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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Jun-Ho Yeom et al.
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 945-948
Power Plants, Demo, and Next Steps | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9032
Articles are hosted by Taylor and Francis Online.
System analysis has been carried out for a finding of key design parameters of future DEMO. The tokamak plasma parameters, which determine plant core performance and engineering requirements are searched. In this analysis, the plasma configuration based on ITER along with several physical and engineering constraints, such as plasma shape and plasma current, are given as an input. With this given constraints, parameters such as major radius, normalized plasma beta, toroidal magnetic field are investigated to look for a design of DEMO plant. These analysis results also would be used as a guideline for the possible design of the magnet and blanket.
