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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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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.
William P. Kelleher, J. Wiley Davidson, Gary R. Thayer, Donald J. Dudziak
Fusion Science and Technology | Volume 17 | Number 3 | May 1990 | Pages 466-475
Technical Note | Shielding | doi.org/10.13182/FST90-A29221
Articles are hosted by Taylor and Francis Online.
A radiation shielding analysis was performed on the Confinement Physics Research Facility (CPRF) under construction at Los Alamos National Laboratory. A reversed-field pinch device, the ZTH, was examined in an effort to obtain an estimate of the spatial distribution of the dose seen by both personnel and electronic components. In the Monte Carlo transport analysis, the MCNP code was used to estimate the neutron and gamma-ray doses and differential flux (in energy) spectra at ten locations within the CPRF. The complex geometry of the ZTH dictated that the problem be solved in a two-step process: First, a cylindrical surface source enclosing the ZTH was computed, and then this source was used as the radiation source for the CPRF building calculations. Using a source strength of 1015 neutrons, identical calculations were performed for both deuterium-deuterium and deuterium-tritium fusion plasmas.