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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.
Seon Jeong Huh (Kookmin Uniy), Joo Hyung Moon, Youngmin Bae, Young In Kim (KAERI), Hee Joon Lee (Kookmin Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 844-848
Local condensation heat transfer coefficient inside a circular vertical tube was experimentally measured for the design purpose of an air-cooled shell and tube heat exchanger in long term passive cooling system. An experiment was conducted in a 1/2500-volume scaleddown model of the emergency cooldown tank (ECT) of the system integrated modular advanced reactor (SMART). While saturated vapor downstream (Ref < 30) flows in the shell side, air natural upstream flows in the tube side. The inner diameter and length of the tube were 261.4 mm and 1.8 m. The outer diameter of the shell was 318.5 mm. Eleven thermocouples were installed at 150 mm apart alongside the outer wall of SUS plate, a thickness of 3 mm, between vapor and air streams. During a performance evaluation of the shell and tube heat exchanger, the heat loss from the emergency cooldown tank was approximately 30% of the total heat load from 1.2 to 1.4 kW. Local condensation heat transfer coefficients were reduced by the Nusselt equation with ranging the quality from 1 to 0. With the range of mass flux from 0.1 to 0.2 kg/m2/s, condensation heat transfer coefficients were distributed at 110 ~ 350 W/m2/K. The experimental data was compared to the existing condensation heat transfer correlations. Among those, Shah correlation gave the best prediction of current experimental data with 54% average error. To increase the accuracy, new correlation is proposed based on the Dittus-Boelter equation and local quality in this study. New proposed correlation predicts current experimental data with 10% average error.