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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
Joh. F. van de Vate, A. Plomp
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 196-200
Technical Paper | doi.org/10.13182/NSE75-A26658
Articles are hosted by Taylor and Francis Online.
A simple boundary condition has been derived which allows prediction of the stability of an enclosed atmosphere above a heated liquid. The correctness of the condition has been shown by experiments with various vapor-gas systems. Application to nuclear reactor containments under hypothetical accident conditions demonstrates the presence of a stirred atmosphere for sodium-cooled reactors. In case of water-cooled reactors, the containment atmosphere will be stirred when large amounts of fission products are present in the sump water in the concrete cavities located in the lower part of the containment building.