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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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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.
Hsiang-Shou Cheng, Ming-Shih Lu, David J. Diamond
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 283-298
Technical Paper | Reactor | doi.org/10.13182/NT78-A32114
Articles are hosted by Taylor and Francis Online.
The space-time effects associated with the void reactivity feedback in a commercial boiling water reactor were studied with the aid of the two-dimensional (R,Z) time-dependent coupled neutronics thermal-hydraulics computer code BNL-TWIGL. The statistical weight factor (SWF), which equates a point-reactor model to an appropriate space-dependent model, was used to quantify these effects. The SWF varied for the different reference reactor conditions and types of void perturbations considered. Its significant magnitude demonstrated that unless proper account is taken of multidimensional effects in plant transient calculations, the void feedback will be incorrect, and this will lead to errors in power and temperature. The presence of bypass void was found to increase the void reactivity feedback. The influence of other feedback mechanisms was studied, and a suggestion was offered for obtaining a measurement of the void reactivity coefficient.