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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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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.
Neil B. Morley, Mark S. Tillack, Mohamed A. Abdou
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1765-1771
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29598
Articles are hosted by Taylor and Francis Online.
In an effort to prolong the lifetime of impurity control components, the idea of protecting the contact surface from erosion and radiation damage with a thin film of liquid metal has been advanced. This flowing, liquid metal film could also be used to remove the high heat fluxes incident on limiter or divertor surfaces, thus eliminating problems with thermal stresses in the components as well. In order to determine the attractiveness and feasibility of such a concept, the heat transfer characteristics of a thin film of liquid metal are examined when the film is exposed to a large, one-sided heat flux incident on the free surface. The method developed yields the temperature at any location in the film and is used to determine, for a given design and space-dependant heat flux, the film velocity required to keep the maximum film temperature below whatever Tmax limit is imposed. In addition, the behavior of the film flow at the required velocity is examined in order to determine if such a flow is possible. This analysis is accomplished by using a one-dimensional model of the film height, developed from the basic set of MHD equations, to show the design conditions that allow for a stable film. The analytical method is applied to ITER-type limiter and divertor configurations, resulting in required film velocities (v < 5 m/s for the cases examined) and allowable values of the design parameters (channel size, wall conductivity, and substrate angle) that yield a stable film, capable of removing all incident heat.