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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.
Yifeng Wang, Carlos F. Jove-Colon, Patrick D. Mattie, Robert J. MacKinnon, Michael E. Lord
Nuclear Technology | Volume 171 | Number 2 | August 2010 | Pages 201-219
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A10783
Articles are hosted by Taylor and Francis Online.
Water is the most important reacting agent that directly controls radionuclide release from a nuclear waste repository to a human-accessible environment. In this paper, we present a water balance model to calculate the amount of water that can accumulate inside or percolate through a breached waste package in Yucca Mountain repository environments as a function of the temperature and relative humidity in the surrounding waste emplacement drift, the rate of water dripping from seepage, the area of breaches on the waste package, and the extent of waste degradation. The model accounts for sheet flows created as water drips fall onto the waste package surface, water vapor diffusion across waste package breaches, and water vapor equilibrium with unsaturated porous corrosion products. Preliminary model simulation results indicate that a breached waste package may maintain a large part of its barrier capability, and probably <1% of the total seepage flux impinging on the waste package surface can enter the package. Vapor diffusion of water through the breaches can be as important as liquid water flow into the waste package. Waste degradation reactions can consume a significant fraction of water entering the waste package. The water saturation inside waste packages will be low (<0.5), and the advective water flux out of a waste package will be small (with the mean value <0.5 [script l]/yr per package) over a wide range of seepage rates considered (1 to 1000 [script l]/yr). Furthermore, the ionic strength of in-package water will remain relatively high for the first 10000 yr, which will likely destabilize colloid suspensions and limit colloid releases.