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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Michael Epstein, Michael A. Grolmes, Robert E. Henry, Hans K. Fauske
Nuclear Science and Engineering | Volume 61 | Number 3 | November 1976 | Pages 310-323
Technical Paper | doi.org/10.13182/NSE76-A26917
Articles are hosted by Taylor and Francis Online.
The extent of penetration of flowing molten ceramic fuel in steel channels before solidification is a problem that arises in the analysis of hypothetical core disruptive accidents. Considerations of fuel crust behavior indicate that fuel freezing in steel channels can occur in two distinct ways that can be identified as conduction-limited freezing (fuel crust growth) and bulk freezing (fuel crust removal). Fuel crust removal can arise from two sources: (a) mechanical breakup and (b) melting heat transfer. Explicit formulas providing rough estimates of critical fuel crust removal conditions are presented. If the conditions in the fuel flow are such to prevent fuel crust growth then the steel wall melting can become severe. It is proposed here that steel ablation rapidly leads to fuel freezing in a bulk manner via turbulent mixing between the relatively “cold” molten steel and hot molten fuel. This steel ablation-induced freezing concept is used to obtain a simple expression for molten fuel penetration into steel channels.