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
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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Tetsuo Fukasawa, Yoshihiro Ozawa, Fumio Kawamura
Nuclear Technology | Volume 94 | Number 1 | April 1991 | Pages 108-113
Technical Paper | Enrichment and Reprocessing | doi.org/10.13182/NT91-A16226
Articles are hosted by Taylor and Francis Online.
The generation and decomposition behavior of nitrous acid is experimentally investigated during dissolution of unirradiated uranium dioxide (UO2) pellets by a nitric acid solution. The nitrous acid is generated by the dissolution of UO2 and it then decomposes to nitrogen oxides through the solution surface. The generation rate is equal to the dissolution rate of the uranium pellet and it depends on the nitric acid concentration, solution temperature, and effective pellet surface area. The decomposition rate depends on the solution surface area and temperature. These findings allow prediction of changes in nitrous acid concentration during and after dissolution.