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Operations & Power
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.
Kozo Katsuyama, Koji Maeda, Tsuyoshi Nagamine, Hirotaka Furuya
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 73-80
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT10-A9344
Articles are hosted by Taylor and Francis Online.
Three-dimensional X-ray computer tomography (CT) images were successfully taken of a fast breeder reactor fuel assembly that had been irradiated to high burnup. The interior and outside of the fuel assembly can be clearly observed on any cross section from any angle. These images make it possible to analyze deformations and microstructural changes in the fuel pins and abnormalities in the fuel assembly. An analysis was made for 127 central voids, i.e., one in each fuel pin of the traverse cross section, and the void sizes were tentatively related to the linear heat rating. Compared with conventional nondestructive and destructive postirradiation examinations (PIEs), this X-ray CT technique has great advantages including acquiring large numbers of PIE data in a short time, reducing PIE costs, reducing the amounts of radioactive waste generation, and physically protecting nuclear materials.
