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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
C. Hernandez, M. Naiim Habib, L. Doceul
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1029-1032
Contamination and Waste | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12591
Articles are hosted by Taylor and Francis Online.
The integration of laser techniques in an embedded system is studied in this paper to propose system able to perform tritium inventory (with in-line and on-line methods) and tritium removal (by ablation of layers or by tritium desorption) in a tokamak. Two complementary embedded systems are currently studied: a first innovative system which can be used between two plasma sessions (without tokamak pressure and temperature breaks) and a second system which can be used during maintenance phases (at atmospheric pressure). The two systems will be presented in this paper with their advantages and disadvantages.
