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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
Harshavardhan Kadvekar, Sana Khan, Sangeetha Prasanna Ram, Jayalekshmi Nair, S. Ganesan
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 356-370
Technical Paper | doi.org/10.13182/NSE15-103
Articles are hosted by Taylor and Francis Online.
In a majority of the cases, error propagation studies in nuclear science and engineering use the sandwich formula, which is strictly applicable when the probability density function of the random input quantities (e.g., the basic cross-section data) are determined completely by the mean and covariances. The use of the sandwich formula, which is also referred to in the literature as traditional first-order sensitivity analysis or adjoint-based sensitivity and uncertainty analysis, requires the assumption of linearity assumption and relatively small errors. For the first time, this paper examines the application of unscented transformation (UT) technique, which is used in control and reliability engineering, to error propagation in the nuclear field for nonlinear cases. Using different examples, this paper shows that this deterministic method of UT produces better results compared to the conventional sandwich formula for error propagation. An example on error propagation given in the literature is revisited, and a calculation of the efficiency of a gamma-ray detector is also presented for illustrative purposes using the UT method.