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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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August 2025
Latest News
Schulz Electric™ Refurbishes Critical Circulating Water Pump Motor in Only Four Days
Schulz Electric™ was contacted by a nuclear power plant in the New England region that serves a community of over 2 million homes. After five years of service, a 1500 HP, 4 kV, 24-pole circulating water pump motor (measuring approximately 7’ wide, 8’ tall, and weighing several tons) needed refurbishing while the plant was still online. To add to their concern, the power plant is located close to the ocean. The aging motor was not only approaching the end of its serviceable life, but was highly susceptible to moisture intrusion and the salt-laden air, which can build up in air passages within the motor. These environmental conditions can lead to elevated operating temperatures and corrosion developing on the rotor, stator, and shaft components. These factors combined, placed the plant at an increased risk of downtime that could have potentially led to a significant loss of revenue if they were forced into a shutdown event.
A. Bruggeman, M. Snykers, P. De Regge, M.J. Embrechts
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 828-832
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25237
Articles are hosted by Taylor and Francis Online.
In the Aqueous Self-Cooled Blanket (ASCB) concept, an aqueous 6Li solution in a metallic structure is used as a fusion reactor shielding-breeding blanket. Radiolysis effects could be very important for the design and the use of an ASCB. Although many aspects of the radiation chemistry of water and dilute aqueous solutions are now reasonably well understood, it is not possible to predict the radiochemical behaviour of the concentrated candidate ASCB solutions quantitatively. However, by means of a worst case calculation for a possible ASCB for the Next European Torus (NET) it is shown that even with an important rate of water decomposition the ASCB concept is still workable. Gas bubbles and explosive mixtures can be avoided by increasing the pressure in the neutron irradiated zone and by extracting and/or recombining the radiolytically produced hydrogen and oxygen. This could require an additional inert gas loop, which could also be used as part of the tritium extraction installation.
