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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
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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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Latest News
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
K. H. Beckurts
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 516-522
Technical Paper | doi.org/10.13182/NSE57-A25417
Articles are hosted by Taylor and Francis Online.
The pulse method has been applied to problems of neutron diffusion in graphite. By measuring the decay constant of the neutron flux emanating from various graphite pile geometries, the diffusion coefficient and the absorption cross section can be determined with great precision. In comparison to an exponential experiment, the quantity of graphite necessary for an accurate determination of the diffusion length can be considerably reduced. The finite geometry of the moderator gives rise to a diffusion-cooling effect on the neutron equilibrium temperature which can be understood quantitatively by a direct measurement of the heat transfer from the neutron gas to the lattice. In the second part of the work, the pulse method is used to determine the influence of eccentric control rods on the buckling of a cylindrical reactor model.
