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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.
Bernard L. Cohen
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 63-69
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32448
Articles are hosted by Taylor and Francis Online.
The several water intrusion scenario studies in the recent literature are all quite similar and may be easily understood if used to estimate the total number of eventual cancers per unit of energy generated, including their sensitivity to input parameters. However, these studies are grossly overpessimistic in several aspects of the problem, especially in using leach rate data from highly unrealistic experimental situations, and in ignoring geochemical considerations in both leaching and in transport. It is concluded that it is reasonable to expect removal and transport for an atom of buried waste to be similar to that for an atom of average rock. Under that assumption, the leach rate can be estimated from the chemical compositions of rock and of groundwater, coupled with the water flow through aquifers. The result (excluding 238U) is 0.0008 eventual cancer/GW(electric)-yr. This treatment would be invalidated if the waste were released through fractures in the rock induced by the emplacement operations or by heat. If such fractures cannot be discounted, total reliance must be on leach resistance.