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Journal Articles

Effect of dissolved $$^{90}$$Sr and $$^{137}$$Cs in HCl solutions on the corrosion potential of Type 316L stainless steel

Aoyama, Takahito; Sato, Tomonori; Ueno, Fumiyoshi; Kato, Chiaki; Sano, Naruto; Yamashita, Naoki; Igarashi, Takahiro

Zairyo To Kankyo, 72(11), p.284 - 288, 2023/11

no abstracts in English

Journal Articles

Study on the free corrosion potential at an interface between an Al electrode and an acidic aqueous NaCl solution through density functional theory combined with the reference interaction site model

Kano, Koichi*; Hagiwara, Satoshi*; Igarashi, Takahiro; Otani, Minoru*

Electrochimica Acta, 377, p.138121_1 - 138121_10, 2021/05

AA2020-0599.pdf:0.95MB

 Times Cited Count:17 Percentile:68.84(Electrochemistry)

We investigated the free corrosion potential at an interface between an Al electrode and an aqueous NaCl solution under acidic conditions via density functional theory combined with the effective screening medium and reference interaction site model (ESM-RISM). The electrode potentials for the anodic and cathodic corrosion reactions were obtained from the grand potential profile as a function of the electron chemical potential at the interface. Thereafter, we determined the free corrosion potential using the Tafel extrapolation method. The results of the free corrosion potential were consistent with previous experimental data. By controlling the pH, we determined the pH dependence of the free corrosion potential, and the results agreed well with the experimental results. Our results indicated that the ESM-RISM method duly described the environmental effect of an acidic solution and precisely determined the free corrosion potential.

Journal Articles

IV. Electrochemical measurements in various environments; Nuclear power plant I (Electrochemical measurement in nuclear power plant)

Ueno, Fumiyoshi

Zairyo To Kankyo, 68(1), p.2 - 8, 2019/01

It is important to control the cooling water of light water reactors (boiling water reactor and pressurized water reactor) to suitable quality in order to reduce corrosion of structural materials and generation of radioactive corrosion products. For that purpose, monitoring of water quality using electrochemical measurement method is necessary. In this article, the application of ECP measurement to BWR is mainly focused, I describe the water quality of light water reactors and the necessity of electrochemical measurement.

Journal Articles

Evaluation of ECP measured in in-pile environment

Hanawa, Satoshi; Uchida, Shunsuke; Hata, Kuniki; Chimi, Yasuhiro; Kasahara, Shigeki*; Nishiyama, Yutaka

Proceedings of 20th Nuclear Plant Chemistry International Conference (NPC 2016) (USB Flash Drive), 11 Pages, 2016/10

ECP is the exclusive index to evaluate corrosion condition directly at the points of interest in the mixing of neutron and $$gamma$$-ray environment. ECP can be calculated through the combination of water radiolysis and ECP model. A water radiolysis model have been applied to experiments performed in in-pile loops in the experimental reactors and applicability was confirmed. An ECP model based on the Butler-Volmer equation was also prepared. ECP of stainless steel was measured under well controlled water chemistry condition in in-pile loop in the Halden reactor, and the model was applied to evaluate ECP measured in the Halden reactor. The measured data were well explained by the water radiolysis calculation and ECP model. Accumulation of in-pile ECP data are expected for further validation of the models.

Journal Articles

Effect of zeolites on the corrosion potential of type 316L stainless steel in diluted artificial sea water under gamma-ray irradiation

Kato, Chiaki; Sato, Tomonori; Ueno, Fumiyoshi; Yamagishi, Isao; Yamamoto, Masahiro

Zairyo To Kankyo 2015 Koenshu (CD-ROM), p.83 - 86, 2015/05

In relation to the consideration for long-term storage of spent Cs adsorption vessels containing zeolites in the Fukushima Daiichi Nuclear Power Station, corrosion of the vessel material in the spent Cs adsorption vessel is one of important issues. We performed electrochemical tests of stainless steel (SUS 316L) in the zeolites containing artificial seawater under gamma-ray irradiation. The spontaneous potential (ESP) and critical pitting potential (VC), of SUS316L were measured to understand the corrosion resistance of the stainless steel in this study. The rest potential of the stainless steel increased with increasing time after gamma-ray irradiation. The ESP, defined as the steady rest potential, increased with increasing dose rate, while increasing ESP was suppressed by contact with the zeolites. Concentration of H$$_{2}$$O$$_{2}$$ in bulk water increased with increasing dose rate. The concentration increasing was suppressed by contact with the zeolites due to decomposition of H$$_{2}$$O$$_{2}$$. There was good relationship between ESP and the concentration of H$$_{2}$$O$$_{2}$$. The VC of SUS316L contacted with the zeolites decreased with increasing Cl$$^{-}$$ ion concentration and is slightly smaller than the VC in the bulk water. The contact with the zeolites causes the suppressant of increasing ESP under the irradiation. The contact with the zeolites can reduce probability in the localized corrosion for SUS316L.

Journal Articles

In-core ECP sensor designed for the IASCC experiments at JMTR

Tsukada, Takashi; Miwa, Yukio; Ugachi, Hirokazu; Matsui, Yoshinori; Itabashi, Yukio; Nagata, Nobuaki*; Dozaki, Koji*

Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems (CD-ROM), 5 Pages, 2004/10

IASCC initiation and propagation tests will be performed on the per-irradiated specimen in the Japan Materials Testing Reactor (JMTR). Since in core, the radiolysis of water causes a generation of various kind of radical species and some oxidizing species such as hydrogen peroxide, the water chemistry in irradiation capsules must be assessed by measurements of the electrochemical corrosion potential (ECP). For the in-core measurement of ECP in JMTR, we fabricated and tested the Fe/Fe$$_{3}$$O$$_{4}$$ type ECP sensor. After the fabrication, the function of each sensor was examined in high temperature water by out-of-core thermal cycling and high temperature holding tests.

JAEA Reports

None

Shimogori, Kazutoshi*; Tomari, Haruo*; ; Fujiwara, Kazuo*; Masugata, Tsuyoshi*

PNC TJ1074 98-002, 270 Pages, 1998/02

PNC-TJ1074-98-002.pdf:25.03MB

None

JAEA Reports

None

; ; ; ; Takeda, Seiichiro

PNC TN8410 97-425, 34 Pages, 1997/11

PNC-TN8410-97-425.pdf:0.97MB

None

JAEA Reports

None

; ; ; ; Takeda, Seiichiro

PNC TN8410 97-104, 56 Pages, 1997/04

PNC-TN8410-97-104.pdf:2.06MB

None

JAEA Reports

None

PNC TJ1150 96-005, 23 Pages, 1996/03

PNC-TJ1150-96-005.pdf:0.7MB

None

JAEA Reports

None

PNC TJ1150 96-004, 128 Pages, 1996/03

PNC-TJ1150-96-004.pdf:7.74MB

None

JAEA Reports

Study on redox potential and free corrosion potential for carbon steel in saturated bentonite

Ishikawajima-Harima Heavy Industries*

PNC TJ1150 94-001, 19 Pages, 1994/03

PNC-TJ1150-94-001.pdf:1.69MB

None

JAEA Reports

None

PNC TJ1560 93-001, 60 Pages, 1993/03

PNC-TJ1560-93-001.pdf:1.64MB

None

JAEA Reports

None

PNC TJ1150 92-003, 136 Pages, 1992/02

PNC-TJ1150-92-003.pdf:2.57MB

None

Oral presentation

Estimation of the corrosive environment induced by alpha-ray radiolysis

Hata, Kuniki; Sato, Tomonori; Kato, Chiaki; Sato, Nobuaki*

no journal, , 

no abstracts in English

Oral presentation

Detection of radioactive materials in carbon steel rust layer using imaging plate

Aoyama, Takahito; Sato, Tomonori; Ueno, Fumiyoshi; Kato, Chiaki; Sano, Naruto; Yamashita, Naoki; Igarashi, Takahiro

no journal, , 

no abstracts in English

Oral presentation

The Effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation, 11; Effects of oxide and hydrogen peroxide on anodic polarization curves and ECP

Uchida, Shunsuke; Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro; Sato, Tomonori

no journal, , 

In order to evaluate ECP, determination of anodic polarization curves as well as oxidant concentrations are the key issues. The anodic polarization curves could be determined as a function of material properties, temperature and pH. ECP used to be analyzed by applying observed anodic polarization curves both for O$$_{2}$$ and H$$_{2}$$O$$_{2}$$. For mixtures of both, a complex average curve based on the ratio of their cathoidic current densities was applied. A radiolysis and ECP combined code, WRAC-JAEA, applied only anodic polarization curve, which was added by the effects of oxidation current of H$$_{2}$$O$$_{2}$$. The procedures could determine FCP for the complex mixture based on theoretical anodic polarization curve of steel and H$$_{2}$$O$$_{2}$$ oxidation current density.

Oral presentation

Development of ECP analysis code for both BWR and PWR primary coolant loops

Hata, Kuniki; Uchida, Shunsuke*; Hanawa, Satoshi; Chimi, Yasuhiro; Sato, Tomonori

no journal, , 

no abstracts in English

Oral presentation

The Effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation, 1; Effects radiation quality and pH on water radiolysis

Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro; Uchida, Shunsuke

no journal, , 

no abstracts in English

Oral presentation

The Effects of hydrogen addition on the corrosive conditions of PWR primary coolant under irradiation, 2; Effects of oxide film and hydrogen on ECP

Uchida, Shunsuke; Hata, Kuniki; Hanawa, Satoshi; Chimi, Yasuhiro

no journal, , 

no abstracts in English

28 (Records 1-20 displayed on this page)