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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.
H. Carlsen, D. N. Sah
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 587-593
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32803
Articles are hosted by Taylor and Francis Online.
The distribution of 239Pu formed in uranium dioxide during irradiation is nonuniform and changes with burnup. This implicates a burnup effect on the fuel temperature distribution. The total 239Pu concentration during irradiation and its radial distribution at end-of-life has been calculated in low-enriched UO2 fuel pellets. The processes considered are 239Pu buildup by capture of thermal and resonance neutrons and 239Pu loss by thermal fissions and neutron capture. The calculated total 239Pu content is verified by chemical analysis, and the calculated 239Pu profile by comparison with results from quantitative alpha autoradiography for two fuel specimens. The effect of a nonuniform radial 239Pu distribution on the fuel temperature profile is evaluated. At a burnup level of 3560 GJ/kg U and a linear heat rating of 50 kW/m, the centerline temperature is calculated to be 245 K lower than that calculated on the assumption that the 239Pu is distributed uniformly.
