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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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%.
