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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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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February 2022
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Fusion Science and Technology
January 2022
Latest News
Advanced reactors: Now comes the hard part
Designing a reactor is complicated but building one may be harder. Even companies that have had lots of practice haven’t always done it well. And all the power reactors in service today were built by companies that had years of experience in other kinds of big steam-electric power plants. In contrast, some of the creative new designs now moving toward commercialization come from start-ups that have never built anything at all. How should they prepare?
T. Asai et al. (19P61)
Fusion Science and Technology | Volume 51 | Number 2 | February 2007 | Pages 379-381
Technical Paper | Open Magnetic Systems for Plasma Confinement | dx.doi.org/10.13182/FST07-A1408
Articles are hosted by Taylor and Francis Online.
The magnetic configuration of a field-reversed configuration (FRC) has a center closed region and open field region. Because of this geometrical property, an FRC can be translated from a formation theta-pinch region into a confinement region while it keeps the closed magnetic field. In this work, the "equivalent" neutral beam injection (NBI) in the translation process has been proposed as a heating and particle injection method for an FRC. Translating an FRC plasma through neutral gas background is equivalent to an end-on NBI into the FRC. For the neutral particle density of 1 × 1020m-3, translation velocity of 100km/s and translation length of 1m, the number of particles ~3 × 1018 and the kinetic energy of ~40J are supplied due to the equivalent NBI.
