ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
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.
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.
Harry M. Ferrari
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 503-512
Technical Paper | doi.org/10.13182/NSE63-A18440
Articles are hosted by Taylor and Francis Online.
The mechanism and kinetics of nitrogen release from UO2 pellets containing high nitrogen impurities have been investigated at elevated temperatures. A combination of metallographic and x-ray analyses showed that nitrogen present in the UO2 exists as a second phase in the form of uranium nitrides. The kinetics of nitrogen release were measured at temperatures of 1000, 1200, 1400, and 1600°C and the mechanism of release was determined to be controlled by the diffusion of nitrogen through the UO2 lattice. The variation in nitrogen pressure upon heating a UO2 fuel element to elevated temperatures was studied. The data showed that a reversible equilibrium pressure-temperature relationship did not exist between the nitrides in the UO2 and the nitrogen gas above it as occurs with pure uranium nitrides. The quantity of nitrogen which will be released in a UO2 fuel element is determined by the kinetics of diffusion of nitrogen through the UO2 lattice and may be computed for any given fuel element design utilizing a diffusion model similar to one used for computing release of fission gases.