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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.
Gordana Vukovic, Michael L. Corradini
Nuclear Technology | Volume 115 | Number 1 | July 1996 | Pages 46-60
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35274
Articles are hosted by Taylor and Francis Online.
To investigate liquid-metal (fuel)/water (coolant) interactions, a vertical shock tube has been designed and constructed. A series of tests was conducted with gallium, indium, lead, and tin as the fuel materials at either low” (Tf ∼ 300°C) or “high” fuel temperature (Tf ∼ 600°C), with water at room temperature (low Tc) and in the range of Tc = 56 to 67°C (high Tc), and with driving pressures from 0.25 to 1.22 MPa. These materials were tested to determine their compatibility for potential use in liquid-metal divertor systems for fusion power plants. The increase in fuel and water temperature, as well as the increase of driving pressure, caused more energetic interactions to occur. High Tf tin and lead interactions, and high Tf and Tc gallium and indium interactions were the most energetic. Stronger interactions produced finer debris fragments. In high Tf gallium and indium interactions, small superficial oxidation was observed. For the first two pulses, larger ratios of compression- (compression of expansion vessel gas) to-expansion work correspond to the experiments with higher fuel and coolant temperatures. For the first pulse, only work ratio values of the most energetic experiments are larger than those of isothermal experiments. Consequently, for such experiments, the impulse values of second pulses are the largest. Higher values of the conversion ratio for the first pulse correspond to more energetic interactions. Even for the most energetic experiments, the conversion ratio is no higher than 1.2%, and no more than 15% (or a few millimetres-thick surface layer) of the initially loaded fuel participated in the interaction, assuming equal initial volumes of fuel and coolant.