ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
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.
Juan C. Ramos, Lance J. Agee, Antonio F. Dias
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 170-178
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2860
Articles are hosted by Taylor and Francis Online.
Reported fuel failures at low peak enthalpies for highly exposed fuel during fast reactivity transients promoted the evaluation of reactivity insertion accidents (RIAs) in light water reactors with an approach different from the ultraconservative point-kinetics licensing evaluations performed in the past. On the basis of realistic estimates for the rod worth and plant conditions, an evaluation of the consequences of the RIAs has been performed. For the pressurized water reactor and boiling water reactor (BWR) cases, rod worth became the most important parameter affecting the severity of the accident. In BWRs high subcooling can adversely affect the consequences of the event. The RIA analyses have been performed using an estimation of the distribution for these parameters in an actual plant during startup. The results show that when assumptions consistent with operating procedures are used, the probability of a significant enthalpy increase due to an RIA is greatly reduced.