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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.
S. I. Abdel-Khalik, L. Crosatti, D. L. Sadowski, S. Shin, J. B. Weathers, M. Yoda, ARIES Team
Fusion Science and Technology | Volume 54 | Number 3 | October 2008 | Pages 864-877
Technical Paper | Aries-Cs Special Issue | doi.org/10.13182/FST08-A1907
Articles are hosted by Taylor and Francis Online.
This paper describes a numerical and experimental investigation in support of the ARIES-CS divertor design, which selected a modular, helium-cooled, T-tube design that can accommodate a peak heat load of 10 MW/m2. Numerical analyses were carried out using the FLUENT computational fluid dynamics software package to evaluate the thermal performance of the divertor at the nominal design and operating conditions. Sensitivity studies were also performed to determine the effect of variations in geometry and operating conditions resulting from manufacturing tolerances and/or flow maldistribution between modules. The results indicate that the selected design is "robust" with respect to such anticipated variations in design and operational parameters and that a peak heat flux of 10 MW/m2 can be accommodated within the constraints dictated by material properties. Extremely high heat transfer coefficients [>40 kW/(m2K)] were predicted by the numerical model; these values were judged to be "outside the experience base" for gas-cooled engineering systems. Hence, an experimental investigation was undertaken to verify the results of the numerical model. Variations of the local heat transfer coefficient within an air-cooled, geometrically similar test module were measured at the same Reynolds number as the actual helium-cooled divertor. Close agreement between the model predictions and experimental data was obtained. The results of this investigation provide added confidence in the results of the numerical model used to design the ARIES-CS divertor and its applicability to other gas-cooled high-heat flux components.