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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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.
L. H. Johnson, K. I. Burns, H. H. Joling, C. J. Moore
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 470-475
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33273
Articles are hosted by Taylor and Francis Online.
The relationship between the quantity of iodine and cesium present in the fuel-sheath gap region and the amount of stable fission gas released from the fuel matrix has been investigated for typical natural UO2 Canada deuterium uranium power reactor fuels. Two leaching techniques were employed to determine the fuel-sheath gap inventories of cesium and iodine, and their respective release fractions were derived from these. The I37Cs/Xe and 134Cs/Xe release ratios were close to one over nearly three orders of magnitude of release fraction. Limited data suggest that 129I may show similar behavior. The experiments were performed in support of the safety assessment of irradiated fuel disposal and may have further application to fuel storage and reactor safety studies.
