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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
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.
M. Ogawa, K. Sanetoshi, T. Harada, K. Imai
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 719-722
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-A25219
Articles are hosted by Taylor and Francis Online.
Hydrogen depth profiles have been measured for stainless steel pre-irradiated with 10 keV helium ions with fluences close to the critical fluence, Fc. The hydrogen retention was stable with time at room temperature for the fluence above Fc. The retention was composed of the decay and stable components for the fluence below Fc. The annealing up to 400 °C indicated the same release behavior for the fluences below and above Fc.
