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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.
Heinz Nabielek, Werner Schenk, Werner Heit, Alfred-Wilhelm Mehner, Daniel T. Goodin
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 62-81
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34196
Articles are hosted by Taylor and Francis Online.
Coated particles embedded in graphitic elements are the fuel for the High-Temperature Reactor (HTR). Experimental investigations of the performance of particles at extremely high temperatures have been conducted to achieve an understanding of coating failure mechanisms and to establish the data base for safety and risk analyses of hypothetical accidents in large-and medium-sized HTRs. The primary mechanism for coating failure and fission product release in the 1900 to 2500°C temperature range is thermal decomposition of silicon carbide (SiC). Heating tests have provided the activation energy of this process and the correlation of SiC decomposition with coating failure and subsequent fission product release. The process of fission product release proceeds in several stages. A certain amount of SiC removal at high temperatures leads to SiC deterioration, which renders a fraction of particles permeable to cesium and strontium. During 50°C/h ramped heating tests, the cesium release approaches 100% at 2500°C. With the onset of SiC failure, the release process of xenon, krypton, and iodine via diffusion through the pyrocarbon (PyC) is initiated. Under all heating conditions examined, krypton release is significantly delayed relative to cesium release due to the higher diffusivity of cesium in PyC. In the intermediate temperature range of 1600 to 1700°C (the maximum temperature in small, modular HTRs), SiC decomposition rates are negligible, and coated particle fuels retain all safety-relevant fission products.