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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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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.
E.U. Bashlakova, V.V. Ignatiev, S.V. Kirillov, V.M. Novikov, A.V. Puzirev
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 620-626
Advanced Fission Reactors | doi.org/10.13182/FST91-A11946908
Articles are hosted by Taylor and Francis Online.
In providing nuclear power plant safety the priority is currently given to reactor self-protection by means of inherent features and passive means. The problems of self-protection for molten-salt fuel reactor (MSR) and molten-salt cooled coated particle fuel graphite reactor (HTMSR) have been studied. The following ways to reach a high level of self-protection are investigated: a) high level of natural circulation (100% for MSR and 10% for HTMSR); b) integrated layout; c) minimization of reactivity changes during fuel burn-up; d) decrease of maximum operative temperature. Calculations of transient processes during heavy accidents without scram are presented. It is shown that maximum temperatures of the primary circuit materials do not reach critical values under such accidents. For the high hypothetical case with the damage of the reactor and guard vessels in MSR the fission products yield from the fuel salt into gas-phase of MSR containment is investigated.
