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Otani, Kyohei; Tsukada, Takashi; Ueno, Fumiyoshi
Zairyo To Kankyo, 68(8), p.205 - 211, 2019/08
In the present study, the iron rust layer formed on the low ally steel in air-solution alternating condition was investigated by cross-sectional observation and analysis, and the mechanism of accelerated corrosion of the steel in the alternating condition was clarified. Observation and analysis showed that the multi-layered iron rust layer composed of red rust layer (FeOOH), rust crust layer (Fe
O
), inner crystal (FeO), and inner rust layer was formed on the low alloy steel. It can be considered that the multi-layered iron rust layer accelerated the cathodic reaction rate of the steel in the alternating condition. This acceleration would be the reason why the corrosion rate of the low alloy steel in the alternating condition was accelerated.
Hasegawa, Masayuki*; Nagai, Yasuyoshi*; Tang, Z.*; Yubuta, Kunio*; Suzuki, Masahide
JAERI-Tech 2003-015, 137 Pages, 2003/03
JAERI-Tech-2003-015.pdf:9.03MB
no abstracts in English
Ara, Katsuyuki*; Ebine, Noriya
Denki Gakkai Magunetikkusu Kenkyukai Shiryo (MAG-01-55), p.1 - 6, 2001/03
no abstracts in English
; Ara, Katsuyuki;
Proc. of 9th Int. Symp. on Reactor Dosimetry, 0, p.785 - 792, 1998/00
no abstracts in English
; ; ;
JAERI-M 85-170, 36 Pages, 1985/10
no abstracts in English
; ; ; ;
Nucl.Eng.Des., 85, p.1 - 13, 1985/00
Times Cited Count：4 Percentile：54.56(Nuclear Science & Technology)no abstracts in English
Kondo, Tatsuo; Ogawa, Yutaka; Nakajima, Hajime
Corrosion Problems in Energy Conversion and Generation, p.346 - 358, 1974/00
no abstracts in English
;
Genshiryoku Kogyo, 19(12), p.53 - 58, 1973/12
no abstracts in English
; ; *; *
JAERI-M 5297, 40 Pages, 1973/06
no abstracts in English
rays irradiation, 3; Effects on depth of localized corrosionNakano, Junichi; Tsukada, Takashi; Ueno, Fumiyoshi; Yamagata, Ryohei
no journal, ,
In the Fukushima Daiichi Nuclear Power Station, it is considered that corrosion of primary containment vessel (PCV) and reactor pressure vessel (RPV) steels is accelerated by seawater injection and high radiation dose. In general, it is known that weight loss in steels increases near gas-liquid interface. Therefore, the lower half of the specimens was dipped in diluted seawater at 50
C under rays irradiation. Gas phase in flasks was air or N
atmosphere. After the tests, oxide layer was removed and 3 dimension (3D) digital data were measured on the specimen surface using a 3D macro-scope. In air atmosphere, the maximum roughness height increased with time and dose rate. After rays irradiation for 500 h, the maximum roughness height in N atmosphere was lower than that in air atmosphere. Since O concentration in liquid was reduced by decrease of O partial pressure in gas phase, it was appeared that localized corrosion was suppressed.
Nakano, Junichi
no journal, ,
Seawater was injected into the reactor cores in the Fukushima Daiichi Nuclear Power Station (1F-NPP). Radiation dose is high in the primary containment vessels (PCVs) because of the fuel debris and the fission products. It is considered that corrosion of the reactor pressure vessels and the PCVs is accelerated by the products of water radiolysis. An amount of the injected seawater, temperature, radiation dose in the PCVs of the 1F-NPP and decommissioning plan are shown. Corrosion tests of low alloy steel and carbon steel under -rays irradiation conducted in the Japan Atomic Energy Agency are introduced. Uniform corrosion rates of the steels were hard to be accelerated remarkably in dose levels which were measured in the PCV of the 1F. Moreover, as a way of corrosion prevention, it was effective to have replaced the gaseous phase with N.
Yamamoto, Masahiro; Motooka, Takafumi*; Nakano, Junichi*; Kato, Chiaki; Sato, Tomonori
no journal, ,
About 10 years have passed after Higashi-Nihon earthquake. Decommissioning process of Fukushima Dai-ichi NPS have been continuing day by day. However, some corrosion problems were revealed at the early stage after the accident, because sea water was used for emergency cooling of reactor vessel. In this report, research and development against those corrosion problems by JAEA researchers are introduced briefly. For example, corrosion mechanism and mitigation procedure for spent nuclear fuel pool, reactor vessel and equipment for removal of radioactive materials are summarized.
