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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
M. Wimmers, P. Pohl
Nuclear Science and Engineering | Volume 97 | Number 1 | September 1987 | Pages 53-57
Technical Paper | doi.org/10.13182/NSE87-A23495
Articles are hosted by Taylor and Francis Online.
In collaboration with Kernforschungsanlage Jülich, Federal Republic of Germany, and other companies, dynamic experiments have been carried out with the Arbeitsgemeinschaft Versuchsreaktor (A VR) to test advanced dynamic computer models with the goal of using low-enriched uranium (LEU) fuel in future high-temperature gas-cooled reactors. Since LEU fuel has been used for the AVR since 1982, both experimental and theoretical behavior has been studied during the changeover from highly enriched uranium to LEU. The experiments comprise fast power transients that are initiated by either a fast control rod movement or a fast change of coolant flow. The neutron flux and other important parameters are registered in suitable time expansion. To prevent the cantilevered segments of the carbon brick core ceiling from being exposed to unallowable high-temperature gradients, the rod movements are restricted to limit the reactivity variation to ∼ 60 mNile. For the coolant flow transients, the blower speed is usually reduced from 100 to 50%, and then elevated again to 80% after 30 min. A return to 100% is not possible because of the overshoot of the neutron flux. Also, in some experiments the speed is reduced to 80%, after which the core remains under the control of xenon influence for ≈1 day.