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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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ANS Standards Committee publishes joint ASME/ANS standard for Level 1/large early release frequency PRA
ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, has been published by the American Nuclear Society. The document, which is a joint standard developed with the American Society of Mechanical Engineers by the ANS/ASME Joint Committee on Nuclear Risk Management, received the approval of the American National Standards Institute on February 29, 2024, and was issued on March 15, 2024.
Mohamed Elsafi, Jamila S. Alzahrani, Mahmoud I. Abbas, Mona M. Gouda, Abouzeid A. Thabet, Mohamed S. Badawi, Ahmed M. El-Khatib
Nuclear Science and Engineering | Volume 195 | Number 9 | September 2021 | Pages 1008-1016
Technical Note | doi.org/10.1080/00295639.2021.1895406
Articles are hosted by Taylor and Francis Online.
The optimization of measurement of environmental samples is achieved by putting the sample closer to the detector to increase the full-energy peak efficiency, which leads to decrease of the detection limit. The present work inspects the utilization of Geant4 simulation for a NaI cubic scintillation detector with a cavity using two tracks. The radionuclide option includes coincidence summing, and the monoenergetic option is summing free coincidence. The ratio between the monoenergetic to redionuclide options gives the coincidence summing correction factors. In the experiments a gamma-ray aqueous source containing the radionuclide 152Eu covering the range from 121 to 1408 keV was used. Comparing the monoenergetic option for calculating the full-energy peak efficiency and the corrected experimental efficiency, the values are in agreement.