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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
P.A. Bagryansky, A.A. Lizunov, A.A. Zuev, E. Yu. Kolesnikov, A.L. Solomachin
Fusion Science and Technology | Volume 43 | Number 1 | January 2003 | Pages 152-156
Transport and Confinement | doi.org/10.13182/FST03-A11963583
Articles are hosted by Taylor and Francis Online.
Influence of the radial electric field on the MHD-stability was studied in the GDT using a set of biased end plates and limiters that provided a possibility to control radial profile of the plasma potential. It was shown that biasing of the limiters or peripheral end plate section to a potential of 250 - 300 V leads to considerable increase of the energy confinement time due to reduction of the electric field in the plasma volume. MHD-stability of the plasma was observed in this regime with the remote anchors not energized. The possible stabilization mechanism associated with radial electric field is discussed.