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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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
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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
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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.
T. Dash, B. B. Nayak, M. Abhangi, R. Makwana, S. Vala, S. Jakhar, C. V. S. Rao, T. K. Basu
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 241-247
Technical Paper | doi.org/10.13182/FST13-663
Articles are hosted by Taylor and Francis Online.
Because of their desirable structural properties, WC, WC+B4C, and WC + TiC are possible materials for use in plasma-facing components of fusion reactors like tokamaks. In this work, seven different compositions of WC-W2C composites have been prepared (30 to 50 at. % C) by an arc plasma melting technique followed by furnace cooling. Efforts have been made to produce a composite that is very hard and tough and that has a high neutron absorbing capacity by adding B4C and TiC (5 to 15 wt% each) to the starting WC powder. Microstructures of the composites were studied by field emission scanning electron microscopy and transmission electron microscopy. Multiphasic structures of the composites exhibited an absence of pores. The WC + TiC and WC + B4C composites showed improvements in microhardness over pure WC. Typical samples of WC-W2C, WC + B4C, and WC + TiC have been characterized by X-ray diffraction, X-ray photoelectron spectroscopy, and Brunauer-Emmett-Teller techniques for analysis and correlation of material properties. When irradiated with 14-MeV D-T neutrons, it was observed that the pure WC melt-cast product exhibited a linear neutron absorption coefficient of 0.172 cm−1. The absorption coefficient was found to be a maximum (0.255 cm−1) for 5 wt% B4C added to WC as against Type 316LN stainless steel, which showed a value of 0.078 cm−1.