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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.
Yuuki Edao, Satoshi Fukada, Hidetaka Noguchi, Yasushi Maeda, Kazunari Katayama
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 831-835
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST56-831
Articles are hosted by Taylor and Francis Online.
Rates and amounts of absorption and desorption of hydrogen and deuterium in a Li0.17Pb0.83 eutectic alloy are determined under the conditions of temperature of 400-700°C and the upstream H2 or D2 partial pressure of 103Pa-105 Pa by using a one-dimensional permeation pot. Because of small interaction between the alloy and dissolved atoms of hydrogen isotopes, the temperature dependence of the Sieverts' solubility constant for the Li0.17Pb0.83 -H or -D system, i.e., the enthalpy change of absorption or desorption, is small, and the absolute value of D solubility is higher than that of H. The isotope effect of diffusivity between H and D is very small. The generation rate and inventory of tritium (T) in a fusion blanket is estimated under an assumption of one-dimensional Li0.17Pb0.83 blanket system with a constant and uniform neutron flux.