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Meeting 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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The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
T. M. Besmann, Y. Yamamoto, K. A. Unocic
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 181-191
Technical Paper | doi.org/10.13182/NT15-132
Articles are hosted by Taylor and Francis Online.
The thermochemical compatibility of potential replacement fuel rod cladding materials for zirconium alloys in light water reactors was assessed. Considered were the family of FeCrAl alloys, Nb-1%Zr (similar to PWC-11), and a hybrid SiC-composite with a metallic barrier layer. The niobium alloy was also seen as requiring an oxidation protective layer, and a diffusion silicide was investigated. Metallic barrier layers for the SiC-composite reviewed included an FeCrAl alloy, Nb-1%Zr, and chromium. Thermochemical calculations were performed to determine oxidation behavior of the materials in steam and for hybrid SiC-composites to determine possible interactions between the metallic layer and SiC. In addition, experimental exposures of SiC-FeCrAl alloy reaction couples at 673, 1073, and 1273 K for 168 h in an inert atmosphere were made, and microanalysis was performed. Whereas all materials were determined to oxidize under higher oxygen partial pressures in the steam environment, these varied by material. The computed and experimental results indicate the formation of liquid phase eutectic in the FeCrAl-SiC system at the higher temperatures.