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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Brent J. Lewis, Anne C. Harnden-Gillis, Leslie G. I. Bennett
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 366-380
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34937
Articles are hosted by Taylor and Francis Online.
Increasing, but still low, radiation fields due to a release of fission products have been observed in the light-water-filled reactor container of SLOWPOKE-2 reactors fueled with a highly enriched uranium alloy. To investigate this phenomenon, samples of water coolant and headspace gas from the reactor container have been examined by gamma spectroscopy methods for several reactors with various burnup. A model has been developed to describe the kinetic behavior of the activity concentrations of the short-lived iodine and noble gas species in the reactor container water, and the noble gas concentrations in the reactor container headspace. The most likely source of the fission product release is an area of uranium-bearing material exposed to the coolant at the end weld line of the fuel elements that originated at the time of fuel fabrication. The fission product release analysis is consistent with observations from an underwater visual examination of a high-burnup core and a metallographic examination of archived fuel elements.