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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Recent surveys confirm high levels of U.S. nuclear support
Surveys have consistently indicated that public support in the United States for the use of nuclear energy has been increasing in recent years. Four recent surveys continue to suggest that near-record-high numbers of Americans support nuclear energy. However, the survey results differ—sometimes widely—in the details of their findings.
R.D. Pillsbury, Jr., R.J. Thome, B.A. Smith
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1065-1069
Ignition Device | doi.org/10.13182/FST91-A29484
Articles are hosted by Taylor and Francis Online.
The poloidal field (PF) coil system in a tokamak must provide the flux swing and the equilibrium and shaping field distributions required to create, maintain, and control the plasma during the discharge. The present design for CIT calls for an 11.8 MA plasma in a double null configuration with a major radius of 2.59 m, a minor radius of 0.795 m, and an elongation (at the 95% flux surface) of 2.0. The toroidal field at the major radius is 9 T. The central solenoid is self-supporting and the TF coils wedge under the Lorentz load. The previous design point called for the TF and PF to buck against each other in order to lower the stresses in both. That design called for an 11 MA, 10 T plasma with a major radius of 2.14 m and a minor radius of 0.66 m. The impact on the PF system of this change in the design point is assessed.