ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
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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. Lindner, R. J. Nagle, and J. H. Landrum
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 381-394
Technical Paper | doi.org/10.13182/NSE76-2
Articles are hosted by Taylor and Francis Online.
Neutron capture cross sections for, 238U, 237Np, 232Th, 197Au, 193Ir, 191Ir, 187Re, 185Re, 186W, 181Ta, and 114Cd relative to the 235U fission cross sections have been determined for neutron energies from 120 keV to 2.9 MeV by the measurement of the activation products. Neutrons were produced by the 3H(H,n)3He reaction on tritium gas targets on the Los Alamos Scientific Laboratory vertical Van de Graaff accelerator. Metal foils were exposed at selected angles and distances from the neutron source to achieve a selection of neutron energies. Neutron fluxes were measured with 235U fission detectors placed at various angles for different proton energies. Scattering corrections were applied to the experimental results through the use of Monte Carlo computer simulation techniques. Corrections were also calculated for the purely geometrical effects on energy resolution due to finite source and sample width and thickness.