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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
Toshihisa Hatano, Kazuyoshi Sato, Masayuki Dairaku, Toshimasa Kuroda, Masanori Araki, Hideyuki Takatsu, Satoshi Sato, Kiyoshi Fukaya, Toshimasa Kurasawa, Ikuhide Tokami, Masato Akiba
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 752-756
Plasma-Facing Components: Analysis and Technology | doi.org/10.13182/FST96-A11963025
Articles are hosted by Taylor and Francis Online.
A shielding blanket design in a fusion reactor such as ITER (International Thermonuclear Experimental Reactor) has been proposed to be a modular structure integrated with the first wall. In terms of the fabrication, HIP (Hot Isostatic Pressing) method has been proposed for the joining of dispersion strengthened copper (DS-Cu) and type 316L stainless steel (SS316L) at FW. High heat flux tests of HIP bonded DS-Cu/SS316L first wall panel were performed at Particle Beam Engineering Facility in JAERI to investigate its thermo-mechanical performance. They consisted of four test campaigns. The former two campaigns simulated ITER normal operation conditions in terms of the temperature and strain at the HIP bonded interfaces between DS-Cu and SS316L, respectively. The latter two simulated disruption conditions. Under normal heat flux conditions, temperature responses of the first wall panel measured by the thermocouples agreed very well with those predicted by FEM analyses. On the other hand, ejection of a number of small particles from DS-Cu surface was observed during the last campaign with the high heat flux simulating disruptions.
