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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.
Robert V. Strain, Lawrence A. Neimark, John E. Sanecki
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 187-190
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27645
Articles are hosted by Taylor and Francis Online.
Detailed microstructural and microchemical examinations of samples of debris extracted from the lower plenum region of the Three Mile Island Unit 2 reactor were performed using optical and electron-beam instrument microscopy. Results of this study indicate that this material was a previously molten ceramic consisting primarily of UO2 and ZrO2 with smaller amounts of iron, chromium, nickel, and aluminum present also as oxides. The microstructures of the samples were typical of cast multicomponent materials, i.e., rounded grains with additional phases in the grain boundaries. In most cases, the primary grains appeared to be singlephase material as would be expected if a UO2-ZrO2 solid solution were rapidly cooled from the liquid state. However, portions of these grains showed indications of segregation into two distinct phases, and in some areas the whole grains were segregated into two phases. The segregated grains are indicative of a slower cooling rate for part of the material. In addition to the primary urania-zirconia grains, there were large areas of eutectic structure in some of the samples. One of the phases in the eutectic structure consisted of iron and chromium with small amounts of aluminum and nickel, all as oxides. This material was also present in many grain boundaries in the primary grain structure. The grain boundary phase could have a solidus temperature as low as ∼1600K. This low melting point compared to the bulk of the material has led to speculation that the grain boundaries may have remained liquid after the grains themselves had solidified. This would allow the material to flow like wet sand through the structure above the lower plenum at temperatures near or possibly below the melting point of stainless steel (1670 K). At these temperatures, the moving mass would not have severely melted the stainless steel structure near the bottom of the vessel.