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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.
Conor O’Carroll, Klaus Lassmann
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 268-273
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34697
Articles are hosted by Taylor and Francis Online.
To describe the transport of volatile fission products along grain boundaries in nuclear fuels, a nonlinear diffusion equation must be used. Analytic solutions exist for the steady-state case, but the equation seems to be intractable when time dependence is included. A simple implicit numerical method has been developed that can guarantee a convergent stable solution when there is a central void. If there is no void, the method always yields a solution. There is perfect agreement between the analytic and numerical solutions for the steady state, and the method developed here offers significant advantages over other methods of solution. This basic model can be used in nuclear fuel performance studies.