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JAEA Reports

Hydrogen absorption of titaniam for nuclear waste container in non-oxidizing condition

Tomari, Haruo*; *; Shimogori, Kazutoshi*; Wada, Ryutaro*; ; Taniguchi, Naoki

JNC TN8400 99-076, 100 Pages, 1999/10

JNC-TN8400-99-076.pdf:45.74MB

Effects of bentonite clay, applied potential, pH, of solution and cathodic polarization time on hydrogen absorption into titanium, which is one of the candidate materials of overpack for high-level radioactive waste container, have been investigated in artificial underground water. Considering the result at various test time and assuming the hydrogen absorption is ruled by the paraboric law, the amount of hydrogen after 1000 years exposure calculated to about 17ppm, which will be absorbed at the applied potential of -0.51 vs. SHE corresponds to equilibrium potential of hydrogen. It seems the assumption of the parabolic law and the test period are proper, because the linear relations were obtained between the amount of absorbed hydrogen and the logarithm of the averaged cathodic current and between the slopes of the lines and a square root of the test time. Titanium seems to have a life over 1000 years in deep underground repository according to assumption that about 500ppm absorbed hydrogen is critical for hydrogen embrittlement of titanium.

JAEA Reports

Corrosion resistance of titanium for nuclear waste container in non-oxidizing condition, III

Wada, Ryutaro*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; Tomari, Haruo*; Masugata, Tsuyoshi*; Shimoda, Hideaki*

JNC TJ8400 99-059, 50 Pages, 1999/02

JNC-TJ8400-99-059.pdf:7.09MB

no abstracts in English

JAEA Reports

Corrosion resistance of titanium for nuclear waste container in non-oxidizing conditiou (III)

Wada, Ryutaro*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; Tomari, Haruo*; Masugata, Tsuyoshi*; Shimoda, Hideaki*

JNC TJ8400 99-046, 144 Pages, 1999/02

JNC-TJ8400-99-046.pdf:14.01MB

The corrosion-resistant material, titanium, is one of the candidate materials for nuclear fuel waste container. The purpose of this study is to investigate hydrogen embrittlement behavior of titanium in non-oxidizing solution clay estimated to be original condition of deep underground. The electrochemical tests were performed in deaerated carbonate solution at 50$$^{circ}$$C by 1440 hours, and hydrogen absorption behavior of titanium was investigated in with relation applied potential. The thoughts of hydrogen embrittlement and corrosion potential model of titanium were also discribed.

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

Corrosion Resistance of Titanium for Nuclear Waste Container in Non-oxidizing Condition (II)

Wada, Ryutaro*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; Tomari, Haruo*; Masugata, Tsuyoshi*; Shimoda, Hideaki*; Fujiwara, Kazuo*; Nishimoto, Hidetoshi*; Oda, Masashi*

PNC TJ1058 98-002, 159 Pages, 1998/02

PNC-TJ1058-98-002.pdf:12.95MB

None

JAEA Reports

Corrosion Resistance of Titanium for Nuclear Waste Container in Non-oxidizing Condition (II)

Wada, Ryutaro*; Nishimura, Tsutomu*; Shimogori, Kazutoshi*; Tomari, Haruo*; Masugata, Tsuyoshi*; Shimoda, Hideaki*; Fujiwara, Kazuo*; Nishimoto, Hidetoshi*; Oda, Masashi*

PNC TJ1058 98-001, 446 Pages, 1998/02

PNC-TJ1058-98-001.pdf:36.59MB

None

JAEA Reports

None

*; Wada, Ryutaro*; *; Fujiwara, Kazuo*; *; Tomari, Haruo*

PNC TJ1058 91-012, 335 Pages, 1991/09

PNC-TJ1058-91-012.pdf:10.6MB

None

JAEA Reports

Development of chemical interaction model between overpack material and underground water

Matsuda, Fumio*; Wada, Ryutaro*; Nakasaku, Toshiyuki*; Fujiwara, Kazuo*; Tomari, Haruo*; Takeda, Kazuo*

JNC TJ1400 2005-018, 790 Pages, 1989/03

JNC-TJ1400-2005-018-1.pdf:12.05MB
JNC-TJ1400-2005-018-2.pdf:13.55MB
JNC-TJ1400-2005-018-3.pdf:102.13MB

In this study, investigation and estimation of the corrosion circums tances of overpack, corrosion mechanism of overpack materials and variation of chemical circumstances was performed. Corrosion tests were conducted under the limited condition of the artifical sea water at 80$$^{circ}$$C.

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