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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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Nuclear energy for maritime shipping and coastal applications
The Boston-based Deon Policy Institute has published a white paper that examines the applications of nuclear energy in the maritime sector—specifically, floating nuclear power plants and nuclear propulsion for commercial vessels. Topics covered include available technologies, preliminary cost estimates, and a status update on the regulatory framework.
Unique opportunity: The paper points out that nuclear energy has the potential to benefit the shipping industry with high energy efficiency, lower operating costs, and zero carbon emissions. The report has a special focus on Greece, a nation that controls about 20 percent of the global commercial fleet and thus has an opportunity to take a leading role in the transition to nuclear-powered shipping.
Belle R. Upadhyaya, Malgorzata Skorska
Nuclear Technology | Volume 64 | Number 1 | January 1984 | Pages 70-77
Technical Paper | Technique | doi.org/10.13182/NT84-A33327
Articles are hosted by Taylor and Francis Online.
Instrument fault detection and estimation is important for process surveillance, control, and safety functions of a power plant. The method incorporates the dual-hypotheses decision procedure and system characterization using data-driven time-domain models of signals representing the system. The multivariate models can be developed on-line and can be adapted to changing system conditions. For the method to be effective, specific subsystems of pressurized water reactors were considered, and signal selection was made such that a strong causal relationship exists among the measured variables. The technique is applied to the reactor core subsystem of the loss-of-fluid test reactor using in-core neutron detector and core-exit thermocouple signals. Thermocouple anomalies such as bias error, noise error, and slow drift in the sensor are detected and estimated using appropriate measurement models.