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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.
Andrey Markin, Alexander Gorodetsky, Francesco Scaffidi-Argentina, Heinrich Werle, Chung H. Wu, Andrey Zakharov
Fusion Science and Technology | Volume 38 | Number 3 | November 2000 | Pages 363-368
Technical Paper | Special Issue on Beryllium Technology for Fusion | doi.org/10.13182/FST00-A36151
Articles are hosted by Taylor and Francis Online.
Deuterium trapping in beryllium oxide films irradiated with 400 eV D ions has been studied by Thermal Desorption Spectroscopy (TDS). It has been found that for thermally grown BeO films implanted in the range 300–900 K the total deuterium retention doesn’t depend on irradiation temperature whereas TDS spectra are temperature dependent. For R.T. implantation the deuterium is released in a wide range from 500 to 1100 K. At implantation above 600 K the main portion of retained deuterium is released in a single peak centered at about 1000 K. The similar TDS peak is measured for D/BeO co-deposited layer. In addition we correlate our implantation data on BeO with the relevant data on beryllium metal and carbon. The interrelations between deuterium retention and microstructure are discussed.
