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
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Zaporizhzhia ‘extremely fragile’ relying on single off-site power line, IAEA warns
Europe’s largest nuclear power plant has just one remaining power line for essential nuclear safety and security functions, compared with its original 10 functional lines before the military conflict with Russia, warned Rafael Mariano Grossi, director general of the International Atomic Energy Agency.
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.