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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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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.
Samuel J. Zenobia, Lauren M. Garrison, Gerald L. Kulcinski
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 344-348
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12377
Articles are hosted by Taylor and Francis Online.
Surface morphology changes of sub-micron tipped tungsten needles (W.N.) and an engineered fine-grain tungsten (FGW) were studied after implantation with He ions at reactor relevant conditions. Surface and subsurface pore formation was observed on all of the samples by using scanning electron microscopy (SEM) and focused ion beam (FIB) milling. Additionally, helium retention analysis was performed on the FGW and compared to several previously studied W materials.Three samples of FGW were irradiated with 30 keV 3He ions to 3×1017 He+/cm2 at 700 °C, 9×1017 He+/cm2 at 850 °C, and 1×1019 He+/cm2 at 1050 °C. SEM analysis revealed that the threshold for visible pore formation was below ~1018 He+/cm2. The sample irradiated to the highest fluence showed “coral-like” morphology on the surface, and FIB analysis showed that the sub-surface semi-porous layer extended almost one micron below the surface. The percentage of implanted helium retained in the samples ranged from 4.5-40%.Two W.N. were implanted with 100 keV 4He ions to conditions of 3×1018 He+/cm2 at 700 °C and 1.3x1019 He+/cm2 at 1000 °C. Extensive pore formation was observed on both specimens. FIB analysis revealed that a sub-surface semi-porous layer developed after ion implantation that extended ~300 nm in the W.N. implanted to the lower dose, and over 1500 nm in the needle implanted to the higher dose. This second needle also exhibited a drastic morphology change, which appears to be a result of the unraveling of the grains at the tip.
