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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.
J. J. Hancke, G. T. Van Rooyen, J. P. R. De Villiers
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 49-56
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15825
Articles are hosted by Taylor and Francis Online.
The crushing strength (load at fracture) of coated particles was measured by compression between soft metal anvils. The method requires no sample preparation and can be used as a quality control method as well as a valuable tool for comparing different coating conditions during the manufacture of TRISO particles. Batches of coated particles manufactured with different coating parameters were prepared and tested. Batches prepared under different conditions exhibited significant differences in crushing strength. Higher argon concentrations in the coater gas mixture resulted in higher crushing strength. Anomalies in the crushing strength of particles are related to defects and possibly residual stresses produced during coating. The influence of annealing at 1950°C on crushing strength was also investigated. The average crushing strength of batches of particles decreased with annealing. Different preparation methods showed a marked difference in the level of deterioration of the particles with annealing. Batches produced with 80% argon gas mixture at 1300°C showed the greatest reduction in crushing strength. An inverse correlation was found between the crushing strength and the uranium that is leached from batches. The particles with the lowest crushing strength would also be more susceptible to mechanical damage during handling and consequently also to leaching of the uranium during leach tests.