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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Annual Conference opening plenary: Full speed ahead
The 2024 American Nuclear Society Annual Conference opened with a bang yesterday as 1,200 attendees gathered in Las Vegas to network, collaborate, and socialize. Honors and awards were presented to several recipients, and ANS welcomed twelve new Fellows.
The plenary opened with an address from ANS Executive Director/Chief Executive Officer Craig Piercy that brought this year’s theme to the fore straight away: The time is now to deploy new nuclear projects—and not acting at this moment is simply not an option.
Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 49-61
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3578
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic performance of a nuclear reactor fuel assembly grid spacer is predicted using computational fluid dynamics. The modeled flow domain exploits the periodicity of the spacer and is separated into a bare bundle and grid region to maintain a manageable model size. An iterative process is used to couple the segregated flow domains to arrive at a converged solution. The grid spacer is a 7 × 7 mixing vane grid representative of an actual pressurized water reactor grid. Pressure drop and rod wall temperature predictions for steady-state operation are computed. The results show excellent agreement with experimental data. The agreement in these results demonstrates the usefulness of the method presented as a design tool for nuclear fuel manufacturers and as a prediction tool for off-design operating conditions such as simulated accident scenarios.