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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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September 2024
Nuclear Technology
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August 2024
Latest News
Singapore, U.S. sign 123 Agreement
The United States and Singapore have signed a civil nuclear cooperation agreement, commonly known as a 123 Agreement.
U.S. secretary of state Antony Blinken and Singapore’s minister of foreign affairs Vivian Balakrishan met on July 31 to formalize the agreement, which outlines a comprehensive framework for peaceful nuclear collaboration between the two nations based on a mutual commitment to nuclear nonproliferation.
S. V. Bechta, V. S. Granovsky, V. B. Khabensky, E. V. Krushinov, S. A. Vitol, A. A. Sulatsky, V. V. Gusarov, V. I. Almiashev, D. B. Lopukh, D. Bottomley, M. Fischer, P. Piluso, A. Miassoedov, W. Tromm, E. Altstadt, F. Fichot, O. Kymalainen
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 210-218
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Materials for Nuclear Systems | doi.org/10.13182/NT10-A9459
Articles are hosted by Taylor and Francis Online.
In case of in-vessel corium retention during a severe accident in a light water reactor, weakening of the vessel wall and deterioration of the vessel steel properties can be caused both by the melting of the steel and by its physicochemical interaction with corium. The interaction behavior has been studied in medium-scale experiments with prototypic corium. The experiments yielded data for the steel corrosion rate during interaction with UO2+X-ZrO2-FeOy melt in air and steam at different steel surface temperatures and heat fluxes from the corium to the steel. It has been observed that the corrosion rates in air and steam atmosphere are almost the same. Further, if the temperature at the interface increases beyond a certain level, corrosion intensifies. This is explained by the formation of liquid phases in the interaction zone. The available experimental data have been used to develop a correlation for the corrosion rate as a function of temperature and heat flux.