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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
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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Contractor selected for Belgian LLW/ILW facility
Brussels-based construction group Besix announced that is has been chosen by the Belgian agency for radioactive waste management ONDRAF/NIRAS for construction of the country’s surface disposal facility for low- and intermediate-level short-lived nuclear waste in Dessel.
Marie-Louise Pointud, Pierre Chenebault
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 494-500
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31909
Articles are hosted by Taylor and Francis Online.
Radioactive fission gas release from coated particles containing UO2 or (Th-U)O2 fuel kernels was studied by taking into account the following parameters: (a) porosities of kernels and materials surrounding them, (b) irradiation temperature, (c) burrnup, and (d) thermal neutron flux. The main results follow. First, the structure of the kernels is modified during irradiation and, consequently, the mechanism and rate of fission gas release vary. Second, for a dense fuel, released activity results from recoil species ejected by the external surface of the kernel and reemitted from the surrounding porous carbon. Finally, for an initially porous fuel or for a heavily irradiated dense fuel, recoil atoms reemitted from the internal open porosity of the kernel and atoms ejected by knockout give the most important contributions to the release.