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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.
