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ANS Student Conference 2025
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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.
Minghui Chen, Xiaodong Sun (Univ of Michigan), Richard N. Christensen (Univ of Idaho)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 835-843
Printed circuit heat exchangers (PCHEs) are promising to be employed in high-temperature gascooled reactors (HTGRs) due to their compactness and intrinsic characteristics of capable of providing high-temperature and high-pressure heat for industrial applications. In our previous study, a reduced-scale zigzag-channel PCHE was fabricated out of Alloy 617 and its heat transfer and pressure drop characteristics were investigated experimentally in a high-temperature helium test facility. In our current study, a computational fluid dynamics (CFD) code, STAR-CCM+, was used to simulate the thermalhydraulic performance of the fabricated PCHE with a simplified geometry model. Comparisons between the experimental data and the CFD simulations showed some discrepancies in the pressure drop and heat transfer results, which may be caused by the use of different thermal boundary conditions in the simulations from those in the experiments. The simplified heat exchanger simulation model was divided into eight segments to identify the thermal boundary conditions for the zigzag-channel PCHE. The temperature and heat flux distributions along the fluid flow direction in the heat exchanger for each segment were obtained. It was observed that the temperatures were not constant along the azimuthal direction of a cross section of the flow channel and the helium temperature distribution for each segment presented a wavy shape. However, the global helium temperature distribution along the entire flow channel was approximately linear. For the heat flux distributions, although they were significantly different at different segments, the trend for the heat flux for each segment along the fluid flow direction was similar.