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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.
Paul A. Demkowicz, James L. Jerden, Jr., James C. Cunnane, Noriko Shibuya, Ronald Baney, James Tulenko
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 157-170
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3522
Articles are hosted by Taylor and Francis Online.
The aqueous dissolution of irradiated and unirradiated uranium-thorium dioxide, (U,Th)O2, fuel pellets in Yucca Mountain well water has been investigated. Whole and crushed pellets were reacted at 25 and 90°C for periods of up to 195 days. The fuel dissolution was measured by analyzing the concentrations of soluble uranium, thorium, and important fission products (137Cs, 99Tc, 237Np, 239Pu, 240Pu, and 241Am) in the well water. The surface-area-normalized fractional uranium release rates for unirradiated crushed uranium dioxide (UO2) pellets were 10 to 40 times higher than the values for (U,Th)O2 fuel. Similarly, the dissolution rates of irradiated (U,Th)O2 pellets with compositions ranging from 2.0 to 5.2% UO2 were at least two orders of magnitude lower than reported literature values for pure UO2. These results demonstrate an advantage of (U,Th)O2 over UO2 in terms of matrix dissolution in groundwater and suggest that (U,Th)O2 fuel is a more stable long-term waste form than conventional UO2 fuel.
