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Rouillard, F.*; Furukawa, Tomohiro
Corrosion Science, 105, p.120 - 132, 2016/04
Times Cited Count:102 Percentile:97.22(Materials Science, Multidisciplinary)The high temperature corrosion behavior of two 9Cr and 12Cr ferritic-martensitic steel grades was studied under CO pressure varying from 1 to 250 bar for exposure times up to 8000 h. No breakaway oxidation was observed. 9Cr steel grades suffered from fast parabolic uniform oxidation and fast carburisation. Increasing CO
pressure had very little effect on the oxidation rate but increased the carburisation rate. The corrosion behavior of both 12Cr steel grades differed and might be influenced by gas composition, minor elements or surface finish. A corrosion mechanism coupling oxidation and carburisation is proposed.
Hamamoto, Shimpei; Nemoto, Takahiro; Sekita, Kenji; Saito, Kenji
JAEA-Technology 2015-048, 62 Pages, 2016/03
The decarburization may take place depending on the chemical impurity composition in helium gas used as the primary coolant in High-Temperature Gas-cooled Reactors, and will significantly reduce the strength of the alloy. The ability to remove impurities by a helium purification system was designed according to the predicted generation rate of impurities so as to make the coolant become the carburizing atmosphere. It has been confirmed that the coolant becomes the carburizing atmosphere during the operation period of the High Temperature engineering Test Reactor (HTTR). However, it is necessary to consider changes of generation rates of impurities since lifetime of commercial reactor is longer than the life of the HTTR. To avoid the influence of the change of generation rate, the control of removal efficiency of impurity in the helium purification system was considered in this study. To reform the decarburizing into the carburizing atmosphere, it is effective to increase the H and CO concentration in the coolant helium. By controlling the efficiency of the Cooper Oxide Trap (CuOT), it is possible to increase the H
and CO concentrations. Therefore, an experiment was carried out by injecting the gas mixture of H
and CO into the existing purification system of HTTR to investigate the dependencies of temperature and impurity concentration on the removal efficiency of CuOT. The experimental results are described as the following, (1) By adjusting the temperature of helium at the CuOT within a range from 110
C to 50
C, it is possible to reduce the removal efficiency of H
sufficiently. (2) Temperature change of helium gas in the CuOT is sufficiently reduced by the cooler located at the downstream of the CuOT, which does not affect the primary cooling system of HTTR. As the results, the applicability of removal efficiency control of CuOT was verified to improve the decarburizing atmosphere for the actual HTGR system.
; Watanabe, Katsutoshi; Shindo, Masami
JAERI-Research 95-088, 16 Pages, 1996/01
no abstracts in English
Kurata, Yuji; ; ; Shindo, Masami; Nakajima, Hajime;
Journal of Nuclear Science and Technology, 32(11), p.1108 - 1117, 1995/11
Times Cited Count:4 Percentile:42.88(Nuclear Science & Technology)no abstracts in English
Kurata, Yuji; ; ; Shindo, Masami; Nakajima, Hajime;
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 36(2), p.149 - 156, 1995/07
no abstracts in English
Shindo, Masami; Nakajima, Hajime
Journal of Nuclear Materials, 144, p.20 - 28, 1987/00
Times Cited Count:6 Percentile:55.27(Materials Science, Multidisciplinary)Carburization tests with experimental fine- and coarse-grained Ni-Cr-W alloys strengthened by -W phase were carried out at 950
C in heavily carburizaing environment (90% Ar + 10% CH
) to investigate the carburization behaviour and its effect on room temperature tensile properties; the aging effect was also examined.
; Ogawa, Yutaka; Nakajima, Hajime
Trans.Iron Steel Inst.Jpn., 27, P. 81, 1987/00
no abstracts in English
Tobita, Tsutomu; Ikawa, Katsuichi
JAERI-M 84-096, 16 Pages, 1984/05
no abstracts in English
; Ogawa, Yutaka; Kondo, Tatsuo
Nuclear Technology, 66, p.250 - 259, 1984/00
Times Cited Count:10 Percentile:70.25(Nuclear Science & Technology)no abstracts in English
; Kondo, Tatsuo
Proc.of 2nd Japan-US HTGR Safety Technology Seminar,Material Properties andDesign Method Session, 12 Pages, 1978/00
no abstracts in English