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Journal Articles

Structure analysis of cation selective Cr-goethite as protective rust of weathering steel

Konishi, Hiroyuki; Yamashita, Masato*; Uchida, Hitoshi*; Mizuki, Junichiro

Materials Transactions, 46(2), p.337 - 341, 2005/02

 Times Cited Count:6 Percentile:49.02(Materials Science, Multidisciplinary)

We have performed extended X-ray absorption fine structure (EXAFS) analysis for artificial Cr-goethite to elucidate the local structure around Cr in Cr-goethite. The spectra were obtained using synchrotron radiation X-rays at the Photon Factory in Tsukuba. The first shell contributions were isolated by Fourier filtering the EXAFS data, and the inverse Fourier transformed single-shell data were analyzed using curve fitting method. The results show that Cr is coordinated with (7$$pm$$1) O$$^{2-}$$ ions. The protective character of Cr-goethite protective rust layer on weathering steel can be interpreted in terms of the O$$^{2-}$$ coordination around Cr$$^{3+}$$ resulting in creation of negative fixed-charge in the Cr-goethite particles.

Journal Articles

Difference between Cr and Ni K-edge XANES spectra of rust layers formed on Fe-based binary alloys exposed to Cl-rich environment

Konishi, Hiroyuki; Yamashita, Masato*; Uchida, Hitoshi*; Mizuki, Junichiro

Materials Transactions, 46(1), p.136 - 139, 2005/01

 Times Cited Count:2 Percentile:72.64(Materials Science, Multidisciplinary)

The rust layer formed on weathering steel possesses a strong protective ability against corrosives in an atmosphere. This ability is related to the structure of the rust layer. The difference in the protective ability of a rust layer in a Cl-rich environment between conventional weathering steel containing Cr and advanced weathering steel containing Ni is believed to be caused by the differences in local structural and chemical properties between alloying elements, Cr and Ni, in the rust layer. In order to examine the effect of these alloying elements on the structure of the rust layer formed on steel in a Cl-rich environment, we have performed Cr and Ni K-edge X-ray absorption near-edge structure (XANES) measurements for the rust layer of Fe-Cr and Fe-Ni binary alloys exposed to a Cl-rich atmosphere using synchrotron radiation. The results of the Cr K-edge XANES measurements for the rust layer of Fe-Cr binary alloys show that the atomic geometry around Cr depends on the concentration of Cr. Therefore, it is expected that the local structure around Cr in the rust layer is unstable. On the other hand, from the results of the Ni K-edge XANES measurements for the rust layer of Fe-Ni binary alloys, Ni is considered to be positioned at a specific site in the crystal structure of a constituent of the rust layer, such as akagan$'e$ite or magnetite. As a consequence, Ni negligibly interacts with Cl$$^{-}$$ ions in the rust layer.

Journal Articles

RIA-simulating experiments on high burnup PWR fuel rods with advanced cladding alloys

Sugiyama, Tomoyuki; Fuketa, Toyoshi; Ozawa, Masaaki*; Nagase, Fumihisa

Proceedings of 2004 International Meeting on LWR Fuel Performance, p.544 - 550, 2004/09

Two pulse irradiation experiments simulating reactivity initiated accidents were performed on high burnup ($$sim$$60 GWd/t) PWR UO$$_2$$ rods with advanced cladding alloys. Test OI-10 was performed on an MDA cladded rod with large-grain ($$sim$$25 $$mu$$m) fuel pellets with a peak fuel enthalpy condition of 435 J/g, and resulted in a peak residual hoop strain of 0.7%. On the other hand, Test OI-11 on a ZIRLO cladded rod with conventional pellets resulted in a fuel failure at a fuel enthalpy of 500 J/g due to the pellet-cladding mechanical interaction (PCMI). A long axial split was generated on the cladding over the active length. The fuel pellets were fragmented and dispersed into the coolant water. The fuel enthalpy at failure is higher than the PCMI failure criterion of 209 J/g at the corresponding burnup. The experimental results suggest that the rods with improved corrosion resistance have much safety margin against the PCMI failure compared to the conventional Zircaloy-4 rod.

JAEA Reports

Compatibility tests between molten salts and metal materials, 2

Shiina, Yasuaki; Kuriki, Yoshiro*

JAERI-Tech 2003-070, 47 Pages, 2003/08

JAERI-Tech-2003-070.pdf:14.83MB

no abstracts in English

JAEA Reports

Evaluation of properties of low activation Mn-Cr steel, 3; Evaluation of corrosion resistnace

Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Sato, Ikuo*; Kusuhashi, Mikio*; Hatakeyama, Tsuyoshi*; Takahashi, Heishichiro*; Kikuchi, Mitsuru

JAERI-Tech 2002-047, 51 Pages, 2002/05

JAERI-Tech-2002-047.pdf:3.42MB

no abstracts in English

Journal Articles

Recent progress and future R&D for high-chromium iron-base and chromium-base alloys

Hishinuma, Akimichi; Takaki, Seiichi*; Abiko, Kenji*

Physica Status Solidi (A), 189(1), p.69 - 78, 2002/01

 Times Cited Count:12 Percentile:44.75

no abstracts in English

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

JAEA Reports

Long-term immersion tests of engineered materials in the Tono mine; Results for metals

; Taniguchi, Naoki;

JNC-TN7430 2000-002, 25 Pages, 2001/01

JNC-TN7430-2000-002.pdf:3.32MB

The burial tests of mild steel and pure titanium were performed in a gallery at Tono mine to assess the corrosion resistance of these materials under goundwater environment. Specimens were placed in the container and immersed into groundwater. After the immersion period, the apperance of the surface of these specimens were observed. The corrosion product of mild steel specimen was analysed by various methods. The average corrosion rate of mild steel for 10 years was assessed by the measurement of the weight loss of carbon steel specimen. The results of the test were summerised as follows : (1)The average corrosion rate of mild steel for 10 years was assessed to be 4.36 $$times$$10$$^{-3}$$mm/y by the weight loss of the specimen. (2)The corrosion product consists of outer porous substance and inner tight corrosion product film. The former contains ferric oxide such as goethite and the latter contains ferrous oxide such as magnetite. (3)The evidence of the initiation of localised corrosion was not observed on the titanium specimens.

JAEA Reports

lnvestigation for corrosion behavior of core materials in lead cooled reactor

Kaito, Takeji

JNC-TN9400 2000-039, 19 Pages, 2000/03

JNC-TN9400-2000-039.pdf:0.66MB

The corrosion behavior of core materials in lead cooled reactor was investigated as the feasibility study for fast breeder reactor. The results are summarized as follows. (1)The corrosion of stainless steels under lead and lithium occurs mainly due to the dissolution of nickel. Consequently ferritic stainless steels have better resistance to corrosion under lead and lithium than austenitic stainless steels, and the corrosion resistance of high nickel steels is worst. (2)The dissolution rate, D(mg/m$$^{2}$$/h), is correlated with lead and lithium temperature, T(K), as log$$_{10}$$ Da = 10.7873 - 6459.3/ T and log$$_{10}$$Df = 7.6185 - 4848.4/T, where D a is the dissolution rate for austenitic steels and D f is for ferritic steels. lt's possible to calculate the corrosion thickness, C($$mu$$m), using the following correlation: C = (D$$times$$t)/$$rho$$$$times$$10$$^{-3}$$, where t is exposure time(hr) and $$rho$$ is density of the core matelial (g/cm$$^{3}$$). (3)The corrosion thickness estimated for austenitic steels using above correlations was extremely larger than ferritic steels, about 6 times at 400$$^{circ}$$C and more than 20 times at above 600$$^{circ}$$C. lt's considered that applicable temperature in lead cooled reactor core is below 400$$^{circ}$$C (about 60$$mu$$m corrosion thickness after 30000 hr) for austenitic steels, and below 500$$^{circ}$$C (about 80 $$mu$$m after 30000 hr) for ferritic steels.

JAEA Reports

None

Shibata, Toshio*; *; *; Tsuru, Toru*; Inoue, Hiroyuki*

JNC-TJ8400 2000-013, 38 Pages, 2000/02

JNC-TJ8400-2000-013.pdf:3.25MB

None

JAEA Reports

Trial manufacturing of copper-carbon steel composite overpack

*; *; Tanai, Kenji

JNC-TN8400 99-049, 94 Pages, 1999/11

JNC-TN8400-99-049.pdf:6.63MB

This paper reports the results of design analysis and trial manufacturing of copper-carbon steel composite overpacks. The overpack is one of the key components of the engineered barrier system, hence, it is necessary to confirm the applicability of current technique in their manufacture. The Copper-Carbon steel composite overpack consists of a double container, an outer vessel made of oxygen-free, high-purity copper as the corrosion allowance material, and an inner vessel made of carbon steel as the pressure-resistant material. The trial manufacturing in this time, only the copper outer vessel has been fabricated. Both oxygen-free copper and oxygen-free phosphorus copper were used as materials for the outer vessel. For the shell and bottom portion, these materials were formed integrally by a backward extrusion method. For sealing the top cover plate to the main body, an electron-beam welding method was applied. After manufacturing, mechanical testing of specimens from the copper vessels were carried out. It was confirmed that current technique has sufficient feasibility to manufacture outer vessel. In addition, potential for irradiation embrittlement of the inner carbon-steel vessel by irradiation from vitrified waste over the life time of the overpack has been analyzed. It was shown that the small degree of irradiation embrittlement gives no significant impact on the pressure resistance of the carbon-steel vessel. Future research and development items regarding copper-carbon steel composite overpacks are also discussed.

Journal Articles

Corrosion tests of iron-silicon alloys in boiling sulfuric acid

Ioka, Ikuo; Onuki, Kaoru; Futakawa, Masatoshi; Kuriki, Yoshiro*; Nagoshi, Masayasu*; Nakajima, Hayato; Shimizu, Saburo

Ryusan To Kogyo, 52(4), p.1 - 6, 1999/04

no abstracts in English

Journal Articles

Corrosion resistance and nature of surface film on Fe-Si alloy in boiling sulfuric acid

Ioka, Ikuo; *; ; Futakawa, Masatoshi; Onuki, Kaoru

Nippon Kinzoku Gakkai-Shi, 63(5), p.609 - 612, 1999/00

no abstracts in English

Journal Articles

Viscosity of amorphous oxide scales on SiSiC at elevated temperatures

Futakawa, Masatoshi; Steinbrech, R. W.*

Journal of the American Ceramic Society, 81(7), p.1819 - 1842, 1998/07

no abstracts in English

JAEA Reports

None

; ; Fujisaku, Kazuhiko*; ; Takeda, Seiichiro

PNC-TN8410 98-060, 74 Pages, 1998/03

PNC-TN8410-98-060.pdf:4.43MB

None

JAEA Reports

None

PNC-TJ1211 98-005, 146 Pages, 1998/02

PNC-TJ1211-98-005.pdf:2.42MB

None

JAEA Reports

None

*; *; *; *

PNC-TJ1211 98-004, 68 Pages, 1998/02

PNC-TJ1211-98-004.pdf:4.66MB

None

JAEA Reports

None

*; *; *; *; *; *; *

PNC-TJ1010 98-001, 221 Pages, 1998/02

PNC-TJ1010-98-001.pdf:12.95MB

None

Journal Articles

New alloy developments for advanced spent fuel reprocessing using nitric acid solutions

Kiuchi, Kiyoshi; ; *; *

Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 3, 8 Pages, 1998/00

no abstracts in English

JAEA Reports

None

*; *; ; Takeda, Seiichiro

PNC-TN8410 97-433, 50 Pages, 1997/12

PNC-TN8410-97-433.pdf:1.34MB

None

62 (Records 1-20 displayed on this page)