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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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 Science and Engineering
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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.
K. Ezato, M. Dairaku, M. Taniguchi, K. Sato, S. Suzuki, M. Akiba, C. Ibbott, R. Tivey
Fusion Science and Technology | Volume 46 | Number 4 | December 2004 | Pages 521-529
Technical Paper | doi.org/10.13182/FST04-A587
Articles are hosted by Taylor and Francis Online.
Thermal-hydraulic tests for pressurized water in an annular tube with a twist fin have been performed to examine its applicability to high-heat-flux components of the International Thermonuclear Experimental Reactor (ITER) divertor. The annular swirl tube consists of two concentric tubes: an outer smooth tube and an inner tube with an external twist fin to enhance heat transfer of the cooling water in the annulus section between the outer and the inner tubes. Critical heat flux (CHF) tests under one-sided-heating conditions show that the annular swirl tube has as high removal limitation as the conventional swirl tube, the dimensions of which are similar to those of the outer tube of the annular swirl tube. A minimum axial velocity of 7.1 m/s is required for 28 MW/m2, the ITER design value. Pressure drops in the annulus section and the end return have been measured. The applicability of the existing correlations for heat transfer and CHF to the annular swirl tube has also been examined.
