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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Han Gon Kim, John C. Lee
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 300-316
Technical Paper | doi.org/10.13182/NSE97-A1937
Articles are hosted by Taylor and Francis Online.
A new critical heat flux (CHF) correlation has been developed by using the alternating conditional expectation (ACE) algorithm, which yields an optimal relationship between a dependent variable and multiple independent variables. In general, CHF correlation development requires tedious and time-consuming effort because it involves multivariate nonlinear regression analysis. For this reason, existing CHF correlations are usually applicable to specific, and often narrow, ranges of physical parameters. The ACE algorithm is applied to a collection of 12879 CHF data points for forced convective boiling in vertical tubes, and a generalized correlation covering a broad range of flow parameters is obtained. The mean, root mean square, and maximum errors of our new correlation are -0.558, 12.5, and 122.6%, respectively. Our CHF correlation represents the entire set of CHF data with an overall accuracy equivalent to or better than that of three existing correlations. Our results are particularly superior in the high-pressure region covering the rated conditions of pressurized water reactors, as well as in the low-pressure region.