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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Contractor selected for Belgian LLW/ILW facility
Brussels-based construction group Besix announced that is has been chosen by the Belgian agency for radioactive waste management ONDRAF/NIRAS for construction of the country’s surface disposal facility for low- and intermediate-level short-lived nuclear waste in Dessel.
C. M. Hollabaugh, L. A. Wahman, R. D. Reiswig, R. W. White, P. Wagner
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 527-535
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31913
Articles are hosted by Taylor and Francis Online.
The experimentally determined quantitative effects of varying gas mixture composition on the properties of the zirconium carbide (ZrC) deposited on microspheres in a fluidized bed were a decrease in metallic appearance of the ZrC coat, with an increase in the ratio of the hydrocarbon gas to the ZrCl4 and co-deposition of carbon at high hydrocarbon gas concentrations. Increasing the H2 concentration inhibited these effects and permitted the ZrC to be deposited at higher hydrocarbon gas concentrations. Deposits of pure sub-stoichiometric ZrC coats were controllable over a limited concentration range. The ZrC was deposited in a fluidized bed of ThO2 particles at a maximum temperature of ∼1650 K, using gas mixtures of H2, argon, ZrCl4, and CH4 or C3H6. The ZrCl4 flow was controlled using a powder feeder.