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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
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.