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Sato, Tomonori; Hata, Kuniki; Kaji, Yoshiyuki; Ueno, Fumiyoshi; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; et al.
JAEA-Review 2021-001, 123 Pages, 2021/06
JAEA-Review-2021-001.pdf:10.33MB
In the implement of the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), there are many problems to be solved. Specially, the mitigation of the aging degradation by the corrosion of the structural materials is important to implement the decommissioning safely and continuously. However, there are limited data for the environmental factors of corrosion in 1F, and the condition of 1F is continuously changing. So, the literature data for the water radiolysis and the corrosion under irradiation are listed as the database of corrosion under irradiation in this report. And the new obtained radiolysis and corrosion data, which have not been reported in the literature and will be required in the decommissioning of 1F, are reported.
Omori, Atsushi*; Akiyama, Eiji*; Abe, Hiroshi*; Hata, Kuniki; Sato, Tomonori; Kaji, Yoshiyuki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; et al.
Zairyo To Kankyo, 69(4), p.107 - 111, 2020/04
To evaluate the effect of oxidants, which are formed by radiolysis of water under gamma ray irradiation, on the corrosion of a carbon steel in humid environment, ozone was introduced as a model oxidant in to humidity-controlled air at 50
C in a thermo-hygrostat chamber. Corrosion monitoring was performed by using an Atmospheric Corrosion Monitor-type (ACM) sensor consisting of a carbon steel anode and an Ag cathode. The output current of the ACM sensor was increased with the increase in relative humidity and it was obviously increased with the increase in the introduced ozone concentration at each relative humidity. The results indicate that ozone accelerates the corrosion of the carbon steel. The effect of ozone on the corrosion acceleration is attributed to the fast reduction reaction and fast dissolution reaction in to water compared to that of oxygen.
Sn demo poloidal coil(DPC-EX)Ando, Toshinari; Takahashi, Yoshikazu; Okuno, Kiyoshi; Tsuji, Hiroshi; Hiyama, Tadao; Nishi, Masataka; Tada, Eisuke; Yoshida, Kiyoshi; Koizumi, Norikiyo; Nakajima, Hideo; et al.
IEEE Transactions on Magnetics, 28(1), p.206 - 209, 1992/01
Times Cited Count：4 Percentile：47.74(Engineering, Electrical & Electronic)no abstracts in English
Sn demo poloidal coil(DPC-EX)Takahashi, Yoshikazu; Yoshida, Kiyoshi; Ando, Toshinari; Hiyama, Tadao; Tsuji, Hiroshi; Nishi, Masataka; Tada, Eisuke; Okuno, Kiyoshi; Koizumi, Koichi; Nakajima, Hideo; et al.
Cryogenics, 31, p.640 - 644, 1991/07
Times Cited Count：11 Percentile：64.45(Thermodynamics)no abstracts in English
Sn Demo Poloidal Coil(DPC-EX)Ando, Toshinari; Hiyama, Tadao; Tsuji, Hiroshi; Takahashi, Yoshikazu; Nishi, Masataka; Tada, Eisuke; Yoshida, Kiyoshi; Okuno, Kiyoshi; Koizumi, Koichi; Nakajima, Hideo; et al.
Fusion Technology 1990, p.243 - 247, 1991/00
no abstracts in English
Kato, Takashi; Tada, Eisuke; Hiyama, Tadao; Kawano, Katsumi; *; *; *; *; Shimamoto, Susumi
Fusion Technology 1990, p.1535 - 1539, 1991/00
no abstracts in English
Tada, Eisuke; Kato, Takashi; Hiyama, Tadao; Kawano, Katsumi; Ando, Toshinari; Tsuji, Hiroshi; Takahashi, Yoshikazu; Nishi, Masataka; Yoshida, Kiyoshi; Okuno, Kiyoshi; et al.
Proc. of the 11th Int. Conf. on Magnet Technology, p.830 - 834, 1990/00
no abstracts in English
Okuno, Kiyoshi; Tsuji, Hiroshi; Takahashi, Yoshikazu; Nakajima, Hideo; Kato, Takashi; Isono, Takaaki; Ando, Toshinari; Hiyama, Tadao; Nishi, Masataka; Tada, Eisuke; et al.
Proc. of the IEEE 13th Symp. on Fusion Engineering, p.776 - 779, 1989/00
no abstracts in English
Uchida, Hiroki*; Tada, Eiji*; Tsuru, Toru*; Ishijima, Yasuhiro; Ueno, Fumiyoshi; Yamamoto, Masahiro; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*
no journal, ,
no abstracts in English
Ishijima, Yasuhiro; Motooka, Takafumi; Ueno, Fumiyoshi; Yamamoto, Masahiro; Uchiyama, Gunzo; Sakai, Junichi*; Yokoyama, Kenichi*; Tada, Eiji*; Tsuru, Toru*; Nojima, Yasuo*; et al.
no journal, ,
Titanium and Ti-5mass%Ta alloy has been utilized in nuclear fuel reprocessing plant material because of its superior corrosion resistance in nitric acid solutions. However, Ti alloy have been known to high susceptibility of hydrogen embrittlement. To evaluate properties of hydrogen absorption and hydrogen embrittlement of Ti alloys, cathodic polarization tests and slow strain rate tests (SSRT) under cathodic polarization were carried out. Results show titanium hydrides covered on the surface of metals and hydrides thickness were within 
m. Ti and Ti-5%Ta did not show hydrogen embrittlement by SSRT under cathodic charging. These results suggested that Ti and Ti-5%Ta could absorb hydrogen. But hydrogen did not penetrate inner portion of the metals more than m in depth because titanium hydrides act as barrier of hydrogen diffusion. It is considered that retardation of hydrogen diffusion hindered hydrogen embrittlement of Ti and Ti-5%Ta alloys.
Ishikawa, Hiroki*; Tada, Eiji*; Nishikata, Atsushi*; Taniguchi, Naoki; Tachikawa, Hirokazu*
no journal, ,
In current concept of geological disposal of high-level radioactive waste, the vittrified wastes are stored in metallic container which is called overpack, and then disposed in deep underground. Similarly in direct disposal of spent nuclear fuel, the fuel assemblies are disposed in deep underground contained in metallic disposal container. In order to ensure the long term integrity and safety of overpack or disposal container, corrosion monitoring was performed using electrochemical impedance spectroscopy (EIS) technique.
Kaji, Yoshiyuki; Sato, Tomonori; Hata, Kuniki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
Risk of corrosion degradation for plant materials in Fukushima-Daiichi Nuclear Power Plant (1F) site have been increasing with time duration and/or environmental changes by decommissioning procedure. We will build the corrosion and radiolysis database in irradiated condition including estimating data area for 1F corrosion in this project. In this presentation, we will describe summary of this project.
Kaji, Yoshiyuki; Sato, Tomonori; Hata, Kuniki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
Since risk of corrosion degradation for plant materials in Fukushima Daiichi Power Plant (1F) site have been increasing with time duration and/or environmental changes by decommissioning procedure, we will build a corrosion and radiolysis database in irradiated condition including estimating data area for 1F corrosion. In this presentation, we will describe the overview of this research project.
Hata, Kuniki; Sato, Tomonori; Kaji, Yoshiyuki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
no abstracts in English
Kaji, Yoshiyuki; Sato, Tomonori; Hata, Kuniki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
Since risk of corrosion degradation for plant materials in Fukushima-Daiichi Power Plant (1F) site have been increasing with time duration and/or environmental changes by decommissioning procedure, we will build a corrosion and radiolysis database in irradiated condition including estimating data area for 1F corrosion. In this presentation, we describe the overview of this project.
Sato, Tomonori; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Inoue, Hiroyuki*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*; Hata, Kuniki; Kaji, Yoshiyuki
no journal, ,
To develop the database for the corrosion under irradiation, the experimental evaluation for the corrosion under irradiation is necessary. So, the corrosion test environment under irradiation with controlling pH, temperature dissolved O
concentration and ion concentration was constructed in Takasaki Research center, QST. And, influence of gamma irradiation on de-passivation of carbon steel was evaluated. The map for corrosion property of carbon steel in the borate and chloride ions containing water was created based on the experimental data. The corrosion behavior changes with the concentration of borate.
Hata, Kuniki; Sato, Tomonori; Kaji, Yoshiyuki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
no abstracts in English
Kaji, Yoshiyuki; Sato, Tomonori; Hata, Kuniki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*; Suzuki, Shunichi*
no journal, ,
Since risk of corrosion degradation for plant materials in Fukushima-Daiichi Power Plant (1F) site have been increasing with time duration and/or environmental changes by decommissioning procedure, we will build a corrosion and radiolysis database in irradiated condition including estimating data area for 1F corrosion. In this presentation, we describe the overview of this project in 2018 fiscal year.
Sato, Tomonori; Hata, Kuniki; Kaji, Yoshiyuki; Inoue, Hiroyuki*; Taguchi, Mitsumasa*; Seito, Hajime*; Tada, Eiji*; Abe, Hiroshi*; Akiyama, Eiji*
no journal, ,
Water radiolysis calculations were performed to evaluate corrosion environments under irradiation by using database of corrosion under irradiation. It was confirmed that the dissolved oxygen is one of major factors to determine the generation of hydrogen peroxide, and the concentration of hydrogen peroxide could be controlled by the control of dissolved oxygen concentration. As a result of the calculation for the water radiolysis including impurities, the effects of Cl
on water radiolysis is negligible at concentration less than 10
mol/L. The effects of Br is negligible at concentration less than 10
mol/L. The effects of HCO is negligible at concentration less than 10
mol/L.
