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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.
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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Nuclear Science and Engineering
Fusion Science and Technology
Donalds, Barnard call for streamlining NRC’s regulatory process
“To be frank, any emissions-related climate goals are moonshots without nuclear energy, and next-generation nuclear technology is something that the United States can and SHOULD lead on.” So writes U.S. Rep. Byron Donalds (R., Fla.) and Christopher Barnard, vice president of external affairs for the American Conservation Coalition, in an essay published by RealClear Energy.
Good news: Donalds, one of the strongest advocates for nuclear energy in the U.S. House, and Barnard, publisher and coauthor of Green Market Revolution, begin their essay by noting some recent positive developments for nuclear power. They characterize the initial criticality of Vogtle-3, the first new nuclear reactor built in the United States in about 30 years, as “a monumental achievement for the American nuclear industry.” They praise the Biden administration’s allocation of funds to keep established nuclear plants operational.
Technical Session|Sponsored by NNPD
Tuesday, June 14, 2022|1:00–2:45PM PDT|Avila A
R. A. Borrelli
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Preliminary Results of MIT Reactor HEU-LEU Mixed Core Fuel Conversion Analysis Using RELAP5 Code
Yinjie Zhao (MIT), Lin-Wen Hu (MIT), Erik Wilson (ANL), Yu-Jou Wang (MIT)
Impact of LEU U-10Mo Fuel Impurities on the Massachusetts Institute of Technology Reactor's Neutronics Performance
Valerio Mascolino (ANL), Laura M. Jamison (ANL), Wilson M. Cowherd (ANL), Kyle E. Anderson (ANL), John A. Stillman (ANL), Lin-wen Hu (MIT), Erik H. Wilson (ANL)
Fuzzy Logic Method for Trend Identification in Radiation Measurements Taken with a Mobile Detector with Application to Nuclear Security
Michael Squire (Univ. Texas, San Antonio), Miltiadis Alamaniotis (Univ. Texas, San Antonio)
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