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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.
D. Demange et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 182-187
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A908
Articles are hosted by Taylor and Francis Online.
This work deals with an indirect and non destructive measurement of tritium in solids. Instead of measuring tritium, we propose to measure the production rate of the decay product: 3He.The amount of tritium enclosed inside a waste drum can be determined with an adapted 3He ingrowth method that takes into account the leak rate of the drum. The model leads to different ways to quantify tritium in the drum. It is confirmed using reference drums that measuring the 3He leak by confining the drum during its equilibrium state gives the same result as sampling the drum atmosphere at the beginning of the storage. For each method, the appropriate apparatus, experimental procedures and calculation of tritium activity from mass spectrometric 3He measurements are detailed. Performances of these techniques are studied and discussed.In addition, we describe a novel and fully automated apparatus based on the confinement method that makes it possible to achieve a close tritium inventory of all the waste drums stored or produced at CEA Valduc.