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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Arsalan Razani, H. E. Hungerford
Nuclear Science and Engineering | Volume 46 | Number 1 | October 1971 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE71-A22330
Articles are hosted by Taylor and Francis Online.
This paper examines a new probabilistic formulation and development of a model for the investigation of three-dimensional gamma-ray transport problems. This model assumes that gamma-ray motion may be sampled at predetermined points. A medium is considered to be filled with a cubic lattice whose unit distance between lattice points may be some fraction of the mean-free-path. The random walk of gamma rays from one point to another is constructed using the lattice framework as reference points. Using this model, a new type of stochastic gamma-ray transport code, PUGT I (Purdue University Gamma Ray Transport I), has been developed based on direct simulation of physical transport process. In another version of the code (PUGT II), capture of gamma rays is taken into account analytically by associating a weight factor to the gamma rays. The codes are used to calculate the transmission and reflection characteristics of gamma rays for different thicknesses of slabs of aluminum and iron. The contribution of annihilation radiation to reflection and transmission is investigated. The results of our calculations are in good agreement with other similar calculations and with experimental results. Gamma-ray streaming through two-legged rectangular concrete ducts was investigated. Results of these studies are in very good agreement with experimental results and demonstrate the ability of the codes and the power of the lattice model to calculate quickly and efficiently the transmission of gamma rays in three-dimensional complex shielding geometries. The method is several times faster than ordinary Monte Carlo.