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
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.
M. M. R. Williams, J. M. Kallfelz
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 416-419
Technical Note | doi.org/10.13182/NSE78-A27170
Articles are hosted by Taylor and Francis Online.
An analysis is made of the accuracy of the buckling approximation for the transverse leakage, used in various one- and two-dimensional transport theory computer codes. We find that the resulting approximate integro-differential form of the transport equation is not suitable for calculating accurate values of the angle-dependent flux for any case where transverse leakage has an appreciable effect on the solution. We have taken four problems, namely, critical equation, pulsed neutron and diffusion length problems, and extrapolated endpoints, and have solved them exactly using an equation derived in an earlier paper; we then solve the same problem by means of the buckling equation. In all cases, important deviations are noted that restrict the use of the buckling approximation.