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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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.
Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 13-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3715
Articles are hosted by Taylor and Francis Online.
This paper addresses the pool boiling critical heat flux (CHF) phenomena in one-dimensional inclined rectangular channels by changing the orientation of a copper test heater assembly. In a pool of saturated water at atmospheric pressure, an account is taken of the gap sizes of 1, 2, 5, and 10 mm and the surface orientation angles from the downward-facing position (180 deg) to the vertical position (90 deg). Tests are conducted on the basis of the visualization of boiling phenomena utilizing a high-speed digital camera. In addition, an engineering correlation relating to the CHF near the vertical position is developed anchored in the experimental results. It is observed that the CHF generally decreases as the surface inclination angle increases and as the gap size decreases. In the downward-facing position (180 deg), on the other hand, the vapor escape and liquid refill are accelerated by the squeezing gap so that the CHF tends to increase as the gap size decreases. It is also found that there exists a transition angle, around which the CHF changes with a rapid slope on account of the CHF triggering mechanism differing with the inclination angle.