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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.
L. Z. Liang, J. L. Wei, S. Liu, Y. H. Xie, C. C. Jiang, W. Liu, J. J. Pan, Y. J. Xu, Z. M. Liu, Y. L. Xie, C. D. Hu, Y. Z. Zhao
Fusion Science and Technology | Volume 75 | Number 2 | February 2019 | Pages 160-165
Technical Note | doi.org/10.1080/15361055.2018.1533619
Articles are hosted by Taylor and Francis Online.
In order to meet experimental requirements on high parameter plasma research, the injected power of the counter injector is expected to increase at a fixed beam energy of 50 keV for deuterium neutral beam. Three candidate schemes are compared to assess the possibilities of raising the injected power. Considering safety and economic factors, raising the electric field in the first gap is employed by adjusting the voltage gradient on the accelerator. The experiments show that the optimum perveance is increased from 2.2 to 2.7 μP by changing of gradient grid voltage from 0.84 to 0.78 Vacc. The ion beam power is promoted by about 50% at 3.0 μP, but beam transmission efficiency decreased to 60% at 3.0 μP. Thus, the injected power is boosted about 25%.