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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong
Nuclear Science and Engineering | Volume 63 | Number 1 | May 1977 | Pages 48-54
Technical Paper | doi.org/10.13182/NSE77-A27003
Articles are hosted by Taylor and Francis Online.
We have measured the spectra of neutrons and secondary gamma rays emerging from a liquid-nitrogen sphere of 129.3-cm radius with a 14-MeV neutron source at its center. Time-of-flight techniques were used to obtain the detailed data and to minimize background. To compare the measurements with calculations, we folded the detector efficiencies and appropriate experimental parameters into the calculated output of TARTNP, a coupled neutron-photon Monte Carlo transport code utilizing the Lawrence Livermore Laboratory Evaluated Neutron Data Library, September 1975. The calculated neutron spectra show fair agreement with the measurements, and the calculated gamma-ray spectrum is nearly the same as the corresponding measured spectrum. The total biological dose derived from these measurements is in good agreement with the calculations and provides a benchmark for a dose-versus-range curve obtained by TARTNP calculations.