. The size of multiunit exchange column was evaluated numerically for the recovery of tritium from the waste water containing a main impurity, HNO3. The Pt-catalyst packed in the exchange column undergoes weak poisoning by HN03. However, the exchange efficiency of catalyst bed η c is maintained at 0.75 even in the presence of 0.1 mol/l HNO3. As the HNO3 concentration in the waste water is estimated as the order of 10−2 mol/l, the column size is little affected by the HNO3 poisoning. The height and diameter of exchange column required for recovering 99% of tritium generated in a 4 t/d reprocessing plant (recovery efficiency ɛ=0.99) are evaluated as about 6m and 0.63m, respectively. When the tritium concentration in the waste gas is depleted below the environmental protection standard (ɛ=0.9999996), they are evaluated as about 19m and 0.57m, respectively.
