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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.
E. L. Grigorescu, A. C. Razdolescu, M. Sahagia, P. Cassette, M. Tanase
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 382-385
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A948
Articles are hosted by Taylor and Francis Online.
An original method, based on the continuous circulation in a closed circuit of saturated HTO vapour, is presented. The saturated vapour are obtained by bubbling from vials containing different tritium standard solutions (IFIN-HH-TDCR method). The main difference from the usual method, elaborated by Osborne, is the use of saturated vapour, which eliminates the measurement in liquid scintillator of the recovered non-saturated vapour. Tritium Monitors type MT-1 made in IFIN-HH were calibrated. The measurements were carried out for three levels of the activity concentration: 0.0180, 0.701 and 1.73 MBq.g-1. The mean response was R=2.25.10-13 A/(MBq m-3) with a relative combined uncertainty lower than 4%. The value agrees with the result obtained with the Osborne method, ROs=2.30.10-13A/(MBq m-3) and with the estimated theoretical value, 2.29 10-13A/(MBq m-3)
