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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Nokyu Seong, Yeonsub Jung, Chanho Sung (Korea Hydro & Nuclear Power Central Research Inst), Poonghyun Seong (KAIST)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1478-1484
Plant procedures are instructions to guide operators in monitoring, decision making and controlling for operation of nuclear power plants. While plant procedures historically have been paper-based, the computer based procedures are being developed and applied to overcome the drawbacks of paper-based procedures in many nuclear power plants. Advance Power Reactor 1400 MWe (APR1400) Computerized Procedure System (CPS) has applied at Shin-Kori 3&4 units of Korea since 2012 and recently Shin Kori unit 3 has achieved one cycle trouble free. APR1400 CPS can be classified as type 2 and family 2 based on IEEE standard 1786, IEC standard 62646 respectively. APR1400 CPS has the function to navigate between procedure elements such as procedures, gross steps, steps and instructions and also has many functions mentioned in IEEE standard such as providing process data in the body of procedure steps and process step logic and evaluated data, and access links to soft control and process displays. To maximize the strength of computer-based procedures and to reduce the human errors, procedure based automation is needed. And international standard also states that the next step of computer based procedure is the automation using computer based procedure. Currently APR1400 CPS can support the functions to implement procedure based automation providing the various logic functions such as procedure entry condition monitoring, re-execution condition monitoring for continuous applied step, and automatic evaluation of instructions. To apply procedure based automation, the logic equations are made in the process of procedure writing. This paper introduces the overview of currently APR1400 CPS including the support functions automated and shows the result of partial procedure based automation using Standard Post Trip Actions (SPTA) and Diagnosis Actions (DA) including procedure entry condition monitoring and automatic evaluation of instructions through the Loss Of Coolant Accident (LOCA) scenario. This validation of partial procedure based automation was tested in full scope simulator of APR1400. And this paper also suggests the necessary functions and considerations to implement the procedure based automation.