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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Sandor Benedek
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 201-215
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34923
Articles are hosted by Taylor and Francis Online.
General scaling laws for transient two-fluid flow heated by a rod are presented. The similarity of these processes can be ensured only by applying the same volume and time scale with identical model parameters. In practice, the requirement of similar interfacial friction terms cannot be fulfilled because of volume (diameter) reducing scale. Numerical examples show remarkable deviations between the state variables (the values of slip) of the prototype and those of the scaled model, especially with unsteady flow rates. The deviation becomes significant when the slip of phase velocities exceeds the range of 1.6 to 1.8. Volume and time scaling can be carried out only if the phase velocities are similar (slip equal to ∼1 in the quasi-homogeneous flow model). Maintenance of the similarity of heat transfer processes of a heated fuel rod may necessitate time scaling. Furthermore, numerical examples are presented for a scale model of a prototype pressurized water reactor, employing the time-scaled homogeneous flow model.
