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Igarashi, Takahiro; Otani, Kyohei; Kato, Chiaki; Sakairi, Masatoshi*; Togashi, Yusuke*; Baba, Kazuhiko*; Takagi, Shusaku*
ISIJ International, 61(4), p.1085 - 1090, 2021/04
Times Cited Count：1 Percentile：8.06(Metallurgy & Metallurgical Engineering)In order to clarify the effect of metal cations (Zn
, Mg, Na
) in aqueous solution on hydrogen permeation into iron, the amount of hydrogen permeation from iron surface was measured by electrochemical tests with a laser ablation. Moreover, in order to obtain the basic mechanism of hydrogen permeation with metal cation, first-principles calculations were used to acquire the adsorption potential of the metal cation and the electronic state around iron surface. By Zn in solution, anodic reaction on ablated surface by laser irradiation was suppressed. Also, by quantum analysis Zn atoms were chemically bonded stronger than Na and Mg atoms to iron surface. It was suggested that the dissolution reaction of iron was suppressed by the formation of the Zn layer, and that lead suppression of hydrogen permeation into iron.
Oya, Yasuhisa*; Li, X.*; Sato, Misaki*; Yuyama, Kenta*; Oyaizu, Makoto; Hayashi, Takumi; Yamanishi, Toshihiko; Okuno, Kenji*
Journal of Nuclear Science and Technology, 53(3), p.402 - 405, 2016/03
Times Cited Count：10 Percentile：68.36(Nuclear Science & Technology)The deuterium (D) permeation behaviors for ion damaged tungsten (W) by 3 keV D
and 10 keV C were studied. The D permeability was obtained for un-damaged W at various temperatures. For both D and C implanted W, the permeability was clearly reduced. But, for the D implanted W, the permeability was recovered by heating at 1173 K and it was almost consistent with that for un-damaged W. In the case of C implanted W, the permeability was not recovered even if the sample was heated at 1173 K, indicating that the existence of carbon would prevent the recovery of permeation path in W. In addition, TEM observation showed the voids were grown by heating at 1173 K and not removed, showing the existence of damages would not largely influence on the hydrogen permeation behavior in W in the present study.
Takeda, Tetsuaki; Iwatsuki, Jin*
JAERI-Research 2000-057, 17 Pages, 2001/01
JAERI-Research-2000-057.pdf:1.58MB
no abstracts in English
Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro
Nihon Genshiryoku Gakkai-Shi, 42(3), p.204 - 211, 2000/03
Times Cited Count：2 Percentile：19.44(Nuclear Science & Technology)no abstracts in English
Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro
JAERI-Tech 98-044, 34 Pages, 1998/11
no abstracts in English
JAERI-Research 98-019, 181 Pages, 1998/03
JAERI-Research-98-019.pdf:5.85MB
no abstracts in English
Takeda, Tetsuaki; Iwatsuki, Jin*; Ogawa, Masuro
Nihon Kikai Gakkai Dai-6-Kai Doryoku, Enerugi Gijutsu Shimpojiumu '98 Koen Rombunshu, p.90 - 95, 1998/00
no abstracts in English
Takeda, Tetsuaki; Iwatsuki, Jin*; Nishihara, Tetsuo
Proc. of ICONE-6, p.392 - 393, 1998/00
no abstracts in English
JAERI-Research 97-012, 96 Pages, 1997/03
JAERI-Research-97-012.pdf:8.65MB
no abstracts in English
Konishi, Satoshi; ; Naruse, Yuji
Nihon Genshiryoku Gakkai-Shi, 24(12), p.973 - 979, 1983/00
Times Cited Count：2 Percentile：32.89(Nuclear Science & Technology)no abstracts in English
Yoshida, Hiroshi; Konishi, Satoshi; Katsuta, Hiroji; Shimizu, Toku; Naruse, Yuji
Nihon Genshiryoku Gakkai-Shi, 24(6), p.475 - 482, 1982/00
Times Cited Count：1 Percentile：21.73(Nuclear Science & Technology)no abstracts in English
Kuroha, Mitsuo; *; *; *; Daigo, Yoshimichi; *; *
PNC TN941 81-51, 70 Pages, 1981/02
An in-cover gas hydrogen concentration meter was designed and manufactured as the water leak detector for sodium heated steam generators. This meter consists of a thin nickel membrane, a vacuum system, and an electric heater. The nickel membrane is used under the internal pressure in order to prevent its buckling. This meter was installed in the Small Sodium-Water Reaction Test Loop (SWAT-2) at PNC-Oarai Engineering Center. The specification, the construction and some of the test results are described in this report. The following results were obtained; (1)This hydrogen meter was very compact and capable for the leak detector and the hydrogen concentration meter. (2)The test result indicated that this meter was applicable to hydrogen concentration from 3 Vppm up to 10000 Vppm at nickel membrane temperature of 500
C and cover gas pressure of 1 kg/cm
G. (3)Hydrogen permeability through the nickel membrane in sodium vapour was similar to that in sodium.
Sanokawa, Konomo; Ouchi, Mitsuo;
Nihon Genshiryoku Gakkai-Shi, 22(2), p.121 - 128, 1980/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
; Sanokawa, Konomo; Ouchi, Mitsuo; Takizuka, Takakazu; Nekoya, Shinichi; Ogawa, Masuro; Emori, Kouichi
Nihon Genshiryoku Gakkai-Shi, 22(4), p.251 - 263, 1980/00
Times Cited Count：3 Percentile：41.98(Nuclear Science & Technology)no abstracts in English
JAERI-M 7293, 139 Pages, 1977/10
no abstracts in English
*; Okamoto, Yoshizo; Sanokawa, Konomo
JAERI-M 7034, 128 Pages, 1977/04
no abstracts in English
; Okamoto, Yoshizo
Gas-Cooled Reactor with Emphasis on Advanced Systems,Vol.2, p.219 - 236, 1976/00
no abstracts in English
Isobe, Kanetsugu; Hayashi, Takumi
no journal, ,
Aiming to understand the hydrogen isotopes permeation behavior in metals, effects of TIG welding, which is one of popular welding methods, on hydrogen permeation in SUS304 stainless steel were investigated. The welding lines to the number of 2, 11 and 20 were processed to the tube type of SUS304 steel specimens. Deuterium permeation behavior on each specimen were carried out in 523 K, 573 K, 623 K and 673 K. Deuterium permeated through the metal was measured with quadrupole mass spectrometer. Steady permeation rate was found to be almost same at 673 K and 623 K and the differences of permeation rate in each specimen were increased with the decreasing of temperature.
Suematsu, Senri*; Katayama, Kazunari*; Izumino, Junichi*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru; Nakagawa, Shigeaki
no journal, ,
It has been proposed that lithium compounds are loaded into a HTGR and tritium for initial fusion reactors is produced by 
Li(n,
)T reaction. Coating PyC layer on the lithium compounds could be one of the method for preventing the produced tritium leakage. In this study, hydrogen permeation experiment was performed to obtain tritium transmission coefficient in PyC, which is an important value to estimate the amount of the tritium leakage.
