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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.
W. J. O'Donnell, B. F. Langer
Nuclear Science and Engineering | Volume 20 | Number 1 | September 1964 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE64-A19269
Articles are hosted by Taylor and Francis Online.
General methods have recently been developed for low-cycle fatigue design. The required basic strain-controlled data for both unirradiated and irradiated Zircaloy–2, −3, and −4 were obtained for temperatures between 70 F and 600 F. Data include both rolled and base-annealed material, and as-welded material tested in various directions. The “cyclic” stress-strain properties of these materials were also obtained and were found to differ quite significantly from the conventional properties. Using the cyclic properties in a Modified Goodman Diagram, fatigue-failure curves were developed which included the deleterious effect of the maximum possible mean stress that can exist in the material as it is cycled. Limited available test data confirm the validity of this method. Using the resulting curves, one need only consider the cyclic stress loads. The worst possible effects of residual stresses due to welding and other fabrication methods, and mean stresses due to differential thermal expansion are included in the curves. The phenomenon of fuel growth introduces a monotonically increasing strain which accompanies the cyclic strain. The effects of such a gradually accumulating increment of strain were investigated and were found to be adequately covered by the adjustment for maximum mean stress. Design curves were constructed from the mean failure curves by applying approximate factors to cover the effects of size, environment, surface finish and scatter of data. The results of fatigue tests on notched irradiated Zircaloy indicate that this material is somewhat less notch sensitive than 100 000-lb/in.2 tensile strength steel. Unirradiated Zircaloy is even less notch sensitive. However, fatigue tests on notched weld metal indicate considerably greater notch sensitivity.