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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
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
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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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.
Jinsuo Zhang, Shaoqiang Guo (Virginia Polytechnic Inst and State Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1029-1033
Molten salts have many applications in nuclear engineering, for example, pyroprocessing for used nuclear fuel treatment for which molten chloride salts are used, and molten salt rectors for which both chloride salt and molten fluoride salts are used. Materials corrosion is more challenging in these molten salt systems as the formation of the passivating oxide layer on the corrosion resistant alloys becomes thermodynamically less favorable. Materials corrosion in molten fluorides appears as bare alloy dissolution while the oxide layers formed in molten chlorides are typically porous, leading to the active metal dissolution in both molten fluoride and chloride salts. This restricts the use of many corrosion resistant alloys that rely on the passivating oxide layers. The present study conducted a critical review on materials corrosion in molten chloride and fluoride salts. The key environmental factors that influence corrosion in nuclear molten salt systems are discussed, including typical oxidants in the salt, fission product tellurium embrittlement, interactions with dissimilar materials, and temperature gradient. The historical development of corrosion resistant alloys for molten salt systems and recent attempts are also reviewed, and the effects of alloying elements and grain size were analyzed. One of the corrosion mitigation methods is to control the redox condition of the molten salt. Therefore, the study also analyzes the available redox control methods as well as the advantages and disadvantages of these methods. Finally, the current progress and challenges are summarized with an attempt at identifying the knowledge gaps and future research directions.