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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
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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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.
Helmut Steiner, Monika Heck
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 209-221
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT98-A2893
Articles are hosted by Taylor and Francis Online.
About 70 single-rod quench tests with fresh and preoxidized Zircaloy specimens are carried out at Forschungszentrum Karlsruhe with water and steam as quench media. A number of mechanical effects are observed on the cladding of the test rods by posttest examination; the most important ones are the occurrence of through-wall cracks mainly for thick oxide scales and a severe degradation of the -phase for water-quenched and steam-cooled tests.Calculations of some tests are done with the WSPAN one-dimensional rod mechanics code. This code calculates a very high stress pulse in the oxide scale occurring at the phase transition in the oxide phase. With the assumption of purely elastic behavior of the -phase at the high strain rates occurring at the phase transition, the cracking in the -phase and the formation of through-wall cracks can be understood.