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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
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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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
G. Dharmadurai
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 345-349
Technical Paper | doi.org/10.13182/NSE83-A15455
Articles are hosted by Taylor and Francis Online.
A simple acoustic mismatch model can predict heat flow across solid/fluid interfaces at high temperatures in terms of known physical properties of the system. Using this model, the thermal boundary conductances of the various interfaces involved in heat transfer from the fuel pellet to the cladding of fast reactor fuel rods are estimated. The typical values of fuel-cladding gap conductance of helium-bonded fast reactor fuel rods quoted in the literature are in reasonable agreement with estimates obtained from this model. In addition to its striking simplicity, an interesting and novel feature of this fundamental approach is the prediction of a marginally high gap conductance for a helium-bonded oxide fuel rod over its carbide counterpart.