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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.
Jae-Woo Ju, Sang-Moon Lee, Kwang-Yong Kim
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 274-281
Technical Paper | Fission Reactors/Thermal Hydraulics | doi.org/10.13182/NT13-A15783
Articles are hosted by Taylor and Francis Online.
The outlet plenum of a pebble bed modular-type gas-cooled nuclear reactor was optimized using three-dimensional Reynolds-averaged Navier-Stokes analysis and optimization techniques. A shear stress transport turbulence model was used as a turbulence closure. Two design variables for the optimization were selected: dimensionless displacement on the horizontal line and the angle of rotation about the center of gravity of the roof support block. The objective function was defined as a pressure drop between the inlet and the outlet of the outlet plenum. Latin hypercube sampling was used for selecting experimental design points within the design space. The objective function value was obtained at each design point through numerical analysis. The results show that the optimal design significantly improved the performance of the outlet plenum with respect to pressure drop. Through optimization, the pressure drop decreased by 11.8% compared to the pressure drop under the reference geometry.