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
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!
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Latest News
2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Luiz Rogério Araujo de Araujo, Aquilino Senra Martinez, Roberto Schirru, Renato Kahn
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 324-329
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34133
Articles are hosted by Taylor and Francis Online.
A computerized system that assists pressurized water reactor (PWR) nuclear plant operators in controlling the saturation margin is described. This system continuously calculates and provides the temperature or pressure margin from saturation, and indicates the temperature and pressure values used for its calculation. The reactor core heatup and cooldown rates are also continuously provided by this computer-based system. The saturation curve is represented by a polynomial approximation as a function of temperature or pressure. Twenty-one analog signals of a PWR power plant are acquired by the system for calculating the margin and temperature variation rates. The man/machine interface is done through the visualization panel, which displays the above-mentioned values. Compared to the temperature and pressure values displayed in the visualization panel, the error of margin is always <0.5%.