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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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.
Timothy Ironman, James Tulenko, Ghatu Subhash
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 144-158
Technical Paper | doi.org/10.1080/00295450.2017.1360714
Articles are hosted by Taylor and Francis Online.
The viability of spark plasma sintering (SPS) for fabrication of industrial-grade nuclear fuel pellets is explored by utilizing die designs for single- and multiple-pellet manufacturing. Traditional UO2 pellets were also manufactured by systematically varying processing temperature and pressure as needed for single- and multiple-pellet fabrication. The pellets were then qualified against commercial fuel specifications for density, shape, microstructure, and surface flaws. Pellets produced one at a time met all commercial specifications except for grain size. Pellets produced in batches of two, four, and eight pellets showed suboptimal density indicating that further changes to sintering conditions are warranted. Additionally, commonly used graphite tooling for pellet fabrication was shown to be ineffective in producing large numbers of fuel pellets, as the die and punches were shown to undergo severe wear in each run thus decreasing the reliability of the tooling for production of pellets as per the specification. Finally, additional discussion is provided for identifying the avenues for scale-up of SPS to meet the current commercial demand of 400 million pellets/year. These studies are viewed as first step toward assessing the ability of SPS technology to meet the quality specifications and quantity demands of nuclear fuel pellets.