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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Akira Shibata, Yoshiaki Kato, Taketoshi Taguchi, Masatoshi Futakawa, Katsuhiro Maekawa
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 89-99
Technical Paper | doi.org/10.13182/NT16-54
Articles are hosted by Taylor and Francis Online.
Zircaloy-4 has been widely used as a nuclear fuel cladding material. However, recently, several European countries have gradually replaced Zircaloy-4 cladding material in pressurized water reactor (PWR) nuclear power plants with a Zr-Nb alloy called M5 and other new zirconium alloys with Nb added that are expected to have relatively longer operating lives. Although improved corrosion resistance of the advanced zirconium alloys was demonstrated in various conditions, the origin of this resistance has not yet been elucidated. In this study, corrosion tests were performed on Zircaloy-4 and M5 under simulated PWR water conditions to explore the origin of the better corrosion resistance of the advanced zirconium alloys. Alloy specimens were exposed to simulated PWR conditions, and the increase in oxide film content was analyzed by weight gain and microscopy observations. Electrochemical impedance spectroscopy (EIS) was performed on Zircaloy-4 and M5 in the pretransition period of oxide film to compare their corrosion properties. The EIS results obtained in this study show that the electrochemical behavior of M5 is significantly different from that of Zircaloy-4 in the early period of the initial stage in the pretransition oxidation process. To explain the result, a multilayer circuit model is assumed. The resistance of the diffusion layer comprising multiple layers restricts the rate of oxidation in the M5 response system. The occurrence of this process caused by multilayered oxide film would contribute to improved corrosion resistance of M5 under PWR water conditions.