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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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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.
Y-K. M. Peng, D. J. Strickler, S. K. Borowski, W. R. Hamilton, R. L. Reid, (ORNL), J. R. Haines, V. D. Lee, (MDAC), G. E. Gorker, S. S. Kalsi, B. W. Riemer, E. C. Selcow, (GAC), G. R. Dalton, (U. of Florida), G. T. Bussell, (S&W), J. B. Miller, (U. of Tennessee)
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 338-343
Power Reactor and Next-Generation Studies | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40067
Articles are hosted by Taylor and Francis Online.
Initial assessments of ignition devices based on the spherical torus concept1 suggest that an ignition spherical torus (IST) can be highly cost-effective and exceptionally small in unit size. Assuming advanced methods of current drive and confinement and beta scalings with plasma current, a D-T IST with a toroidal field of 2 to 3 T is estimated to have a major radius ranging from 1 m to 1.6 m, and a fusion power less than 60 MW. For the nominal IST (at 2 T and 1.6 m), the direct cost of the nuclear island is estimated to be about $120 M with a total direct cost about $340 M in mid-1984 dollars based on the Fusion Engineering Design Center (FEDC) cost algorithm2. For ISTs with higher field and smaller size (e.g., at 3 T and 1 m), further reductions of the cost of the nuclear island are estimated. In case of confinement scaling with the plasma size only, strong plasma paramagnetism (self-generated magnetic field) in the spherical torus may still serve to compensate for the projected confinement shortfall. Because of the modest field strength, only conventional engineering approaches are needed in the IST concepts, leading to dramatic engineering simplifications in comparison with the conventional high-field ignition designs3. A free-standing TF coil/vacuum vessel structure is assessed to be feasible and relatively independent of the shield structure and poloidal field coils. The direct cost of this “stand-alone” torus of the nominal IST is estimated to be $70 M. These highly attractive projections of the IST result directly from a combination of the possible exceptional features of the spherical torus plasma4: high beta, low beta poloidal, naturally large elongation, high plasma current, strong paramagnetism, and tokamak-like confinement, which also place the spherical torus in a plasma regime distinct from tokamaks of conventional aspect ratios. Experimental testing of the viability of the spherical torus concept is suggested.