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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
G. Ferran, W. Haeck, M. Gonin
Nuclear Science and Engineering | Volume 179 | Number 3 | March 2015 | Pages 285-301
Technical Paper | doi.org/10.13182/NSE14-64
Articles are hosted by Taylor and Francis Online.
This paper describes in detail a new method to calculate the integral that appears in the expression of cross-section Doppler broadening. This method is based on a Fourier transform and seems quite promising as our tests suggest it is able to reach any required precision within a reasonable amount of calculation time. Another method to calculate Doppler-broadened cross sections based on Gauss quadrature will be presented, even if it requires too much computation time to be of practical use. Both methods have been implemented in a new nuclear data-processing software called GAIA, which is currently under development at the French Institut de Radioprotection et de Sûreté Nucléaire. Results of the comparison of the broadened cross sections obtained with the GAIA methods and with the NJOY processing system are discussed in the paper.