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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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NEI chief executive highlights “unlimited potential” for nuclear in state of the industry address
Korsnick
In the Nuclear Energy Institute’s annual State of the Nuclear Energy Industry report, NEI president and CEO and Maria Korsnick expressed optimism about the nuclear industry and she issued a call to action.
Her address was part of NEI’s Nuclear Energy Policy forum. The forum, being held in Washington, D.C., on May 20 and May 21, brings together industry leaders, policy stakeholders, and clean energy experts to discuss nuclear advocacy. Korsnick’s remarks focused on the private capital flowing into the industry, progress on regulatory reform and new nuclear technology, and how the U.S. is trying to take the lead on the global nuclear stage.
“We are here at an unprecedented time in our industry history,” Korsnick said. “I’m proud to say that the nuclear industry has a future of unlimited potential.”
L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 238-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32851
Articles are hosted by Taylor and Francis Online.
An integrated experimental approach to mechanistic studies of the leaching and dissolution of irradiated UO2fuel is described. The program includes an investigation of the solubility of the UO2 matrix under thermodynamically well-defined conditions, detailed measurements of the leaching and dissolution of irradiated fuel under simulated disposal conditions, and electrochemical measurements with a novel UO2 electrode to elucidate dissolution mechanisms. Initial experiments show that the solubility of UO2 under alkaline reducing conditions is relatively insensitive to temperature changes, that the leach rates of irradiated fuel are also not strongly temperature dependent, and that surface films on the UO2 fuel may play an important role in the dissolution process. Several aspects of the UO2 matrix dissolution process are now understood, and the approach taken has indicated where future work is needed.