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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Mar 2025
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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
Robert W. Lyczkowski, Delwin C. Mecham, Charles W. Solbrig
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 279-289
Technical Paper | doi.org/10.13182/NSE79-A20617
Articles are hosted by Taylor and Francis Online.
A transient velocity difference model called the dynamic slip model has been integrated into the FLASH-4 numerical scheme. The numerical scheme resulting from combining this model with the general purpose RELAP4 network computer code is described. The result is a code that calculates slip in all junctions both vertical and horizontal. Results of computations are compared to U.S. Nuclear Regulatory Commission standard problems 1 and 6.