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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
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.