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IAEA, PNNL test new uranium enrichment monitor
A uranium enrichment monitor developed by a team at Pacific Northwest National Laboratory will soon be undergoing testing for nonproliferation applications at the International Atomic Energy Agency Centre of Excellence for Safeguards and Non-Proliferation in the United Kingdom. A recent PNNL news article describes how the research team, led by nuclear physicist James Ely, who works within the lab’s National Security Directorate, developed the UF6 gas enrichment sensor (UGES) prototype for treaty verification and other purposes.
Alicia M. Raftery, Rachel L. Seibert, Daniel R. Brown, Michael P. Trammell, Andrew T. Nelson, Kurt A. Terrani
Nuclear Technology | Volume 207 | Number 6 | June 2021 | Pages 815-824
Technical Paper | doi.org/10.1080/00295450.2020.1823187
Articles are hosted by Taylor and Francis Online.
Ceramic-metallic nuclear fuels are a candidate fuel for nuclear thermal propulsion systems due to their high heat transport properties, which are necessary in very high-temperature environments. The conventional fabrication of uranium nitride–molybdenum fuel has been thoroughly studied in the past, but modern manufacturing techniques have presented a unique opportunity for further development within this field. This work demonstrates the use of advanced manufacturing techniques to produce nuclear fuel pellets composed of uranium nitride microspheres encased in a molybdenum matrix. Binder jetting is used to print molybdenum disks that are filled with uranium nitride microspheres and afterward sintered using spark plasma sintering. Two fuel pellets were fabricated to demonstrate the methodology and to provide a baseline analysis of the effects of temperature and pressure processing conditions. Characterization of the sintered fuel pellets includes detailed microstructural analysis and thermal conductivity measurements.