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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
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.