A Project focusing on the contamination mechanism of concrete after the accident at Fukushima Daiichi Nuclear Power Plant

Yamada, Kazuo*; Maruyama, Ippei*; Haga, Kazuko*; Igarashi, Go*; Aihara, Haruka; Tomita, Sayuri*; Kiran, R.*; Osawa, Norihisa*; Shibata, Atsuhiro; Shibuya, Kazutoshi*; et al.

Proceedings of International Waste Management Symposia 2021 (WM 2021) (CD-ROM), 10 Pages, 2021/03

Cement solidification test for incinerated ash, 1; Fundamental solidification characteristics of incinerated ashes

Kawato, Yoshimi; Tomioka, Osamu; Takahashi, Kuniaki; Meguro, Yoshihiro; Sakamoto, Hiroyuki*; Haga, Kazuko*

JAEA-Technology 2010-013, 38 Pages, 2010/07

JAEA-Technology-2010-013.pdf:1.36MB

It is important to understand fundamental solidification characteristics of incinerated ashes of combustible and poorly combustible wastes generated by JAEA. Simulated solidified substances using incinerator fly ash were prepared under different conditions such as solidified materials, ash filling rates, amount of solidification retarders and so on. The compressive strength of the solidified substances prepared using a normal portland cement (OPC), a blast furnace slag cement (BB), and a low alkalinity cement (LAC) exceeded a standard value, 1.47 N/mm. The compressive strength made from the BB was lower 1.47 N/mm when the filling rate of the incinerated ash was 40%. For the substances using the LAC, all the strengths were over 1.47 N/mm. Pb and Zn would behave as retardative substances for solidification. All substances showed the compressive strength with the BB or the LAC. As insolubilizers for heavy metals, ferrous sulfate and sodium sulfide prevented Cr from elution.

Study of cement solidification for incinerated ash, 1; Stabilization of heavy metals in cement solidified material

Tomioka, Osamu; Kawato, Yoshimi; Meguro, Yoshihiro; Haga, Kazuko*; Sakamoto, Hiroyuki*

no journal, , 

no abstracts in English

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 5; Gamma-ray irradiation test on solidified body of cement and Alkali Activated Material

Taniguchi, Takumi; Imaizumi, Ken*; Namiki, Masahiro*; Osugi, Takeshi; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*

no journal, , 

It is important to understand fundamental solidification characteristics of contaminated water management waste at Fukushima Daiichi Nuclear Power Station. The Solidified bodies are fabricated with cementitious material and Alkali Activated Material, and are irradiated with Gamma-ray.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 3; Outline of characteristics evaluation study on solidified body of cement and Alkali Activated Material

Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Shibata, Masahito*; Haga, Kazuko*; Taniguchi, Takumi; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Summary of the study which is for characterization of Solidified cement and alkali activated materials was carried out due to obtain the data available for applicability evaluation low-temperature solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 9; Synthesis of simulated carbonate slurry

Nakashio, Nobuyuki*; Kawasoe, Takahiro*; Aikawa, Kohei*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Simulated carbonate slurry was synthesized to obtain basic data for the low temperature processing of the waste generated from contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 11; Dissolution test of solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Osawa, Norihisa*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kawato, Takaya*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated material blending carbonated slurry were prepared and their dissolution tests were carried out in order to obtain basic data for the low temperature processing of the waste generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.

Study on the radionuclide contamination mechanisms of concrete and the estimation of distribution of radionuclides, 10; Modeling of penetration behavior of Cs and Sr into concrete at turbine building basement of Fukushima Daiichi Nuclear Power Station

Tomita, Sayuri*; Kobayashi, Yutaro*; Haga, Kazuko*; Hosokawa, Yoshifumi*; Yamada, Kazuo*; Aihara, Haruka; Igarashi, Go*; Maruyama, Ippei*

no journal, , 

no abstracts in English

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 18; Leachability of nuclides from solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 23; Interaction between Iron Slurry and Alkali Activated Materials

Raudhatul Islam, C.*; Kobayashi, Yutaro*; Haga, Kazuko*; Kaneda, Yoshihisa*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Sato, Tsutomu*

no journal, ,