ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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%.