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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
International High-Level Radioactive Waste Management Conference
Workshop
Sunday, November 13, 2022|9:00AM–12:00PM MST|Honeysuckle
UNF-ST&DARDS is being developed to provide the ability to perform automated analysis of spent nuclear fuel (SNF) storage, transportation, and disposal systems. UNF-ST&DARDS provides a database for storing and preserving SNF data and streamlines various analyses using the data from the database for time-dependent characterization of SNF and related systems (e.g., dry storage system). UNF-ST&DARDS allows for modelling the variation of cask payload burnup, enrichments, and cooling times through a flexible GUI. This tutorial will include 1) discussions on various data need for realistic SNF characterizations and demonstration of the data import processes in UNF-ST&DARDS, 2) assembly-specific, time-dependent depletion and decay analyses, 3) as-loaded (using actual cask loading maps) criticality and shielding analyses of currently loaded casks for storage, transportation, and disposal (over disposal time periods), 4) discussion of as-loaded analyses to support licensing/certification of dry SNF systems, 5) misload analysis methodology to support as-loaded criticality analysis, 6) design-basis criticality and shielding analyses using user-defined loading patterns and fuel assembly types, and 7) dry storage loading optimization using UNF-ST&DARDS. The tutorial/demonstration is open to all registered meeting attendees who signed up at the time of registration. Attendees have no requirements to watch the demonstration, however, an RSICC license for UNF-ST&DARDS and SCALE is necessary if they would like to follow along.
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