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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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.
Won Il Ko, Jong Won Choi, Jae Sol Lee, Hyun Soo Park, Kun Jai Lee
Nuclear Technology | Volume 127 | Number 1 | July 1999 | Pages 123-140
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT99-A2989
Articles are hosted by Taylor and Francis Online.
A simulation technique has been applied for evaluation of the Direct Use of Pressurized water reactor (PWR) spent fuel In Canada deuterium uranium (CANDU) reactors (DUPIC) fuel-cycle cost incorporating uncertainty terms that have often been a controversial factor in economic analyses. With a view to look at actual scenarios, the present and future Korean nuclear grids with both PWRs and CANDUs were assumed. The resulting values were compared with such conventional options as reprocessing with mixed-oxide fuel to recycle, as well as direct disposal. The results of the probabilistic analysis indicate that the DUPIC fuel cycle could be an option competitive with direct disposal and superior to the reprocessing option. The cost difference between direct disposal and DUPIC options, although dependent on assumed scenarios of nuclear grids, was very small.