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Furukawa, Tomohiro; Kato, Shoichi; Inagaki, Yoshiyuki; Aritomi, Masanori*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 5 Pages, 2011/10
A key problem in the application of a supercritical carbon dioxide (CO
) turbine cycle to a fast breeder reactor is the corrosion of structural materials brought about by supercritical CO at high temperatures. In this study, high-temperature oxidation tests on the structural materials were performed in carbon dioxide pressurized at 0.2 and 1 MPa, and in air, and the oxidation behavior were compared. Results of investigating the effect of CO pressure including the previous reports tested at 10 MPa and at 20 MPa, the effect was hardly observed for all steels. In air environment, weight gain caused by high temperature oxidation was much lower than that in CO.
Furukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
Progress in Nuclear Energy, 53(7), p.1050 - 1055, 2011/09
Times Cited Count：63 Percentile：97.53(Nuclear Science & Technology)Compatibility of the FBR candidate materials, 12Cr-steel and 316FR, with supercritical CO pressurized at 20 MPa for up to 8000 hours at 400-600 
C has been investigated. Corrosion due to the high temperature oxidation was measured in both steels. Results showed that the behavior differed greatly. For 12Cr-steel, weight gain showed parabolic growth as exposure time increased at each temperature, and no breakaway oxidation was observed. The specimens were covered by two successive oxide layers. For 316FR, the weight gain was significantly lower than that of 12Cr-steel, and good resistance against corrosion was observed. No dependency of temperature or immersed time on weight gain was observed. Based on the metallurgical examination, corrosion formula in supercritical CO has been shown for the candidate materials for provisional design.
Furukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
Journal of Power and Energy Systems (Internet), 4(1), p.252 - 261, 2010/04
Corrosion test of high-chromium martensitic steel (12Cr-steel) and FBR grade type 316 stainless steel (316FR) were performed at 400-600 C in supercritical CO pressurized at 20MPa. High temperature oxidation was measured up to approximately 2000h in both steels. In the case of 12Cr-steel, the weight gain showed parabolic growth with exposure time at each temperature. The oxidation coefficient could be estimated by the Arrhenius function. The specimens were covered by two successive oxide layers. In the case of 316FR specimens, the weight gain was significantly lower than that of 12Cr-steel. Dependency of neither temperature nor exposed time on oxidation was not observed. Nodule shape oxides were observed on the surface of the 316FR specimen. Carburizing, known as a factor in the occurrence of breakaway corrosion and/or the degradation of ductility, was observed on the surface of both steels.
Furukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 6 Pages, 2009/06
A key problem in the application of a supercritical carbon dioxide (CO) turbine cycle to a fast breeder reactor is the corrosion of structural materials by supercritical CO at high temperature. In this study, corrosion tests on the candidate materials, high-chromium martensitic steel (12Cr-steel) and FBR grade type 316 stainless steel (316FR), were performed for up to approximately 2000h at 400-600 C in supercritical CO pressurized at 20 MPa.
Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; et al.
JAERI-Research 2004-008, 383 Pages, 2004/06
JAERI-Research-2004-008.pdf:21.49MB
The present report contains the achievement of "Research and Development on Reduced-Moderation Light Water Reactor with Passive Safety Features", which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies.
Okubo, Tsutomu; Iwamura, Takamichi; Takeda, Renzo*; Moriya, Kumiaki*; Yamauchi, Toyoaki*; Aritomi, Masanori*
Nihon Kikai Gakkai 2003-Nendo Nenji Taikai Koen Rombunshu, Vol.3, p.245 - 246, 2003/08
A design study on a 300MWe class small Reduced-Moderation Water Reactor (RMWR) has been performed, based on the experienced LWR technology. The core can be cooled by the natural circulation and can achieve a conversion ratio of 1.01, a negative void reactivity coefficient, a core average burn-up of 65 GWd/t and a cycle length of 25 months. The system has been simplified as much as possible by introducing the passive safety components, in order to reduce the construction cost per electric power output overcoming “the scale demerit" for a small reactor comparing with the large one. The results show a 1.35 times higher cost than for the ABWR case, but suggest the possible lower cost when the effects such as the mass production are taken into account.
Aritomi, Masanori*; Onuki, Akira; Arai, Kenji*; *; Yonomoto, Taisuke; Araya, Fumimasa; Akimoto, Hajime
Nihon Genshiryoku Gakkai-Shi, 41(7), p.738 - 757, 1999/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; Aritomi, Masanori*; Kozaki, Yasutsugu*; *; *; *; *; et al.
JAERI-Tech 96-019, 122 Pages, 1996/05
no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto; Ogawa, Masuro; ; Aritomi, Masanori*; Kozaki, Yasutsugu*; *; *; *; et al.
JAERI-Review 96-007, 87 Pages, 1996/05
JAERI-Review-96-007.pdf:2.66MB
no abstracts in English
Hishida, Makoto; Ogawa, Masuro; Aritomi, Masanori*; *; *; *; Kozaki, Yasutsugu*
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.765 - 770, 1995/00
no abstracts in English
Furukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
no journal, ,
Corrosion tests on the candidate materials, 12Cr-steel and 316FR, were performed for up to 1000h at 400-600 C in supercritical carbon dioxide, and the corrosion behavior was investigated.
Furukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
no journal, ,
Corrosion test of FBR Candidate Materials, 12Cr-steel and 316FR has been performed in high temperature supercritical CO (20MPa). This report describes the results of the corrosion behavior exposed at 400-600 C for up to 5000h.
, 3; Effect of CO pressure and Impurities in COFurukawa, Tomohiro; Inagaki, Yoshiyuki; Aritomi, Masanori*
no journal, ,
For the structral materials for advanced fast reactor, the effect of CO pressure and the impurities (oxygen and dew point) in CO was estimated.
