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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Fusion Science and Technology
August 2025
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The newest era of workforce development at ANS
As most attendees of this year’s ANS Annual Conference left breakfast in the Grand Ballroom of the Chicago Downtown Marriott to sit in on presentations covering everything from career pathways in fusion to recently digitized archival nuclear films, 40 of them made their way to the hotel’s fifth floor to take part in the second offering of Nuclear 101, a newly designed certification course that seeks to give professionals who are in or adjacent to the industry an in-depth understanding of the essentials of nuclear energy and engineering from some of the field’s leading experts.
Y. Oka, S. Koshizuka, S. Kondo
Fusion Science and Technology | Volume 16 | Number 2 | September 1989 | Pages 260-262
Technical Note | doi.org/10.13182/FST89-A29159
Articles are hosted by Taylor and Francis Online.
Conceptual design of an electrochemically induced deuterium-tritium fusion power reactor has been carried out. A double-tube-type fuel cell is proposed for efficient electrolysis and to provide a large cathode area. The fuel cell tubes are assembled like a pressurized water reactor (PWR) control rod cluster. The tritium fuel is continuously fed through the cluster rod to the cell. The voltage for the electrolysis is supplied through the rod. The tritium breeding Li2O is contained in a hexagonal blanket through which coolant tubes penetrate. The fuel cell tube is inserted in the coolant tube and the water coolant flows through the annuli. The tritium is continuously recovered from the blanket by using helium gas. The blanket assemblies are contained in the pressure vessel. The tubes of the helium gas and the cluster rods penetrate through the upper dome of the vessel. The shape of the reactor and the coolant system are similar to those of PWRs. The vessel is somewhat squat, because the height of the blanket is approximately half that of a PWR core.