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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.
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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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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.
Ken-ichi Hattori, Yoichi Hirano, Yasuyuki Yagi, Toshio Shimada, Kiyoshi Hayase
Fusion Science and Technology | Volume 28 | Number 4 | November 1995 | Pages 1619-1633
Technical Paper | Plasma Engineering | doi.org/10.13182/FST95-A30429
Articles are hosted by Taylor and Francis Online.
Zero-dimensional power balance is analyzed, and an operation boundary is deduced in a “beam-assisted reversed-field pinch”; the latter utilizes partial poloidal current drive by neutral beams so that transport losses arising from magnetohydrodynamics (MHD)-dynamo, i.e., tearing mode instability are reduced. Changes of power flow and heat conductivity due to a beam driven current are treated by considering an MHD-dynamo-based power balance model that assumes linear dependence of magnetic fluctuation level on the externally driven current. It is shown that a ratio of a beam driven current to a dynamo current must not exceed ∼40% regarding a beta-limit in the next generation of plasma experiments (minor radius/major radius = 0.6m/1.8 m, plasma current = 1 MA, poloidal beta = 0.1). At that point, the energy confinement time is predicted to increase by a multiple or so of that estimated from the MHD dynamo model without a current drive.