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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear Science and Engineering
November 2024
Nuclear Technology
October 2024
Fusion Science and Technology
Latest News
Report touts lessons from era of nuclear waste negotiator
As the Department of Energy embarks on its consent-based process for siting a geologic repository for spent nuclear fuel and high-level radioactive waste, a new report from the Center on Global Energy Policy at Columbia University SIPA highlights relevant lessons from the federal government’s now defunct Office of the Nuclear Waste Negotiator.
Established under Title IV of the Nuclear Waste Policy Act, the office, an independent agency within the executive branch, was primarily active from 1990 to 1995. Its role was to engage with state and tribal governments to find an acceptable and suitable host site for a repository.
The full report, Lessons from the Nuclear Waste Negotiator Era of the 1990s for Today’s Consent-Based Siting Efforts, is now available online. Its executive summary is available here.
Emilio Baglietto, Etienne Demarly, Ravikishore Kommajosyula, Nazar Lubchenko, Ben Magolan, Rosie Sugrue
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 1-22
Technical Paper | doi.org/10.1080/00295450.2018.1517528
Articles are hosted by Taylor and Francis Online.
Building on the strong belief that the advancement and consistent adoption of cutting-edge simulation tools is critical to the future of nuclear power, three-dimensional thermal-hydraulic methods in the form of computational fluid dynamics (CFD) have made enormous advancement and promise to transform the way we approach the design of more efficient and reliable systems. The success of these methods hinges on the accuracy and predictive ability of the underlying models, which must, at the same time, limit the computational cost and allow optimal scalability. A large effort at the Massachusetts Institute of Technology has been devoted to the development of a second-generation of multiphase-CFD (M-CFD) closures and to leveraging the continuous progression in the experimental techniques. Among the numerous objectives, the central challenge that has driven the overall approach is the prediction of departure from nucleate boiling. This work focuses on deriving the fundamental meso-scale mechanisms from the CFD-grade experiments and incorporates them in the M-CFD framework as subgrid-scale models. A more complete representation of lateral lift force and near-wall effects are proposed, in combination with direct numerical simulation–driven understanding of bubble-induced turbulence effects. The improved description of the multiphase flow distribution is coupled to a novel representation of boiling heat transfer, which aims at introducing all the physical mechanisms that are encountered at the boiling surface. Starting from the improved representation at the wall, this work concentrates on the micro-hydrodynamics of the thin liquid film on the heated surface, which governs the critical heat flux limit.