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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.
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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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.
Dong H. Nguyen
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 80-91
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32509
Articles are hosted by Taylor and Francis Online.
A methodology has been constructed to assess the uncertainty in an output consequence calculated by a large code, due to the uncertainties in input data. A sensitivity analysis was first applied to the code to screen the input variables, leaving only those most affecting the output consequences. The variations of these effective inputs were prescribed by an effective combination of statistical designs, which accounted for the linear, quadratic, and two-factor interaction effects of the inputs on the calculated consequence. A key result of the methodology was the probability density function of the consequence of interest, expressed as a distribution of the Pearson family. The confidence level in calculating a consequence was readily obtained from this distribution function. The methodology was applied to the computer code MELT-IIIA, a major code for the analysis of the hypothetical core disruptive accident in liquidmetal fast breeder reactors, and the confidence level in predicting the time of initial pin failure during a transient overpower accident in the fast test reactor was determined. The sensitivity of this confidence level to the uncertainties of the input data was also shown, thereby establishing the need for well-documented statistical properties of data used in nuclear reactor safety analysis.