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Development of an electrochemical measurement method for carbon steels in radiation source dissolved solution and a corroded specimen analysis method using an imaging plate

Yamashita, Naoki; Aoyama, Takahito   ; Kato, Chiaki   ; Sano, Naruto; Tagami, Susumu

At the Fukushima Daiichi Nuclear Power Station (1F), which is currently undergoing decommissioning, there is growing interest in the effects of radiation-emitting radionuclides such as $$^{90}$$Sr and $$^{137}$$Cs on the structural integrity. In particular, the corrosion behavior of carbon steel, which is used in many parts of 1F, is known to change depending on metal cations in solution, but the effects of $$^{90}$$Sr and $$^{137}$$Cs on corrosion are not yet understood. In addition, it is important to investigate the distribution of $$^{90}$$Sr and $$^{137}$$Cs in the rust layer in order to understand the corrosion behavior, but the method has not yet been established. In this study, a glove box was prepared to conduct corrosion tests of carbon steel in NaCl containing $$^{90}$$Sr and $$^{137}$$Cs in the glove box. In addition, in order to clarify the influence of $$^{90}$$Sr and $$^{137}$$Cs, which exist as metal cations in the solution, on the corrosion behavior of carbon steel, we attempted to establish a detection method for radioactive materials in the rust layer using an imaging plate.

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