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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

*; *; *; *; *

PNC-TJ1074 98-002, 270 Pages, 1998/02

PNC-TJ1074-98-002.pdf:16.72MB

None

JAEA Reports

None

; ; *; ; Takeda, Seiichiro

PNC-TN8410 97-425, 34 Pages, 1997/11

PNC-TN8410-97-425.pdf:1.01MB

None

JAEA Reports

None

; *; ; ; Takeda, Seiichiro

PNC-TN8410 97-104, 56 Pages, 1997/04

PNC-TN8410-97-104.pdf:2.1MB

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:7.12MB

None

JAEA Reports

None

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

Effects of temperature on the corrosion potential of stainless steel under $$gamma$$-ray irradiation

Sato, Tomonori; Kato, Chiaki; Ueno, Fumiyoshi

no journal, , 

The structural materials of the instruments used in Fukushima Daiichi Nuclear Power Station are exposed to the corrosive condition under the $$gamma$$-ray irradiation. In order to determine the effects of the temperature of water under $$gamma$$-ray irradiation on the corrosion potential of stainless steel, the measurements of the corrosion potential under $$gamma$$-ray irradiation condition was performed. The dissolved oxygen concentration was aerated condition in each temperature in this study. And the corrosive condition under the irradiation was evaluated by the water radiolysis calculation and the measurements of the included hydrogen peroxide in the water after the irradiation. As parameters, the temperature of water and the $$gamma$$-ray dose rate were changed. The major results are listed as follows; (1) The corrosion potentials rose about 400 mV by the $$gamma$$-ray irradiation in all temperature conditions. (2) The potential was low with higher temperature under irradiation with the aerated condition. It was assumed that the lower dissolved oxygen concentration with higher temperature will cause the dependency of the corrosion potential on the temperature under irradiation. (3) The generation of some ppm of hydrogen peroxide was confirmed by the measurements of hydrogen peroxide concentration. It was indicated that the increase of the corrosion potential by the irradiation was caused by the generation of the high concentration of hydrogen peroxide. (4) It was confirmed that the generation of hydrogen peroxide was lower in higher temperature condition due to the lower dissolved oxygen concentration in high temperature. It was indicated that lower potential in high temperature water was caused by not only lower dissolved oxygen but also lower generation of hydrogen peroxide.

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