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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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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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.
R. P. Gardner, C. L. Barrett, W. Haq, D. E. Peplow
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 326-343
Technical Paper | doi.org/10.13182/NSE96-A24168
Articles are hosted by Taylor and Francis Online.
A Monte Carlo code named Mcnaff has been developed and tested for flow rate measurement and general composition determination of a flowing fluid by neutron activation analysis. Specifically, oxygen determination in a flowing fluid is treated, including simulating the emission and transport of neutrons in the fluid, the activation of l6O to 16N, the subsequent flow and dispersion of the 16N in the flow channel, the downstream decay of 16N, and the subsequent detection of the emitted decay gamma rays. This code is very efficient, partly because (a) the continuous single history approach has been taken, which follows a single history from emission of a neutron, through the production and decay of the 16N and the emission of a characteristic gamma ray, and finally to the full energy detection of the gamma ray and (b) the principle of forcing can be and is used throughout so that almost every history results in a partial success. The present Mcnaff code is capable of calculating gamma-ray detection yields per neutron emitted to the same accuracy as an approach by Perez-Griffo, Block, and La hey, which numerically solves the partial differential equations for modeling particle dispersion and diffusion and calculates separately by Monte Carlo both the neutron absorption and gamma-ray detection process. The Mcnaff code is estimated to be about two orders of magnitude faster and should be more convenient to use because all calculations are accomplished in a single step.