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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.
Jing-Luen A. Shih, Robert M. Brugger†
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 217-223
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT92-A34677
Articles are hosted by Taylor and Francis Online.
Application of gadolinium in neutron capture therapy is under evaluation. Crucial to development of this therapy is an imaging technique that would show the distribution and concentration of parts-per-million amounts of I57Gd in sliced samples. A technique that utilizes the principles of autoradiography and neutron radiography has been tried. The images taken with this method display the gadolinium distribution and its relative concentration in samples. Concentrations of I57Gd ranging from ∼20 to 500 ppm can be determined. The intrinsic spatial resolution of the system used in the Missouri University Research Reactor is 70 μm.
