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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.
Yeon Soo Kim, Gerard L. Hofman, James L. Snelgrove
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 18-24
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3686
Articles are hosted by Taylor and Francis Online.
Fission gas release and fuel expansion of irradiated uranium-zirconium hydride fuel were measured during fuel heating to melting. The first indication of melting occurred at approximately the uranium-cladding eutectic temperature, whereas complete melting took place at the U metal melting point. Fission gas release began with the onset of uranium-cladding melting and gradually increased with rising temperature. Two sharp peaks in the fission gas release were observed corresponding to the events of uranium-zirconium eutectic melting and uranium melting. The fractional release was much higher than that measured previously for fuel without cladding at comparable temperatures.
