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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.
L. L. Briggs, E. E. Lewis
Nuclear Science and Engineering | Volume 63 | Number 3 | July 1977 | Pages 225-235
Technical Paper | doi.org/10.13182/NSE77-A27035
Articles are hosted by Taylor and Francis Online.
A new coarse-mesh technique, the constrained finite element method, is formulated from the variational form of the even-parity transport equation: Linear finite elements in space are combined with a P1 constraint on the angular trial functions at selected nodes to obtain a coarse-mesh three-point difference scheme for the scalar flux. Beginning with the same variational form of the transport equation, response matrix equations are derived that differ from the constrained finite element method only in the angular approximation made at the coarsemesh nodes. The two techniques are compared to each other, to S8 reference solutions, and to diffusion calculations for a number of one-group slab geometry problems involving both homogeneous media and lattice cells; they are found to be of comparable accuracy and efficiency. The generalization of the constrained finite element method is discussed.