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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.
Ihor Pasichnyk, Markus Klein, Kiril Velkov, Winfried Zwermann, Andreas Pautz
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 464-472
Technical Paper | Hydraulic Reactor Safety / Fission Reactors | doi.org/10.13182/NT183-464
Articles are hosted by Taylor and Francis Online.
The effects of nuclear data covariance on the rod ejection transient of the pressurized water reactor mixed-oxide/UO2 core benchmark sponsored by the Organisation for Economic Co-operation and Development/Nuclear Energy Agency and the U.S. Nuclear Regulatory Commission are investigated. For this purpose the uncertainty and sensitivity software package XSUSA developed at Gesellschaft für Anlagen- und Reaktorsicherheit is applied to propagate uncertainties in nuclear data libraries to the transient calculations. A statistically representative set of transient calculations is analyzed, and both integral and local output quantities are compared with the benchmark results of different participants. It is shown that the uncertainties in nuclear data play a crucial role in the interpretation of the simulation results. The work is a step forward in establishing a methodology that combines best-estimate calculation with performing uncertainty analysis for coupled full-core calculations.