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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
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Amelia Island, FL|Omni Amelia Island Resort
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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Daniel Maier, Paul Coddington
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 153-168
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3022
Articles are hosted by Taylor and Francis Online.
The RETRAN-3D code provides the user with a range of options for calculating the liquid-vapor slip. In the three-equation model, for example, two drift flux correlations are available, while the four-equation model includes an additional momentum equation with three interphase friction options. To assess the adequacy of these options, RETRAN-3D has been evaluated against a wide range of rod bundle void fraction data. The data used for this analysis includes information on 83 experiments from nine facilities performed in four different countries.The results of the assessment show that all options provide an excellent prediction of the data for conditions typical of boiling water reactor normal operation. However, there is a progressive worsening of the predictive quality of all options, except that of the Chexal-Lellouche correlation, as first the flow rate and second the system pressure is reduced. At low mass fluxes and pressures, there is some overprediction by the Chexal-Lellouche correlation, while at very low pressures the code fails to reach a converged solution. An assessment of the five-equation subcooled boiling model shows an overprediction of the void fraction for negative values of the equilibrium quality.