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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Ninos S. Garis, Imre Pázsit, Urban Sandberg, Tell Andersson
Nuclear Technology | Volume 123 | Number 3 | September 1998 | Pages 278-295
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2899
Articles are hosted by Taylor and Francis Online.
A method is described by which the axial position of a control rod can be determined. The method is based on the influence of a partially inserted control rod on the axial flux profile. By measuring this flux profile, the control rod position can be in principle unfolded. One problem is however that the relationship between rod position and flux profile is rather implicit and cannot be explicitly inverted. Thus, it is suggested here to use neural network techniques to unfold the rod position from the measured flux profile. For training of the network, a large number of flux profiles are needed, corresponding to various known rod positions. These data can be generated by advanced core calculational codes. In this study, the Studsvik core master system SIMULATE was used. The method was tested with good results on both fully simulated data as well as on a measurement taken at the Swedish pressurized water reactor Ringhals 4.