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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
S. N. Cramer, E. M. Oblow
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 532-549
Technical Paper | doi.org/10.13182/NSE77-A26990
Articles are hosted by Taylor and Francis Online.
Monte Carlo transport calculations were made to analyze the results of two integral measurements of neutron scattering and gamma-ray production from liquid nitrogen samples. The experimental data from Intelcom Radiation Technology and Oak Ridge National Laboratory (ORNL) were given as angular-dependent NE-213 detector count rates of neutrons and gamma rays scattered from a spherical nitrogen Dewar pulsed with a 1- to 20-MeV neutron source. ORNL results also included unfolded neutron and gamma-ray spectra as a function of detector angle in broad incident neutron energy bins. Multigroup Monte Carlo calculations using the MORSE code and ENDF/B-IV nitrogen cross-section data were made to analyze all reported results. Comparisons of calculated and measured results indicate that no major deficiencies exist in the ENDF/B-IV gamma-ray production data, in contrast to the conclusions drawn from studies in previous years. Deficiencies, however, were found in the neutron data, primarily in the elastic and inelastic data above 9 MeV and in the elastic angular distribution data around 5 MeV.