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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Ibrahim Jarrah, Rizwan uddin (Univ of Illinois)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 503-512
The spent fuel dry cask should remain subcritical under normal, abnormal, and accident conditions. The cask becomes susceptible to criticality if it is misloaded with assemblies that do not conform with the Certificate of Compliance (CoC). To avoid this scenario, the cask loading process involves several verification steps to make sure that all of the loaded assemblies satisfy the CoC requirements. However, most of loading and verification steps are carried out by humans with finite probabilities for errors, which need to be quantified. In this paper, the probability of misloading a cask with light water reactor (PWR and BWR) fuel is quantified using the event tree method. Probability distribution functions for all of the human errors are obtained using the SPAR-H human reliability analysis method. The Fussell-Vesely (FV) importance measure is performed to determine the tasks that contribute the most to the having a misloaded cask. The probability of misload is found to be 5.56E-06 for cask loaded with the PWR and 2.95E-05 for the cask loaded with the BWR fuel. Both of these are considered to be small.
