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test plant; System performance evaluation for HTTR gas turbine cogeneration plantSato, Hiroyuki; Nomoto, Yasunobu*; Horii, Shoichi*; Sumita, Junya; Yan, X.
Nuclear Engineering and Design, 329, p.247 - 254, 2018/04
Times Cited Count：12 Percentile：76.34(Nuclear Science & Technology)This paper presents the system performance evaluation for HTTR gas turbine cogeneration test plant (HTTR-GT/H plant) so as to confirm that the design meets the requirements with respect to the demonstration test objective. Start-up and shut down operation sequences as well as operability of load following operation were investigated. In addition, system dynamic and control analyses for the test plant in the events of loss of generator load and upset of H plant were performed. The simulation results presented in the paper show that the test plant is suitable for the test bed to validate control schemes against postulated transients in the GTHTR300C. The results also lead us to the conclusion that HTTR-GT/H plant can be used to test operational procedures unique to HTGR direct-cycle gas turbine cogeneration.
test plantYan, X.; Sato, Hiroyuki; Sumita, Junya; Nomoto, Yasunobu*; Horii, Shoichi*; Imai, Yoshiyuki; Kasahara, Seiji; Suzuki, Koichi*; Iwatsuki, Jin; Terada, Atsuhiko; et al.
Nuclear Engineering and Design, 329, p.223 - 233, 2018/04
Times Cited Count：20 Percentile：89.78(Nuclear Science & Technology)The pre-licensing design of an HTGR cogeneration test plant to be coupled to JAEA's existing test reactor HTTR is presented. The plant is designed to demonstrate the system of JAEA commercial plant design GTHTR300C. With construction planned to be completed around 2025, the test plant is expected to be the first-of-a-kind nuclear system operating on two of the advanced energy conversion systems attractive for the HTGR closed cycle helium gas turbine for power generation and thermochemical iodine-sulfur water-splitting process for hydrogen production.
test plant (Revised version)Imai, Yoshiyuki; Sato, Hiroyuki; Yan, X.
JAEA-Data/Code 2017-011, 39 Pages, 2017/08
JAEA-Data-Code-2017-011.pdf:2.93MB
This report is the revised version of the report titled "Design Database of Helium Gas Turbine for High Temperature Gas-cooled Reactor, JAEA-Data/Code 2016-007" reflecting component design and experimental data analysis results for fission product isotope diffusion through the turbine blade alloy conducted in Fiscal Year 2016.
Imai, Yoshiyuki; Sato, Hiroyuki; Nomoto, Yasunobu; Yan, X.
JAEA-Data/Code 2016-007, 27 Pages, 2016/08
JAEA-Data-Code-2016-007.pdf:3.65MB
This report provides design database for helium gas turbine for HTGR. The design details for secondary helium cooling system and helium gas turbine in a heat application system to be coupled to the HTTR are described. In addition, experimental data for fission product isotope diffusion through turbine blade alloy is compiled.
Sato, Hiroyuki; Yan, X.; Sumita, Junya; Terada, Atsuhiko; Tachibana, Yukio
Journal of Nuclear Engineering and Radiation Science, 2(3), p.031010_1 - 031010_6, 2016/07
This paper explains the outline of HTTR demonstration program with a plant concept of the heat application system directed at establishing an HTGR cogeneration system with 950
C reactor outlet temperature for production of power and hydrogen as recommended by the task force. Commercial deployment strategy including a development plan for the helium gas turbine is also presented.
Tochio, Daisuke; Fujiwara, Yusuke; Ono, Masato; Shinohara, Masanori; Hamamoto, Shimpei; Iigaki, Kazuhiko; Takada, Shoji
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 9 Pages, 2016/06
From the HTTR operational experience, it is needed to clear the thermal mixing characteristics of the helium gas at the annulus of the co-axial double-walled piping in HTGR. In this paper, thermal-hydraulic analysis on the helium gas at the annular flow path of the co-axial double pipe with T-junction was conducted. The analysis was performed under the condition of the different annular flow path height and with the different flow rate of the higher- and the lower-temperature helium gas. It is shown that the thermal mixing behavior is not so much affected by the flow rate of higher- and lower-temperature helium gas, and it is difficult to mix the helium gas with the smaller height of the annular flow path. It is confirmed that it is difficult to mix the helium gas in the annular flow path of the co-axial double-walled piping by using the hydraulic behavior, and it is necessary to arrange the mixing promotor in the annular flow path.
Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Tanihira, Masanori*; Itaka, Hidehiko*; Mori, Eiji*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(3), p.291 - 300, 2003/09
no abstracts in English
Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Minatsuki, Isao*
Dai-31-Kai Gasu Tabin Teiki Koenkai Rombunshu, p.55 - 60, 2003/06
no abstracts in English
Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Shiozawa, Shusaku
Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.189 - 192, 2002/00
no abstracts in English
Kunitomi, Kazuhiko; Katanishi, Shoji; Shiozawa, Shusaku
Nihon Genshiryoku Gakkai-Shi, 43(11), p.1085 - 1099, 2001/11
no abstracts in English
Takase, Kazuyuki
Fusion Engineering and Design, 49-50, p.349 - 354, 2000/11
Times Cited Count：6 Percentile：42.51(Nuclear Science & Technology)no abstracts in English
Uwaba, Tomoyuki
JNC TN9420 2000-005, 28 Pages, 2000/03
JNC-TN9420-2000-005.pdf:0.94MB
In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.
Ishiyama, Shintaro; Muto, Yasushi; Kasaba, Michihiro*; Kaneta, Takayoshi*
Nihon Genshiryoku Gakkai-Shi, 42(3), p.196 - 203, 2000/03
Times Cited Count：1 Percentile：12.05(Nuclear Science & Technology)no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Tonogochi, Makoto*; Takenaka, Yutaka*
Enerugi, Shigen, 19(6), p.558 - 563, 1998/11
no abstracts in English
Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Akino, Norio; Shimizu, Saburo; Hada, Kazuhiko; Inagaki, Yoshiyuki; Onuki, Kaoru; Takeda, Tetsuaki; Nishihara, Tetsuo
IAEA-TECDOC-1056, p.191 - 200, 1998/11
no abstracts in English
Kaminaga, Atsushi; Arai, Takashi; ; *; Saido, Masahiro
Shinku, 41(10), p.846 - 850, 1998/00
no abstracts in English
Hino, Ryutaro; Fujisaki, Katsuo; ; ; Ota, Yukimaru; ; ; Haga, Katsuhiro; ; Mogi, Haruyoshi; et al.
JAERI-Tech 96-037, 45 Pages, 1996/09
no abstracts in English
Sakasai, Akira; Kubo, Hirotaka; Hosogane, Nobuyuki; Shimada, Michiya
3rd Int. Workshop on Helium Transport and Exhaust, 0, 28 Pages, 1996/00
no abstracts in English
Hino, Ryutaro; Haga, Katsuhiro; Takizuka, Takakazu; ;
JAERI-Tech 95-046, 54 Pages, 1995/10
no abstracts in English
; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;
JAERI 1333, 196 Pages, 1995/03
no abstracts in English
