ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
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.
Reijo Munther, Juhani Vihavainen, Heikki Kalli, Jyrki Kouhia, Vesa Riikonen
Nuclear Technology | Volume 119 | Number 3 | September 1997 | Pages 235-243
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35400
Articles are hosted by Taylor and Francis Online.
The RELAP5 calculation results for a series of gravity-driven emergency core-cooling (ECC) experiments with the parallel channel test loop (PACTEL) facility are provided. The simulated accident was a small-break loss-of-coolant accident with a break in one hot leg of the three loops of the facility. The ECC flow was provided from a core makeup tank (CMT) located at a higher elevation than the main part of the primary system. The CMT was pressurized with pipings from the pressurizer and a cold leg. The tests indicate that rapid condensation in the CMT influences the ECC flow. The experimental results are numerically analyzed using the RELAP5/MOD3.1 code. The calculations show good agreement with the tests except in the modeling of rapid condensation.
