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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. Smith
Nuclear Technology | Volume 50 | Number 2 | September 1980 | Pages 187-189
Technical Note | Fuel | doi.org/10.13182/NT80-A32545
Articles are hosted by Taylor and Francis Online.
As a result of a post-irradiation metallographic study of power-ramped Canadian natural uranium, heavy-water-moderated and -cooled power (CANDU) reactor fuel rods, it was recently concluded that the observed beneficial effects of graphite CANLUB coating on CANDU fuel’s tolerance to power-ramp defects stem primarily from the interaction of the coating with fission products, rather than by lubrication of the fuel-cladding interface. These arguments are based on a consideration of fuel cracking patterns and the assumption that stress corrosion crack growth within the cladding is the controlling event in the failure process. While these arguments are examined in detail, the present reappraisal leads to the same view of the primary origin of the beneficial effects of graphite coatings on CANDU fuel rod performance.
