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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
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.
Bernd K. Buchheim, Hans Bunschi, and, Franz J. Hoop, James Fitzpatrick
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 444-449
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33167
Articles are hosted by Taylor and Francis Online.
One of the methods currently under consideration for the disposal of radioactive wastes is emplacement in a repository within deep, continental formations. A licensing requirement for such a facility will presumably be some form of safety analysis report on the radiological impact of the facility. A methodology has been developed to make an assessment of the radiological consequences both for normal operation and for possible accident situations for a specific repository design in a salt dome at Gorleben in Germany, a repository which has been designed to accommodate all categories of radioactive waste (low, intermediate, and high level). Radionuclide release scenarios were derived from a systematic analysis of the facility design and proposed operational procedure. Where necessary, simple numerical models for such topics as direct radiation exposure from waste containers, release and transport of radionuclides, radiolysis, heat transfer, creep, and impact were developed to give a first estimate of the radiological consequences due to radionuclide releases. The results enabled sensitive areas of the design and the operational procedure to be identified, and thus possible modifications and/or precautionary measures could be recommended. The results also gave an indication of those parts of the analysis requiring more sophisticated and specialized modeling techniques to yield a more detailed radiological consequence analysis in preparation for a safety analysis report.