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Shibata, Taiju; Mizuta, Naoki; Sumita, Junya; Sakaba, Nariaki; Osaki, Takashi*; Kato, Hideki*; Izawa, Shoichi*; Muto, Takenori*; Gizatulin, S.*; Shaimerdenov, A.*; et al.
Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7 Pages, 2018/10
Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR). Oxidation damage on the graphite components in air ingress accident is a crucial issue for the safety point of view. SiC coating on graphite surface is a possible technique to enhance oxidation resistance. However, it is important to confirm the integrity of this material against high temperature and neutron irradiation for the application of the in-core components. JAEA and Japanese graphite companies carried out the R&D to develop the oxidation-resistant graphite. JAEA and INP investigated the irradiation effects on the oxidation-resistant graphite by using a framework of ISTC partner project. This paper describes the results of post irradiation experiment about the neutron irradiated SiC-coated oxidation-resistant graphite. A brand of oxidation-resistant graphite shows excellent performance against oxidation test after the irradiation.
Mizuta, Naoki; Sumita, Junya; Shibata, Taiju; Osaki, Takashi*; Kato, Hideki*; Izawa, Shoichi*; Muto, Takenori*; Gizatulin, S.*; Sakaba, Nariaki
Tanso Zairyo Kagaku No Shinten; Nihon Gakutsu Shinkokai Dai-117-Iinkai 70-Shunen Kinen-Shi, p.161 - 166, 2018/10
To enhance oxidation resistance of graphite material for in-core components of HTGR, JAEA and four Japanese graphite companies; Toyo Tanso, IBIDEN, Tokai Carbon and Nippon Techno-Carbon, are carrying out for development of oxidation-resistant graphite by CVD-SiC coating. This paper describes the outline of neutron irradiation test about the oxidation-resistant graphite by WWR-K reactor of INP, Kazakhstan through an ISTC partner project. Prior to the irradiation test, the oxidation-resistant graphite by CVD-SiC coating of all specimens showed enough oxidation resistance under un-irradiation condition. The neutron irradiation test was already completed and out-of-pile oxidation test will be carried out at the hot-laboratory of WWR-K.
Shibata, Taiju; Sumita, Junya; Sakaba, Nariaki; Osaki, Takashi*; Kato, Hideki*; Izawa, Shoichi*; Muto, Takenori*; Gizatulin, S.*; Shaimerdenov, A.*; Dyussambayev, D.*; et al.
Proceedings of 8th International Topical Meeting on High Temperature Reactor Technology (HTR 2016) (CD-ROM), p.567 - 571, 2016/11
Graphite are used for the in-core components of HTGR, and it is desirable to enhance oxidation resistance to keep much safety margin. SiC coating is the candidate method for this purpose. JAEA and four Japanese graphite companies are studying to develop oxidation-resistant graphite. Neutron irradiation test was carried out by WWR-K reactor of INP of Kazakhstan through ISTC partner project. The total irradiation cycles of WWR-K operation was 10 cycles by 200 days. Irradiation temperature about 1473 K would be attained. The maximum fast neutron fluence (E 
0.18 MeV) for the capsule irradiated at a central irradiation hole was preliminary calculated as 1.2
10
/m
, and for the capsule at a peripheral irradiation hole as 4.210
/m. Dimension and weight of the irradiated specimens were measured, and outer surface of the specimens were observed by optical microscope. For the irradiated oxidation resistant graphite, out-of-pile oxidation test will be carried out at an experimental laboratory.
ISTC/STCU Fukushima Initiative Technical Review Committee; Fukushima Initiative Technical Review Committee
JAEA-Conf 2016-003, 107 Pages, 2016/07
The final ISTC/STCU Technical Review Committee Meeting "On the environmental assessment for long term monitoring and remediation in and around Fukushima" was held in Hitotsubashi University Hall, Tokyo, on November 5-6, 2015. This report consists of summary reports of Fukushima Initiative projects, which were presented at the meeting. As regarding to the sections those which will be published elsewhere, only their executive summaries are included.
ISTC/STCU Fukushima Initiative Technical Review Committee; Fukushima Initiative Technical Review Committee
JAEA-Conf 2016-002, 111 Pages, 2016/06
The final ISTC/STCU Technical Review Committee Meeting "On the environmental assessment for long term monitoring and remediation in and around Fukushima" was held in Hitotsubashi University Hall, Tokyo, on December 5-6, 2015. This report consists of summary reports of Fukushima Initiative projects, which were presented at the meeting. As regarding to the sections those which will be published elsewhere, only their executive summaries are included.
Soukhovitskij, E. Sh.*; Chiba, Satoshi; Iwamoto, Osamu; Shibata, Keiichi; Fukahori, Tokio; Morogovskij, G. B.*
JAERI-Data/Code 2005-002, 78 Pages, 2005/03
JAERI-Data-Code-2005-002.pdf:7.7MB
no abstracts in English
Soukhovitskij, E. Sh.*; Morogovskij, G. B.*; Chiba, Satoshi; Iwamoto, Osamu; Fukahori, Tokio
JAERI-Data/Code 2004-002, 32 Pages, 2004/03
JAERI-Data-Code-2004-002.pdf:1.43MB
This report gives a detailed description of the theory and computational algorithms of modernized coupled-channels optical model code OPTMAN based on the soft-rotator model for the collective nuclear structure and excitations. This work was performed under the Project Agreement B-521 with the International Science and Technology Center (Moscow), financing party of which is Japan. As a result of this work, the computational method of OPTMAN was totally updated, and an user-friendly interface was attached.
Tkalin, A. V.*; Aramaki, Takafumi; Togawa, Orihiko; Volkov, Y. N.*
Proceedings of International Symposium on Oceanography of the Japan Sea (CREAMS-2000), p.181 - 187, 2000/00
no abstracts in English
Danchenkov, M. A.*; Togawa, Orihiko; Hong, G. H.*
Proceedings of International Symposium on Oceanography of the Japan Sea (CREAMS-2000), p.188 - 192, 2000/00
no abstracts in English
Maekawa, Hiroshi; Mukaiyama, Takehiko; Yamane, Tsuyoshi; *; *; Suzuki, Atsuyuki*; Takeda, Renzo*; *; Kawashima, Masatoshi*; *; et al.
Nihon Genshiryoku Gakkai-Shi, 40(12), p.963 - 965, 1998/12
no abstracts in English
31,1996,JAERI,Tokai,JapanKatakura, Junichi
JAERI-Conf 97-001, 293 Pages, 1997/03
no abstracts in English
Kato, Shohei
Hoken Butsuri, 30, p.345 - 347, 1995/00
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 36(4), p.292 - 300, 1994/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
