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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
Ronald D. Boyd, Sr., Aaron M. May
Fusion Science and Technology | Volume 57 | Number 2 | February 2010 | Pages 129-141
Technical Paper | doi.org/10.13182/FST10-A9367
Articles are hosted by Taylor and Francis Online.
High-heat-flux (HHF) removal (HHFR) limits can be formidable technological barriers that prevent or limit the normal implementation or optimization of new and novel devices or processes. A conjugate heat transfer HHFR simulation methodology has been developed with excellent resulting accuracy (>98.0% accurate) for predicting HHF amplification (peaking factors) and the peak flow channel inside wall temperature. The methodology can be used directly or expanded to a correlation form. Although the simulation utilized axial and swirl water flows with single-phase fully developed turbulent and subcooled flow boiling in a single-side-heated circular inside flow channel with a rectangular outer boundary, the methodology appears to be fluid- and flow regime-independent (e.g., applicable to developing or jet impingement flows) so that other fluids (e.g., gases, dielectric liquids, liquid metals) and flow regimes can be employed possibly for HHFR applications requiring specialized fluids and/or flow conditions. However, more work is required to validate the applicability of this methodology (and the correlation) to other fluids, flow regimes, and channel materials. Further, the approach can be expanded possibly to include applications employing a hypervapotron for HHFR. For the prototypic simulation cases (38.0 MW/m2) considered, the circumferential inside flow channel heat transfer coefficient distribution [h([varphi])] was not known a priori, so, h([varphi]) was determined from the unknown local inside wall heat flux via iterative finite element conjugate heat transfer analyses for flow regimes ranging from fully developed turbulent subcooled flow boiling (at the top of the flow channel) to single-phase turbulent flow (at the bottom of the flow channel).