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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
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.
V. K. Sikka, J. Moteff
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 52-65
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16274
Articles are hosted by Taylor and Francis Online.
The thermal stability of neutron-induced defects in molybdenum irradiated in Experimental Breeder Reactor II (EBR-II) to a fast-neutron fluence of ∼1 × 1022 n/cm2 (E >1 MeV) clearly suggests that there are critical temperature regimes that should be avoided by reactor design engineers. These regions are manifested by a rapid change in the micro structure within a small temperature interval, a circumstance that can significantly influence the strength and corresponding ductility of the material. One critical temperature occurs at ∼800°C, where the irradiation-induced modulus-corrected strength could vary significantly compared to unirradiated molybdenum for a small temperature variation around 800°C. Voids have been shown to occur in specimens irradiated at 430, 580, 700, 800, 900, and 1000°C; these voids are stable at temperatures up to ∼0.60 Tm , rather than the 0.55 Tm value reported earlier for low fluence irradiations. The increase in the complete void removal temperature is suggested to exist due to the presence of a larger void size and the ordered void lattice structure in EBR-II samples.