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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Y. Naito, M. Maekawa, K. Shibuya
Nuclear Science and Engineering | Volume 58 | Number 2 | October 1975 | Pages 182-192
Technical Paper | doi.org/10.13182/NSE75-A28221
Articles are hosted by Taylor and Francis Online.
A new iterative method is proposed for solving the three-dimensional neutron diffusion equation. This method reduces the discretization error in the calculation of neutron leakage from a subregion. In addition, when only one fine-mesh point is located in each subregion, this method becomes the same as a fine-mesh finite-difference approximation method. Therefore, it is easy to compare the results of this method with those of a fine-mesh difference approximation. The computer code for this method can be used for calculating both the collapsed neutron flux and fine-mesh difference approximations. The conditions for the convergence of this iterative technique are introduced as a function of the neutron leakage.