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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Xiao Gang
Nuclear Science and Engineering | Volume 169 | Number 1 | September 2011 | Pages 56-67
Technical Paper | doi.org/10.13182/NSE10-14
Articles are hosted by Taylor and Francis Online.
To obtain the probability distribution of the burst waiting time of neutron initiation in a multiplying assembly, a method that simulates the neutrons that induce a persistent fission chain is introduced in this paper. By this simulation method, neutron initiation experiments performed on Godiva-II and CFBR-II at a reactivity above prompt critical and performed on Godiva-I at a reactivity above delayed critical are studied. The probability density function of the burst waiting time of these experiments is calculated, and the results agree well with those of the experiments. Based on this simulation algorithm, the strength of the delayed neutron source changing with time is also calculated, which helps in the understanding of these neutron initiation experiments conducted on the pulse reactor.