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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
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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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Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
K. A. Werley, C. G. Bathke, R. A. Krakowski, R. L. Miller, J. N. DiMarco
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1266-1271
Result of Large Experiment and Plasma Engineering | doi.org/10.13182/FST91-A29515
Articles are hosted by Taylor and Francis Online.
Essential to the achievement of economically compact fusion power cores is the radiation of a large fraction of the plasma heating power uniformly to the first wall, thereby assuring adequate longevity of the divertor impurity control system. The radiation of significant fractions of the heating power from the beta-limited core-plasma region in an RFP, however, requires a corresponding increase in the quality of (non-radiative) confinement. It is shown that radiating ≳ 70% of the total heating power from the core plasma of the TITAN compact reversed-field-pinch (RFP) reactor is possible with non-radiative confinement times that are a large factor (> 15) below classical confinement predictions and are within the present scaling relation based upon extrapolations of the existing RFP transport database. By comparison, the confinement in the ARIES-I tokamak reactor is within a factor of 2 of neo-classical predictions.