ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Vinicius-Nicolae-Petre Anghel
Nuclear Science and Engineering | Volume 97 | Number 3 | November 1987 | Pages 249-256
Technical Note | doi.org/10.13182/NSE87-A23508
Articles are hosted by Taylor and Francis Online.
A general acceleration scheme for the iterative transport calculations is analyzed, and the implementation of this scheme in the two-dimensional transport code TWOTRAN PNWV is described. The convergence radius is estimated for homogenous one-dimensional slab problems. Two-dimensional benchmark problems are used to outline the dependence of the convergence on the material properties and on the fine- and coarse-mesh grids. Possible applications of this scheme to obtain acceleration methods for other iterative algorithms are suggested.