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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jun 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Technical Session
Thursday, May 19, 2022|3:30–5:15PM EDT|Brighton III/IV
Session Chair:
Una Baker (University of Wisconsin)
Alternate Chair:
Session Organizer:
Ben Lindley (University of Wisconsin)
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Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE
Joseph R. Burns (ORNL), Germina Ilas (ORNL), Ugur Mertyurek (ORNL), William Wieselquist (ORNL)
Paper
Criticality Analysis of a Variant Model of a Spent Fuel Cask
Loretta Boahemaa Manu (Harbin Engineering Univ.), Xiang Wang (Harbin Engineering Univ.)
Presentation Video (Visible to Attendees)
Scoping Studies of Subcritical Minor Actinide-Burning Fission-Fusion Hybrid Designs for Nuclear Waste Reduction
J. Ruegsegger (Univ. Wisconsin, Madison), C. Moreno (Univ. Wisconsin, Madison), M. Nyberg (Univ. Wisconsin, Madison), T. Bohm (Univ. Wisconsin, Madison), P. Wilson (Univ. Wisconsin, Madison), B. Lindley (Univ. Wisconsin, Madison)
Markov Chain Models of Nuclear Transmutation: Theory and Application
Máté Halász (Budapest Univ. Technology and Economics), Mate Szieberth (Budapest Univ. Technology and Economics)
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