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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.
Saam Yasseri, Farzad Rahnema
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 292-311
Technical Paper | doi.org/10.13182/NSE13-9
Articles are hosted by Taylor and Francis Online.
In this paper, a new spatial homogenization method in transport theory is developed that reproduces the heterogeneous solution by using conventional flux-weighted homogenized cross sections. By introducing an additional source term via an auxiliary cross section, the resulting homogeneous transport equation becomes consistent with the heterogeneous equation, enabling easy implementation into existing solution methods/codes. This new method utilizes on-the-fly rehomogenization, performed at the assembly level, to correct for the effect of core environment on the homogenized cross sections. The method is derived in general geometry and continuous energy and implemented and tested in fine-group one-dimensional slab geometries typical of boiling water reactor and gas-cooled reactor cores. The test problems include two single-assembly and four-core configurations.