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Division Spotlight
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.
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.
Jerzy Kubowski
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 59-69
Technical Paper | Reactor | doi.org/10.13182/NT80-A32412
Articles are hosted by Taylor and Francis Online.
The dynamics model for fast transients analysis in the Polish research reactor Maria has been developed. The model includes, besides the point kinetic equations, the heat transfer and spatially dependent equations for calculating the temperature distribution in the average fuel channel. The space effects in the reactor core were taken into account by flux-weighted temperatures. The code TOTEM, for the CDC-CYBER 73 digital computer, was written in FORTRAN-EXTENDED. Detailed calculations allowed us to obtain the following dynamics parameters for the hot and poisoned reactor core: βeff = 0.00726 and l = 2.65 × 10−4 s. The temperature-dependent reactivity coefficients were used to calculate the feedback effects. To examine the applicability of the model, a series of rod drop experiments was performed, and the comparison of the calculated and measured excess reactivities has shown that the discrepancy does not exceed 2%.