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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Shi-Chien Lin, Michiko Hamasaki, Yii-Der Chuang
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 237-250
Technical Paper | doi.org/10.13182/NSE79-A19061
Articles are hosted by Taylor and Francis Online.
We studied the dispersion and spheroidization treatment of zirconium hydride in reactor-grade zirconium alloys. Our aim was to find a workable way to improve the properties of Zircaloys. A scanning electron microscope was used to observe zirconium hydride precipitated in specimens of Zircaloy-2 and Zircaloy-4. We also examined hardness and corrosion before and after spheroidization in hydrogen. Experimental procedures and results can be summarized as follows. The specimens of low hydrogen concentration (<680 ppm) were hydrided at 420°C for 15 h, then cooled at a rate of <5 °C/min, and finally spheroidized at 520°C, just below the eutectoid temperature, for 20 to 72 h (the exact time required depending on the concentration of hydrogen). Successful spheroidization of zirconium hydride was obtained. The specimens of high hydrogen concentration (680 to 2210 ppm) were cycled near the eutectoid temperature, i.e., 547° C, for six to eight times and then annealed f or 30 to 128 h (the exact time depending on hydrogen concentration); finally, the specimens were slowly cooled at a rate of <5°C/min. It was found that for specimens with a hydrogen concentration ranging from 1000 to 2000 ppm, the heat treatment described above is satisfactory. But for specimens with a hydrogen concentration >2000 ppm, a heat treatment time >128 h at 520°C is required. The corrosion resistance of a spheroidized specimen was better than that of a specimen with platelet hydrides.