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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
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.
Doron Gal, David Saphier, Ezra Elias
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 64-76
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34568
Articles are hosted by Taylor and Francis Online.
A U-tube steam generator (UTSG) module for the Dynamic Simulator for Nuclear Power Plants is developed. This module is to be used in the simulation of pressurized water reactor (PWR) transients and parametric studies, and it is based on a movable boundary model in which the volumes of the various control volumes are dynamic variables. The UTSG is divided into ten control volumes with movable boundaries between them. The intensive mass and energy balance equations are solved in each control volume, while two integral momentum equations are solved for the primary and secondary flow paths. A homogeneous equilibrium model is assumed in the boiling region. The UTSG model was included in a detailed simulation of the Trojan PWR primary loop. A small loss-of-coolant accident event resulting from a stuck open relief valve transient is presented as an application example.