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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.
M. Coquerelle, C. T. Walker
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 43-53
Technical Paper | Fuel | doi.org/10.13182/NT80-A32446
Articles are hosted by Taylor and Francis Online.
Mixed carbide, carbonitride, and nitride fuels have been irradiated in DFR and Rapsodie to a maximum burnup of 7.8 at.% at a maximum linear power of 135 kW·m−1. At low burnup, xenon release from helium-bonded fuels was found to be dependent on the chemical composition of the fuel Release was greatest from carbide (75%) and least from nitride fuels (35%). At medium burnup, improved gap conductance led to a fall in the fuel centerline temperature and consequently a decrease in gas release. For nitride and carbonitride fuels, over 75% of the retained fission gas was contained in bubbles (<1 µm in diameter) and in the fuel matrix. For all three fuels, xenon release from the outer unrestructured region of the fuel was <15%, whereas release from the central porous region was 50% or more. In the restructured region, gas was released to the plenum by way of interconnected pores. Gas in pores contained proportionally more krypton than the bonded gas, and consequently, it is proposed that atomic diffusion is the principal mechanism of gas transport within the fuel.
