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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 Technology
Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
Boyce W. Travis, Mohamed S. El-Genk
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 161-166
Fission | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13414
Articles are hosted by Taylor and Francis Online.
This paper presents the results of a coupled 3-D thermal-hydraulics and CFD analysis of helium flow in a coolant channel of a prismatic core, Very High Temperature Reactor (VHTR). Results are used to develop a turbulent convection heat transfer correlation that accounts for induced mixing in the entrance region as:h = [0.10(k/D)Reb0.653Prb0.4][1 + 0.57e-(0.20z/D)]The entrance effect (second term) increases the local turbulent heat transfer coefficient, but diminishes for z/D > 25. This correlation is within ± 2% of the numerical results.