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Division Spotlight
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.
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.
Marianna Papadionysiou, Kim Seongchan, Mathieu Hursin, Alexander Vasiliev, Hakim Ferroukhi, Andreas Pautz, Han Gyu Joo
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1056-1066
Technical Paper | doi.org/10.1080/00295639.2020.1753418
Articles are hosted by Taylor and Francis Online.
The current standard for computational neutronic analysis of nuclear power plants (NPPs) is the so-called conventional approach, which relies on few-group, coarse-mesh diffusion calculations. The recent evolution of computing clusters and computational techniques gives the opportunity to use codes that perform first principles–based multiphysics simulations, allowing high resolution of the calculated parameters. The goal of this work is to assess the performance of the deterministic high-resolution transport code nTRACER and the nodal code PARCS on the basis of VVER core configurations. The V1000-2D benchmarks of the NUclear REactor SIMulation (NURESIM) project framework are used to provide the neutronic and modeling data as well as reference solutions for both codes. A reference solution is also generated using Serpent2. The accuracy and limitations of the codes are illustrated together with their computational requirements. PARCS shows good agreement with the reference solutions although the results present some discrepancies due to the provided discontinuity factors. nTRACER is capable of producing high-accuracy and high-resolution solutions in a fraction of the time required by the Monte Carlo solver.