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The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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ANS Student Conference 2025
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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.
Haico V. Kok, Tim H. J. J. van der Hagen
Nuclear Technology | Volume 127 | Number 1 | July 1999 | Pages 38-48
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2982
Articles are hosted by Taylor and Francis Online.
A model is developed that enables the determination of steady-state values of all system variables of the boiling water reactor simulator loop DESIRE. The model calculates natural-circulation mass flow rate, subcooling, carry-under, and feedwater flow rate from the three independent variables: power, feedwater temperature, and the setting of a controllable friction valve. The void fraction in the assembly is calculated using the drift-flux model with Dix's correlation. A submodel for the calculation of carry-under is derived on the basis of measurements. Comparison of the model with measurements shows an excellent agreement over a wide range of operating conditions.