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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.
Peter Hofmann, Siegfried J. L. Hagen, Gerhard Schanz, Alfred Skokan
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 146-186
Nuclear Safety | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT-TMI2-146
Articles are hosted by Taylor and Francis Online.
Chemical interactions that may occur in a light water reactor fuel rod bundle containing Ag-In-Cd absorber rods or Al203/B4C burnable poison rods with increasing temperature up to the complete melting of the components and the reaction products formed are described. The kinetics of the most important chemical interactions is investigated and the results are described. In most cases, the reaction products have lower melting points or ranges than the original components. This results in a relocation of liquefied components, often far below their melting points. Three distinct temperature regimes exist in which liquid phases can form in the core in different large quantities and are described in detail. The phase relations in the important ternary U-Zr-0 system are extensively studied. The effect of steel constituents on the phase relations is also given. These considerations focus on pressurized water reactor conditions only.