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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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Latest News
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.
R. G. Abrefah, P. A. A. Essel
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1245-1250
Technical Note | doi.org/10.1080/00295450.2019.1585736
Articles are hosted by Taylor and Francis Online.
The high-enriched-uranium core of the Ghana Research Reactor-1 has been removed and replaced by low-enriched-uranium fuel. Some components of the reactor that were not transported to China as part of the Chinese take-back program will be managed and stored in Ghana. The amount of decay heat and activity in these components were estimated using the ORIGEN-S code in order to select the best waste management option and to protect the personnel that will handle these components. The results obtained showed relatively low decay heat and activity in the reactor components that were considered in this study.
