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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.
E. Treille, J. Wendling, F. Plas
Nuclear Technology | Volume 174 | Number 3 | June 2011 | Pages 353-363
Technical Paper | TOUGH2 Symposium / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A11745
Articles are hosted by Taylor and Francis Online.
The choice of the Callovo-Oxfordian formation in eastern France for construction of a proposed repository for high-level, long-lived radioactive waste (HLW) is based primarily on the low hydraulic conductivity of the clay-rich host rock. This property is also intrinsically linked to a low capacity of the rock to evacuate the significant amounts of hydrogen gas generated over time by processes such as anoxic corrosion of metallic materials and radiolysis of organic waste. The effects of hydrogen production on the behavior and safety performance of the disposal system components must be evaluated for the operating and postclosure periods of the repository. In order to do this, numerical simulations using TOUGH2-MP were performed on a vitrified waste (HLW) disposal cell and its access drift, for the operating period. The objective was to investigate generation and transfer of hydrogen within and outside the disposal cell, coupled with the desaturation of the access drift near field due to the combined action of drift ventilation and the coupled behavior of dry air and hydrogen within the disposal cell. Particular attention was focused on the form of hydrogen (expressed or dissolved), total gas pressure buildup, degree of gas saturation, gas transport pathways, gas concentrations, and gas exchanges between the disposal cell and the access drift.Simulation results show the validity of the conceptual assumption based on anoxic conditions in the useful part of the disposal system. The major part of the hydrogen comes to the access drift during the operating phase. Internal boundaries between interface zones and concrete lining are preferential pathways for the gas transfer.