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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.
K. Kobayashi, T. Hayashi, Y. Iwai, N. Asanuma, M. Nishi
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 673-677
Safety and Safety System | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22672
Articles are hosted by Taylor and Francis Online.
To construct the ITER with high safety and acceptability, it is very important to grasp the removal behavior of tritium happened to leak in the room, the final confinement barrier. In order to obtain data on tritium removal behavior from atmosphere in a room under the various conditions (humidity, ventilation flow rate), intentional tritium release experiments have been carried out with the Caisson Assembly for Tritium Safety Study (CATS) which consists of 12 m3 gas-tight box (Caisson) for the study of tritium behavior in large space. Effect of adding water vapor has also investigated for effective removal. When the tritiated water existed in the released tritium, residual contamination on the wall of the Caisson was detected under the various ventilation flow rate and it was found that it depended on the initial humidity in the Caisson. On the other hand, when the water vapor was added into the Caisson after found the residual contamination, the residual contamination was removed quickly on the wall of the Caisson. The adding water vapor into the Caisson, it was effective for the tritium removal. Analytical work have also progressed and analyzed tritium removal behavior became to be in good agreement with the experimental results by considering the adsorption and desorption reaction rate of tritiated water on the wall.