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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.
K. Linga Murty
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 124-131
Technical Paper | Material | doi.org/10.13182/NT84-A33535
Articles are hosted by Taylor and Francis Online.
Improvements in both the yield strength and ductility were noted in mild steel at elevated temperatures (≳315 K) following neutron irradiation to 2 × 1022 n/m2, in contrast to hitherto observed radiation hardening and embrittlement. This beneficial effect was shown to be due to the interaction of interstitial impurities with radiation-produced defects resulting in reduced concentration of interstitial carbon and nitrogen in solution, and thus blue brittleness is suppressed following radiation exposure. Consequently, the energy absorbed by the irradiated material (a measure of toughness) improved at these temperatures. In the temperature range examined, namely from 300 to 550 K, Lüders strain increased following neutron irradiation. While the Lüders strain of unirradiated material exhibited a peak at ∼460 K due to dynamic strain aging, it decreased continuously with test temperature following neutron irradiation. Radiation exposure resulted in decreased rates of work hardening at all of the test temperatures. Peaks in the temperature dependence of the work-hardening parameter are noted for the unirradiated material in the serrated flow regime. Thermal recovery of radiation damage resulted in increased rates of work hardening at elevated temperatures.
