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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.
A. Colombini, S. Tosti, V. Violante, G. Simbolotti
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 573-577
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30464
Articles are hosted by Taylor and Francis Online.
The analysis of the tritium inventory in Li2O, carried out for the Safety and Environmental Assessment of Fusion Power (SEAFP) helium-cooled ceramic blanket, is based on a diffusion and desorption tritium release model. Within the specific range of breeder temperatures taken into account, desorption was the dominant mechanism so it can be defined as the rate controlling step. At steady state, the model for the tritium inventory in the solid Li2O breeder is supported by a computer code for several operating conditions. At reference conditions of breeder temperatures, by varying the mean grain radius from 1 to 5 µm, a tritium inventory from 0.5 to 2.8 g can be obtained. A helium purge gas velocity from 0.1 to 0.4 m/s gives rise to gas pressure losses from 0.22 to 0.9 MPa, which could probably be reduced by increasing the pebble diameter to 1 mm. This breeder configuration seems to ensure reactor safety.
