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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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.”
R. Stephen Devoto, William L. Barr, Richard H. Bulmer, Robert B. Campbell, Max E. Fenstermacher, Joseph D. Lee, B. Grant Logan, John R. Miller, Louis L. Reginato, R. A. Krakowski, Ronald L. Miller, Oscar A. Anderson, W. S. Cooper, Joel H. Schultz, James J. Yugo, Joel H. Fink, Yousry Gohar
Fusion Science and Technology | Volume 19 | Number 2 | March 1991 | Pages 251-272
Technical Paper | Fusion Reactor | doi.org/10.13182/FST91-A29363
Articles are hosted by Taylor and Francis Online.
The extensions of the physics and engineering guidelines for the International Thermonuclear Experimental Reactor (ITER) device needed for acceptable operating points for a steady-state tokamak power reactor are examined. Noninductive current drive is provided in steady state by high-energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma, and bootstrap current. Three different levels of extension of the ITER physics/engineering guidelines, with differing assumptions on the possible plasma beta, elongation, and aspect ratio, are considered for power reactor applications. Plasma gain Q = fusion power/input power in excess of 20 and average neutron wall fluxes from 2.3 to 3.6 MW/m2 are predicted in devices with major radii varying from 7.0 to 6.0 m and aspect ratios from 2.9 to 4.3. Only modest enhancements over L-mode (Goldston) energy confinement are required. Peak divertor heat fluxes range up to 12.4 MW/m2, which is somewhat higher than the current ITER design limit of 10 MW/m2 with a magnetically swept divertor. These designs were selected on the basis of improvements in physics/engineering consistent with time scales for development of future reactors. The design reoptimization on the basis of cost of electricity (COE) was then examined using a reactor systems model. This analysis generally verified the original estimates for the required extensions of the ITER guidelines. The COE is projected to be <66 mill/kW(electric) · h in all of the configurations. The smallest reactor, which has the largest neutron wall flux and mass power density, yields the lowest COE, 56 mill/kW(electric)· h. While these costs are marginally competitive with fission power, these modest extensions of the ITER guidelines do produce a viable power reactor. With time for further improvements such as those pursued in the ARIES study, similar designs could present an even more competitive commercial product.