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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.
L. H. Johnson, K. I. Burns, H. H. Joling, C. J. Moore
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 470-475
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33273
Articles are hosted by Taylor and Francis Online.
The relationship between the quantity of iodine and cesium present in the fuel-sheath gap region and the amount of stable fission gas released from the fuel matrix has been investigated for typical natural UO2 Canada deuterium uranium power reactor fuels. Two leaching techniques were employed to determine the fuel-sheath gap inventories of cesium and iodine, and their respective release fractions were derived from these. The I37Cs/Xe and 134Cs/Xe release ratios were close to one over nearly three orders of magnitude of release fraction. Limited data suggest that 129I may show similar behavior. The experiments were performed in support of the safety assessment of irradiated fuel disposal and may have further application to fuel storage and reactor safety studies.
