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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
J. E. Bodine, I. J. Groce, J. Guon, L. A. Hanson
Nuclear Science and Engineering | Volume 19 | Number 1 | May 1964 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE64-A19784
Articles are hosted by Taylor and Francis Online.
The oxidative decladding of UO2 fuels has been demonstrated on three-foot sections of unirradiated fuel rods and on eight-inch sections of fuel rods irradiated to 21,000 MWd/MTU. Decladding rates were unaffected by the extent of irradiation. Uranium dioxide which was unirradiated, irradiated, and with fissia added to simulate 100,000 MWd/MTU irradiation was declad at similar rates. The effect of pressure and temperature on decladding rates was determined. Puncturing the cladding greatly enhanced the rate and gave a coarser product. This product was not completely converted to U3O8 during oxidative decladding. Greater than 99.9% of the UO2 fuel was removed from the cladding. There was no detectable contamination of the product by the cladding material. Little or no fission-product or plutonium decontamination was observed. Dissolution rates for the declad product, in 50% nitric acid, were 20 times as fast as for the “as received” UO2 fuel.
