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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.
Alan P. Main, Bryce L. Shriver
Nuclear Technology | Volume 59 | Number 3 | December 1982 | Pages 456-462
Technical PaperTechnical Paper | The Backfill as an Engineered Barrier for Radioactive Waste Management / Material | doi.org/10.13182/NT82-A33003
Articles are hosted by Taylor and Francis Online.
A model for predicting the annealing response of A553-B weld materials has been developed. This model assumes that the irradiation-induced shifts in the nil ductility transition temperature (ΔNDTT) and Charpy upper shelf energy (ΔUSE) are a result of the introduction of three types of defects into the alloy. The recovery of ΔNDTT and ΔUSE depends on the concentration of each defect remaining after the annealing treatment. The three defect types, including their diffusion constants, are assumed to be the same for all A533-B welds. However, the contribution of each defect type to ΔNDTT and ΔUSE depends on the chemical composition of the material and possibly the neutron fluence. Copper, nickel, manganese, and chromium were found to correlate with ΔNDTT, while sulfur and phosphorus appeared to correlate with ΔUSE. Once the relative contribution of each defect type is known, the recovery of ΔNDTT and ΔUSE is predicted based on diffusion calculations. Both the annealing temperature and time are accounted for in the calculations. The final model was compared with experimental data on three materials tested by Westinghouse Electric Corporation and two materials tested by the Naval Research Laboratory. The model accurately predicted the recovery of ΔNDTT for all five materials annealed at 343°C (650°F) to 454°C (850°F) for 24 to 336 h. The predicted recovery of ΔUSE was not as accurate as that of ΔNDTT.