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
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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February 2025
Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
M. Gholampour, K. N. Proskouriakov
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 311-320
Technical Paper | doi.org/10.13182/NSE159-311
Articles are hosted by Taylor and Francis Online.
The goal of this research is to study the coolant parameter fluctuations in the operation mode and start-up period of a nuclear power plant (NPP) with a VVER-1000 water cooled-water moderated power reactor. The coolant pressure pulsations and vibrodynamic processes of the equipment were studied. A new systematic analysis of flow pulsations has been worked out.The measurement results of coolant parameter fluctuations in Unit 1 of the Volgodonskaya NPP are presented. The results of this research are to be utilized for the coolant analysis and detection of the processes that had not been covered in the project documentation but may affect the equipment reliability.
