HYDRATION AND MICROSTRUCTURE OF IRRADIATED CONCRETES

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  • 放射線を照射されたコンクリートの水和特性と微細構造

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This study aims to obtain basic knowledge of predicting the life of power reactors. To this end, biological shield concretes in Japan Power Demonstration Reactor (JPDR) exposed to radiations under long term operation was inspected in terms of hydration behavior and microstructure, and compared with model specimens cured under the same thermal conditions. Major findings are as follows, a. SEM observation showed that needle-like crystals in concrete exhibited greater development at the reactor core side than at the perimeter, and they had similar shapes to ettringite and C-S-H as observed in the model specimens. b. Bound water content of mortar was 5 % larger at the reactor core side than at the perimeter, whereas it was average 6.5 % larger in the model specimen. This tendency agrees well with the analysis of concrete in JPDR. c. Hydration products assigned by X-ray diffraction for the model specimens were monosulfate and calcium hydroxide, which were coincide with the analysis of concrete in JPDR. d. Pore size distribution of concrete showed larger amount of small pores at the reactor core side than at the perimeter. This tendency agrees well with the model specimens with a seal. e. Hydration and microstructure analysis of the model specimens supported the test results that the biological shield concrete undergoes no substantial changes.

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