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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
Dimitar Altiparmakov, Robert Wiersma
Nuclear Science and Engineering | Volume 182 | Number 4 | April 2016 | Pages 395-416
Technical Paper | doi.org/10.13182/NSE15-28
Articles are hosted by Taylor and Francis Online.
The size and the density of the collision probability matrix have been recognized as major deficiencies since the early era of development of the collision probability method. The computing time of the matrix inversion is proportional to the third degree of the number of unknowns per group and increases rapidly with the increase of the problem size. This is a severe limitation that restricts the capabilities of the method and makes it inapplicable to large-size neutron transport problems. This paper presents a new solution method that overcomes these deficiencies and extends the capabilities of the collision probability approximation. To reduce the matrix inversion time, a block partition is applied, and the solution is obtained by block iteration. Owing to the partition, the method is suitable for parallel calculations on contemporary computers. To illustrate the potential advantages, the following three groups of calculations are presented. In the first group, results of sequential calculations reveal the advantage over traditional methods of direct solution and point iteration. In the second group, memory shared parallelism results present the speedup that can be achieved in solving medium-size problems on a standard multicore desktop computer. In the third group, distributed memory calculations show an example of the solution of a large-size two-dimensional model problem of a heavy water power reactor invoking 100 thousand unknowns per group.