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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
Ronald C. Brockhoff, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE07-A2641
Articles are hosted by Taylor and Francis Online.
Empirical parameters for a new fast-neutron differential dose albedo formula are presented for water, concrete, iron, and lead and for ten energy bands between 0.1 and 10.0 MeV. Data are also presented for 252Cf spontaneous fission neutrons, 14-MeV neutrons, and thermal neutrons. The 24-parameter approximation, based on modern dose units, agrees with MCNP-calculated values within 10%. Revised data are also presented for a five-parameter secondary-photon albedo formula, proposed earlier by Maerker and Muckenthaler, that is within 20% of MCNP values for the four materials. Finally, these revised albedo formulas are applied to the problem of thermal neutrons transmitted through a three-legged duct and compared to previous experimental results.
