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ANS Student Conference 2025
April 3–5, 2025
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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.
Yeon Soo Kim, D. R. Olander, S. K. Yagnik
Nuclear Technology | Volume 128 | Number 3 | December 1999 | Pages 300-312
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3033
Articles are hosted by Taylor and Francis Online.
As a means of improving the gap-thermal conductance, a liquid metal (LM) is proposed as the gap-filling material replacing helium gas in the conventional light water reactor fuel rod. The potential application of the concept includes power reactor fuel rods, special-purpose test-reactor experimental rods, and mixed-oxide fuel rods. Novel fabrication methods to ensure a uniform LM-filled gap between the fuel and the cladding of minirods have been developed. The main concern was overcoming the large surface tension of an LM to eliminate LM-free spots in the gap. Compatibility tests of the LM with a Zircaloy tube have been conducted. Liquid gallium showed excessive reaction with Zircaloy at 350°C for a month. Liquid Bi-Sn-Pb alloy, on the other hand, showed a nearly negligible reaction with Zircaloy under the same conditions. Thermal superiority of the LM-bonded gap over a conventional helium-gas gap in a miniature fuel rod was confirmed through theoretical calculations and experimental measurements. The experiments involved water-quenching the element from 600°C and measuring the decrease of the fuel centerline temperature. The LM-bonded element reached 100°C in 10 s, while the gas-bonded element required nearly 100 s to attain this temperature.