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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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Technical Session
Tuesday, September 27, 2022|3:50–5:55PM PDT|Harbor
Session Chair:
Carmen Jacobs (South African Nuclear Energy Corporation)
Alternate Chair:
Robert E. Grove (ORNL)
Session Organizer:
Thomas M. Miller (ORNL)
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Proposal of New Structure for Duct Shielding in Radiation Therapy Room
3:50–4:15PM PDT
Sangrok Kim (Korea Institute of Radiological and Medical Sciences), Gisub Kim (Korea Institute of Radiological and Medical Sciences)
Paper
Attachment — Revised summary
On Publication of "A Handbook of Radiation Shielding" Supervised by the Shielding Research Committee of Atomic Energy Society of Japan
4:15–4:40PM PDT
Yoshihiro Hirao (National Maritime Research Institute), Yoshitomo Uwamino (Institute of Physical and Chemical Research)
Radiation Shielding for the Transportation of Radioactive Lutetium-177
4:40–5:05PM PDT
C. Jacobs (South African Nuclear Energy Corp.), E.M. Chinaka (South African Nuclear Energy Corp.), L. Bedhesi (South African Nuclear Energy Corp.)
MCNP Analysis for Dose Rate Measurements on Radioactive Waste Transportation Ship
5:05–5:30PM PDT
Kaori Yamagata (Mitsubishi Heavy Industries), Masashi Osaki (MHI NS Engineering Co.), Yu Sugimoto (MHI NS Engineering Co.)
Shielding Calculation of the Low- and Intermediate-Level Radioactive Waste Drum from a Nuclear Reactor Using Monte Carlo Codes
5:30–5:55PM PDT
Wenxuan Wang (Harbin Turbine Co.), Luis Fernando Salas-Tapia (Harbin Engineering Univ.), Xiang Wang (Harbin Engineering Univ.), Tian Zhang (Harbin Engineering Univ.)
Presentation Video (Visible to Attendees) — Presentation 39173
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