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Division Spotlight
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.
Meeting Spotlight
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.
Cesare Frepoli
Nuclear Science and Engineering | Volume 194 | Number 8 | August-September 2020 | Pages 825-832
Technical Note | doi.org/10.1080/00295639.2020.1753419
Articles are hosted by Taylor and Francis Online.
Integral systems test (IST) facilities, which are sometimes referred to as integral effects tests (IETs), play a key role in the design, assessment, and certification of innovative reactor designs. Data obtained using such facilities have been used to benchmark the best-estimate safety analysis computer codes used to evaluate nuclear plant safety. They have also been used to assess the effectiveness of safety system functions under simulated accident conditions. Scaling analyses are an important component in determining the applicability of an evaluation model for its intended purpose. Evaluation models can only approximate the physical behavior of postulated events on a prototype, and the judgment of their adequacy relies heavily on their capability in predicting IETs that were designed to simulate the events analyzed. With few exceptions, all ISTs are subscale representations of the power plants they are built to represent. As thermal-hydraulic computer codes are benchmarked to an IST database, the most important challenge for the analyst is the development of convincing scaling similarities between the IST and the plant. Unless such rules are clearly identified, it would not be possible to extend conclusions from the assessment of the tools against subscale data to the plant scenario time and geometry scales.