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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.