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Division Spotlight
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.
Meeting Spotlight
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
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
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.
E. E. Lewis, W. F. Miller, Jr., T. P. Henry
Nuclear Science and Engineering | Volume 58 | Number 2 | October 1975 | Pages 203-212
Technical Paper | doi.org/10.13182/NSE75-A28223
Articles are hosted by Taylor and Francis Online.
A spatial finite element method is formulated for neutron transport calculations in two-dimensional reactor lattice cells in x-y geometry. The method is closely related to classical integral transport techniques in that scalar flux equations result that are similar in form to those of collision probability methods. The use of triangular spatial elements permits flexible geometrical representation of material regions, including regions with curved interfaces. On a rectangular domain, a block inversion technique provides for the incorporation of exact-reflected boundary conditions into the transport kernel. The method is implemented in a computer code and illustrated in a series of lattice cell calculations.
