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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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.
Fujio Maekawa, Yujiro Ikeda, Yuriy M. Verzilov, Chikara Konno, Masayuki Wada, Hiroshi Maekawa, Yukio Oyama, Yoshitomo Uno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1081-1087
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963094
Articles are hosted by Taylor and Francis Online.
To assess validity of the shielding design tools for ITER, the benchmark experiment on SS316/Water shield conducted at FNS/JAERI is analyzed. As far as a simple bulk shield of SS316/Water is concerned, the followings are found assuming that no uncertainty is involved in the response functions of the design parameters. Nuclear data bases of JENDL Fusion File and FENDL/E-1.0 are valid to predict all the design parameters with uncertainties less than a factor of 1.25. At the connection legs between shield blanket modules and back plates, both MCNP and DOT calculations can predict helium production rate with uncertainties less than 10 %. For the troidal field coils on the midplane, all the nuclear parameters can be predicted with uncertainties less than a factor of 1.25 by MCNP and DOT with consideration of self-shielding correction of cross sections and energy group structure of 125-n and 40-γ. The uncertainties for toroidal field coils are considerably smaller than the design margins secured to the shielding designs under ITER/EDA.