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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Y. S. Rana, Arun Singh, S. B. Degweker
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 245-263
Technical Paper | doi.org/10.13182/NSE11-117
Articles are hosted by Taylor and Francis Online.
Several low-power experiments have evaluated various methods, including those based on noise analysis, to measure the subcritical reactivity in accelerator-driven systems (ADSs). Similar experiments are planned at the Bhabha Atomic Research Centre (BARC). We have developed a new theory of reactor noise in ADSs taking into account the non-Poisson character of the source. One of the aims of the BARC experiments is to verify the theory and to interpret the results in terms of the new theory. As part of the experimental planning, a simulation of the kinds of results that might be expected with different counting and analyzing setups is necessary. We have developed an analog Monte Carlo code for carrying out these simulations. The simulator generates a detailed time history of counts in the detector so that any method of analysis can be carried out. Since analog Monte Carlo takes a very long computing time, instead of carrying out a simulation to yield results equivalent to transport theory, we attempt to reproduce results equivalent to few-group diffusion theory, which requires much less time. We discuss the basic theory of the simulation method and the results of our simulations on a simplified model of a proposed subcritical assembly.