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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Hisae Togashi, Kazuhisa Yuki, Hidetoshi Hashizume
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 740-745
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | doi.org/10.13182/FST05-A774
Articles are hosted by Taylor and Francis Online.
In a fusion reactor, almost 30% of fusion energy is deposited on plasma facing components. In the divertor region, it is, however, difficult to utilize this energy with conventional cooling techniques based on high velocity flow with highly subcooled cooling. From this viewpoint, the authors have been developing a cooling technique with metal porous media. In this study, in order to attain both the higher cooling performance and the acquisition of high density energy, high heat removal experiments are performed by using homogeneous and functionally graded porous media to estimate their fundamental heat transfer performances. From the experiments with the homogeneous porous media, it is clarified that the cooling performance is not always improved by using finer pore size media. The functionally graded porous media can reduce a pressure loss. Additionally, in case of the functionally graded porous media with the finer pore, the heat transfer coefficient is higher than that obtained in the homogeneous case. As for the optimal design, it is important to consider the degree of vapor development near a heated surface in the porous media and an effective discharge of vapor from the heated region.