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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
R. Krieg, T. Malmberg, G. Messemer, T. Stach, E. Stratmanns
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 369-385
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15867
Articles are hosted by Taylor and Francis Online.
The most severe consequence of a pressurized water reactor in-vessel steam explosion is a molten fuel slug impact against the head of the reactor pressure vessel that could cause a failure of this head and lead to missiles endangering the reactor containment. An investigation is described that attempts to determine the maximum slug impact that a vessel head is capable of withstanding without failing and, consequently, without impairing the containment safety-related function. Preliminary theoretical assessments are presented that suggest that the head might be able to withstand rather strong impacts and that the shape of the fuel slug will have only a moderate influence on the results, provided the upper internal structures are taken into account. A low sensitivity against the slug shape is an essential prerequisite for a reliable safety proof. However, investigations primarily based on computational models are not sufficient; therefore, an investigation concept is proposed that relies on model experiments in which the geometry is scaled down by factors of 10 and 20, respectively. Theoretical and experimental investigations for liquid-structure impact problems in different scales are discussed to assess the degree of similarity that can be obtained. Finally, model experiments are described in some detail simulating the molten fuel slug impact on the vessel head.