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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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DOE issues new NEPA rule and procedures—and accelerates DOME reactor testing
Meeting a deadline set in President Trump’s May 23 executive order “Reforming Nuclear Reactor Testing at the Department of Energy,” the DOE on June 30 updated information on its National Environmental Policy Act (NEPA) rulemaking and implementation procedures and published on its website an interim final rule that rescinds existing regulations alongside new implementing procedures.
C. A. Flanagan, T. G. Brown, W. R. Hamilton, V. D. Lee, Y-K. M. Peng, T. E. Shannon, P. T. Spampinato, J. J. Yugo, D. B. Montgomery, L. Bromberg, D. Cohn, R. M. Thome, John C. Commander, Robert H. Wyman, J. A. Schmidt, C. W. Bushnell, J. C. Citrolo, R. B. Fleming, D. Huttar, D. Post, Jr., K. Young, F. A. Puhn, R. Gallix, E. R. Hager, J. R. Bartlit, D. W. Swain
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 491-497
The Compact Ignition Tokamak Program | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24794
Articles are hosted by Taylor and Francis Online.
The Compact Ignition Tokamak (CIT) mission is to achieve ignition and provide the capability to experimentally study burning plasma behavior. A national team has developed a baseline concept including definition of the necessary research and development. The baseline concept satisfies the physics performance objectives established for the project and complies with defined design specifications. To ensure that the mission is achieved, the design requires large magnetic fields on axis ( ∼ 10 T) and use of large plasma currents ( ∼ 10 MA). The design is capable of accommodating significant auxiliary heating to enter the ignited regime. The CIT is designed to operate in plasma parameter regimes that are directly relevant to future fusion power reactors. The CIT uses a high-strength copper-Inconel composite plate toroidal magnet design and relies on inertial cooling starting from a liquid nitrogen temperature at the beginning of each pulse. The design is capable of both limiter and divertor operation. The design is compact (1.22 m major radius, 0.45 m plasma radius), has 20 toroidal field (TF) magnets, and has ten major horizontal access ports, about 20 cm by 80 cm, located between alternate TF coils. A total of 3000 full parameter deuterium-tritium (D-T) pulses and 50,000 partial parameter pulses are planned; each full parameter pulse is about 3–5 s. Significant fusion power (300–400 MW depending on ignition assumptions) will be generated; corresponding neutron wall loadings will be in the range 5–10 MW/m2. The current schedule is for a construction project to be authorized for the period FY 1988–93.