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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Iskender Atilla Reyhancan, Ayse Durusoy
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 202-207
Technical Paper | doi.org/10.13182/NSE11-96
Articles are hosted by Taylor and Francis Online.
In this study, the activation cross sections were, first, measured for the 144Sm(n,)141mNd reaction at six different neutron energies from 13.57 to 14.83 MeV. The fast neutrons were produced by using a neutron generator, through the 3H(2H,n)4He reaction. The cyclic activation technique was used as the irradiation and counting method. Induced gamma activities were measured using a high-resolution gamma-ray spectrometer equipped with a high-purity germanium detector. In the cross-section measurements, corrections were made regarding the effects of gamma-ray attenuation, dead time, fluctuation of neutron flux, and low-energy neutrons. The measured cross sections were compared with the results of model calculations (TALYS code).