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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
S. Imagawa, A. Sagara, H. Yamada, N. Nakajima, A. Komori, O. Motojima, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 593-598
Chapter 13. Prospects for Fusion Reactor | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10847
Articles are hosted by Taylor and Francis Online.
Heliotron reactors have several features suitable for a fusion power plant, such as no need for current drive, no plasma current disruptions, suitability for steady-state operation, and a wide space between helical coils useful for maintenance of in-vessel components. According to recent reactor studies based on the experimental results in the Large Helical Device (LHD), the plasma major radius of a heliotron reactor is set to 14 to 16 m in order to install shielding and breeding blankets with total thickness of 1 m. The central toroidal field for the self-ignition is 5 to 6 T under the assumption that the confinement enhancement factor is 1.2 to 1.4 with respect to the LHD. The stored magnetic energy is estimated to be 120 to 150 GJ. Both the major radius and the magnetic energy are three times larger than those of ITER. Its large helical windings, however, can be realized by steady extension from the ITER technology, because cable-in-conduit conductors similar to those for ITER toroidal field coils can be adopted. Improvement of plasma confinement is essential to reduce the number of magnet systems. A roadmap to a heliotron DEMO is discussed.