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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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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November 2021
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August 2021
Latest News
ANS Winter Meeting: What it will take to “Fuel our Nuclear Future"
The 2021 ANS Winter Meeting and Technology Expo began this morning with a Opening Plenary Session chaired by Winter Meeting general chair Amir Vexler, president and chief executive officer of Orano USA. It was an opportunity to both celebrate achievements that are already building a “Nuclear Future” and to identify needs and challenges ahead.
Influential speakers from the U.S. Congress, the Department of Energy, and the Nuclear Energy Institute joined ANS president Steven Nesbit and ANS CEO/executive director Craig Piercy to explore key issues associated with the front end of the nuclear fuel cycle, including supply and demand for high-assay, low-enriched uranium (HALEU). They didn’t stop there, however. They took questions from an in-person and virtual audience that probed other requirements of a sustainable nuclear future, including fueling a human resources pipeline.
Rui Hu
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 313-322
Technical Paper | Thermal Hydraulics | dx.doi.org/10.13182/NT14-78
Articles are hosted by Taylor and Francis Online.
This paper provides an overview of a new one-dimensional finite element flow model for incompressible but thermally expandable flow. The flow model was developed for use in system analysis tools for whole-plant safety analysis of sodium fast reactors. Although the pressure-based formulation was implemented, the use of integral equations in the conservative form ensured the conservation laws of the fluid. A stabilization scheme based on streamline-upwind/Petrov-Galerkin and pressure-stabilizing/Petrov-Galerkin formulations is also introduced. The flow model and its implementation have been verified by many test problems, including density wave propagation, steep gradient problems, discharging between tanks, and the conjugate heat transfer in a heat exchanger.
