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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.
William E. Kastenberg, Clyde D. Newman
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 241-251
Technical Paper | Economic | doi.org/10.13182/NT92-A34619
Articles are hosted by Taylor and Francis Online.
A cost/risk framework is developed to compare waste management alternatives such as partitioning and transmutation (P-T) to the currently open light water reactor fuel cycle in the United States in which spent fuel will be buried in a geologic repository. This framework has utility for developing economic values associated with long-term risk and was originally developed as part of a system study to define and determine the scope of the driving features of a P-T scheme involving nonconventional (pyrochemical) reprocessing and a fast-spectrum reactor fueled primarily with minor actinides. A potentially significant benefit is shown to be obtainable in the form of reduced long-term repository health risks; although the primary risk reduction is derived from the destruction or selective packaging and disposal of 99Tc and 129I, the modification of probabilities associated with site-specific repository features or highly uncertain future events could affect these results. The potential benefits are represented as a cost stream and appear as a large annual investment available for the development and implementation of P-T. Preliminary results suggest further studies in selected areas; a particularly significant near-term health risk benefit is expected to arise from reduced uranium mining and purification activities associated with the closure of the currently open fuel cycle. Although the cost/risk framework was originally developed to evaluate a specific waste management concept, similar analyses can be used to evaluate other waste management schemes as well. Reprocessing of spent fuel to recover specific problem isotopes is an obvious possibility but may lack the overall flexibility engendered in P-T to address the complete spectrum of public concerns.