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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.
Sol-Il Su, Man-Sung Yim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 71-88
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3078
Articles are hosted by Taylor and Francis Online.
Ion-exchange resins represent one of the most important waste streams in low-level waste management due to the unstabilized nature of the waste form and the large amount of radioactivity contained. To describe the release of radionuclides from ion-exchange resins stored in a disposal facility, a mechanistic release model was developed. The model is based on description of radionuclide migration both in the resin bead phase and the bulk pore water phase within waste containers. This modeling setup provides the capability to describe all the major physical processes taking place for the release of radionuclides. Because of the difficulty in obtaining analytical solutions, the numerical solution approach was employed in this model.The new resin release model was used to examine key processes and parameters in describing radionuclide release. These were found to be diffusion within the bulk pore water phase, flow rate of infiltrating leachant water, concentration of counterions of the leachant water, and sorption during the transport in the bulk pore water phase. Some parameters were found to have little impact in describing the release. These include the interdiffusion coefficient within resin beads and the density and radius of resin beads. Existing simplified modeling approaches were also compared with the new resin release model, and validities of using these simplified models are discussed.