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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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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.
Michael Boček, Claus Petersen, Lothar Schmidt
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 284-297
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33252
Articles are hosted by Taylor and Francis Online.
The life fraction rule is applied to predict the time to failure of internally pressurized Zircaloy-4 cladding tubes subjected to temperature ramps similar to those expected in a hypothetical loss-of-coolant accident. For given loading conditions, the calculations are solely based on data from uniaxial stress rupture tests. No fitting procedure is involved in the comparison between prediction and results of burst tests. This evidently is an advantage of the present procedure. The agreement between the results of calculations and experiments is good. A modified Monkman-Grant (MMG) relationship, which connects the lifetime with the minimum creep rate and the strain to failure, is used to predict the failure strain of Zircaloy-4 cladding subjected to temperature ramps. This problem turned out to be more complicated than the prediction of lifetime. Contrary to the latter, due to the anisotropy of strain, data from burst experiments enter into the failure strain calculations. Thus the applicability of this method in the present form is restricted to particular loading conditions. However, considering the complexities of the problem, the agreement between experiments and calculations is encouraging.