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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
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.