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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.
Hangbok Choi, Gyuhong Roh, Donghwan Park
Nuclear Science and Engineering | Volume 150 | Number 1 | May 2005 | Pages 37-55
Technical Paper | doi.org/10.13182/NSE05-A2500
Articles are hosted by Taylor and Francis Online.
Benchmark calculations of the Canada deuterium uranium reactor design and analysis codes were performed for the Monte Carlo and conventional methods using Phase-B measurement data of the Wolsong Nuclear Power Plant 2. In this study, the benchmark calculations were done for the criticality, boron worth, reactivity device worth, and flux scan. For the benchmark calculation of the Monte Carlo method by MCNP-4B, the criticality was estimated within 4 mk. The reactivity worth of the control devices was consistent with the measurement data within 15%. For the benchmark calculation of the conventional method composed of WIMS-AECL, SHETAN, and RFSP, the criticality was also predicted within 4 mk. The reactivity device worth was generally consistent with the measured data except for the strong absorbers such as shutoff rods and mechanical control absorbers. The results of the flux distribution calculations were also satisfactory for both code systems.