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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
Friday, April 9, 2021|11:00AM–12:30PM EDT
Session Chair:
Cao Da (NC State Univ.)
Alternate Chair:
Ishita Trivedi
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producer:
Roberto Fairhurst-Agosta (Univ. of Ill., Urbana-Champaign)
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Designing a Load Following High Temperature Gas-Cooled Reactor System
Kaitlyn E. Barr (University of Michigan Ann Arbor), Joshua Cooper (University of Michigan Ann Arbor), Lincoln Johnston (University of Michigan Ann Arbor), Volkan Seker (University of Michigan), Thomas J. Downar (University of Michigan)
Paper
Design and Safety Considerations for the Purification and Testing of Uranium-Bearing Molten Salts
Kristen Geddes (University of Idaho), Robin V. Roper (University of Idaho)
A Web Application to Visualize Advanced Fuel Cycle Waste Characteristics
Robert Stallman (Santa Clara University), Milos I. Atz (Argonne National Laboratory)
High Temperature Lead Cooled Fast Reactor for Advanced Drilling
Cole M. Kostelac (Missouri University of Science and Technology), Ashley R. Raster (Missouri University of Science and Technology), Matthew Resz (Missouri University of Science and Technology), Taylor D. Loftus (Missouri University of Science and Technology)
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