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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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.
Noriaki Nakao, Toshiya Sanami, Tsuyoshi Kajimoto, Robert Froeschl, Davide Bozzato, Elpida Iliopoulou, Angelo Infantino, Hiroshi Yashima, Eunji Lee, Takahiro Oyama, Masayuki Hagiwara, Seiji Nagaguro, Tetsuro Matsumoto, Akihiko Masuda, Yoshitomo Uwamino, Stefan Roesler, Markus Brugger
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 336-347
Research Article | doi.org/10.1080/00295639.2023.2196228
Articles are hosted by Taylor and Francis Online.
Measurements of high-energy neutrons through shield penetration and maze streaming were performed at the Conseil Européen pour la Recherche Nucléaire (CERN) High-energy Accelerator Mixed-Field (CHARM) facility. The protons of 24 GeV/c were injected onto a 50-cm-thick copper target and the released neutrons were transmitted through shields and a maze in the facility. The transmitted neutrons in the shield and maze were measured using activation detectors placed behind various materials and thicknesses of the shields and at several locations in the maze. From the radionuclide production rates in the activation detectors, the attenuation profiles though the shield thickness and along the maze were obtained for the reactions of 209Bi(n,xn)210-xBi(x = 4–9), 27Al(n,α)24Na, 115In(n,n’)115mIn, and 12C(n,2n)11C. Monte Carlo simulations were performed with three codes, PHITS, FLUKA, and GEANT, which had good agreement with the measurements within a factor of 2 for the production rates.