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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.
H. Yamasaki, K. Kashimura, T. Kanazawa, K. Katayama, N. Yamashita, S. Fukada, M. Nishikawa
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1151-1154
Blanket and Breeder Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12619
Articles are hosted by Taylor and Francis Online.
It is observed that a fair amount of physical and chemical adsorbed water is released from solid breeder materials by introduction of dry N2 gas and that not a little amount of water is also continuously produced by the water formation reaction when the purge gas with hydrogen is applied. It is reported by present authors that the water released to the purge gas from solid breeder materials affects the tritium release behavior. The capacity and desorption rate of chemical adsorbed water, and the capacity and rate of water formation reaction for Li4SiO4, which has been supplied from FzK, are quantified in this study. It is found that the overall reaction rate of water formation on Li4SiO4 is larger than the rate observed for other solid breeder materials. Therefore, most hydrogen added to the blanket purge gas changes to water so far as the water formation capacity of Li4SiO4 remains. It is also found that water formation capacity of Li4SiO4 is almost the same as that of Li2TiO3. Tritium release behavior from Li4SiO4 and Li2TiO3 packed in the blanket are compared in this paper using the Kyushu University model and properties obtained in this study.