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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.
Luciano Burgazzi
Nuclear Technology | Volume 173 | Number 2 | February 2011 | Pages 153-161
Technical Paper | Reactor Safety | doi.org/10.13182/NT11-A11544
Articles are hosted by Taylor and Francis Online.
This paper describes a modeling and analysis approach for reliability prediction based on degradation modeling, considering multiple degradation measures and with respect to the thermal-hydraulic passive systems.Previous research on the topic has drawn attention to the susceptibility of passive systems to several modes of failure. In fact, it has been recognized that a system may have, in addition to component mechanism failures, multiple degradation paths, so it is necessary to simultaneously consider multiple degradation measures. Also, many research efforts on degradation analysis were initiated by making assumptions about the degradation mechanism. In reality, often there is very limited understanding about the concerned degradation mechanisms together with their interdependencies.In this paper, an analysis procedure is developed to address this aspect. Simulated data have been used to illustrate the applicability of this approach. Results on the application of the methods to a simplified model of the passive residual heat transport system in water-cooled reactors is presented. It was verified that when the multiple degradation measures in a system are correlated, an incorrect independence assumption may overestimate the system reliability.