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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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.
Alex Galperin, Jean-Michel Evrard
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 131-141
Technical Paper | doi.org/10.13182/NSE91-A15727
Articles are hosted by Taylor and Francis Online.
Development of a knowledge-based system for supervision of a continuous process requires, on the one hand, efficient and flexible knowledge structuring and, on the other hand, overall system control, which provides coherence between the diagnosis task (deduction) and the prediction task (simulation). The development of a reasoning method that combines qualitative and quantitative analysis approaches is described. This method is integrated into an overall computational system for a knowledge-based supervisor. The prototype was tested by simulating the transient behavior of the auxiliary feedwater system of a pressurized water reactor. The preliminary results indicate the feasibility of the methods and their potential for industrial applications.