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emission reduction goal in 2050Kamiji, Yu; Suzuki, Koichi*; Yan, X.
JAEA-Technology 2016-010, 24 Pages, 2016/07
JAEA-Technology-2016-010.pdf:1.05MB
Japanese government has set the goal of reducing CO emission by 26% in 2030 below the 2013 level, in longer term, by 80% below the 1990 level. To achieve the goals, various measures should be taken. The GTHTR300, a commercial High Temperature Gas-cooled Reactor (HTGR) design being developed by JAEA offers spectrum of heat applications by using its high temperature heat up to 950
C. The potential contribution of CO emission reduction by HTGR is estimated considering domestic and overseas deployment of the GTHTR300. The best estimate for domestic CO reduction is 2.07
10
ton- CO/yr and that from oversea is 2.2510 ton- CO/yr. The sum of these is about 47% of 9.1310 ton- CO/yr which is CO reduction target in 2050, for which deployment of 52 plants in Japan and 113 plants abroad, with each plant containing four 600 MWt reactor units, is required.
Hayashi, Koji; Inagaki, Yoshiyuki; Kato, Michio; Fujisaki, Katsuo*; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.
JAERI-Tech 2005-032, 46 Pages, 2005/06
JAERI-Tech-2005-032.pdf:4.79MB
This is annual report on the experimental operation of the mock-up test facility with a full-scale reaction tube for the HTTR hydrogen production system in 2001 fiscal year. The first experimental operation was performed during two weeks from March 1, 2002 to March 13, 2002 to test on the thermal hydraulic performance of the steam reformer and also to train the operators. The thermal hydraulic performance test of the steam reformer was performed to evaluate the heat transfer characteristics between helium gas and process gas in the steam reformer. This report is summarized with an overview of the test, the results and its operation records.
Sakaki, Akihiro*; Kato, Michio; Hayashi, Koji; Fujisaki, Katsuo*; Aita, Hideki; Ohashi, Hirofumi; Takada, Shoji; Shimizu, Akira; Morisaki, Norihiro; Maeda, Yukimasa; et al.
JAERI-Tech 2005-023, 72 Pages, 2005/04
JAERI-Tech-2005-023.pdf:14.86MB
In order to establish the system integration technology to connect a hydrogen production system to a high temperature gas cooled reactor, the mock-up test facility with a full-scale reaction tube for the steam reforming HTTR hydrogen production system was constructed in fiscal year 2001 and its functional test operation was performed in the year. Seven experimental test operations were performed from fiscal year 2001 to 2004. On a period of each test operation, there happened some troubles. For each trouble, the cause was investigated and the countermeasures and the improvement works were performed to succeed the experiments. The tests were successfully achieved according to plan.This report describes the improvement works on the test facility performed from fiscal year 2001 to 2004.
Sato, Hiroyuki; Ohashi, Hirofumi; Inaba, Yoshitomo; Maeda, Yukimasa; Takeda, Tetsuaki; Nishihara, Tetsuo; Inagaki, Yoshiyuki
JAERI-Tech 2005-014, 89 Pages, 2005/03
JAERI-Tech-2005-014.pdf:7.25MB
In a hydrogen production system using HTTR, it is required to control a secondary helium gas temperature within an allowable value at an intermediate heat exchanger (IHX) inlet to prevent a reactor scram. To mitigate thermal disturbance of the secondary helium gas caused by the hydrogen production system, a cooling system of the secondary helium gas using a steam generator(SG) and a radiator will be installed at the downstream of the chemical reactor. In order to verify a numerical analysis code of the cooling system, numerical analysis has been conducted. The pressure controllability in SG is highly affected by the heat transfer characteristics of air which flows outside of the heat exchanger tube of the radiator. In order to verify a numerical analysis code of the cooling system, the heat transfer characteristics of air has been investigated with experimental results of a mock-up model test. It was confirmed that numerical analysis results were agreed well with experimental results, and the analysis code was successfully verified.
Maeda, Yukimasa; Nishihara, Tetsuo; Ohashi, Hirofumi; Sato, Hiroyuki; Inagaki, Yoshiyuki
JAERI-Data/Code 2005-001, 149 Pages, 2005/03
JAERI-Data-Code-2005-001.pdf:12.66MB
A heat and mass balance analysis code (N-HYPAC) has been developed to investigate transient behavior in the HTTR hydrogen production system. The code can analyze heat and mass transfer (temperature and mass and pressure distributions of process and helium gases) and behavior of the control system under both static state(case of steady operation) and dynamic state(case of transient operation). Analysis model of helium and process gases from IHX to secondary helium loop and hydrogen production system has been constructed. This report describes analytical flow sheet, construction of the code, basic equations, method to treat the input data, estimation of the preliminary analysis.
Tachibana, Yukio
Genshiryoku Nenkan 2005-Nen Ban, p.279 - 287, 2005/00
no abstracts in English
Ohashi, Hirofumi; Inaba, Yoshitomo; Nishihara, Tetsuo; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Hayashi, Koji; Katanishi, Shoji; Takada, Shoji; Ogawa, Masuro; Shiozawa, Shusaku
Journal of Nuclear Science and Technology, 41(3), p.385 - 392, 2004/03
Times Cited Count：17 Percentile：72.33(Nuclear Science & Technology)Prior to construction of a HTTR hydrogen production system, a mock-up test facility was constructed to investigate transient behavior of the hydrogen production system and to establish system controllability. The Mock-up test facility with a full-scale reaction tube is an approximately 1/30 scale model of the HTTR hydrogen production system and an electric heater is used as a heat source instead of a reactor. Before the mock-up test, a performance test of the test facility was carried out in the same pressure and temperature conditions as those of the HTTR hydrogen production system to investigate its performance such as hydrogen production ability, controllability and so on. It was confirmed that hydrogen was stably produced with a hot helium gas about 120Nm
/h which satisfy the design value and thermal disturbance of helium gas during the start-up could be mitigated within the design value by using a steam generator.
Tachibana, Yukio
Genshiryoku Nenkan 2004-Nen Ban, p.79 - 87, 2003/11
no abstracts in English
Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.
JAERI-Tech 2003-034, 129 Pages, 2003/05
JAERI-Tech-2003-034.pdf:7.62MB
no abstracts in English
Nishihara, Tetsuo; Shiozawa, Shusaku; Ogawa, Masuro
IAEA-TECDOC-1236, p.11 - 25, 2001/08
Design and evaluation of heat utilization systems for the high temperature engineering test reactor was carried out as the Coordinated Research Program in the IAEA from 1994 to 1999. The final technical document was published as the TECDOC. The chapter 3, outline of the HTTR, and section 5.2.1, Japanese process design to steam reforming of methane for hydrogen production, were written by JAERI.
Inaba, Yoshitomo; Fumizawa, Motoo*; Tonogochi, Makoto*; Takenaka, Yutaka*
Applied Energy, 67(4), p.395 - 406, 2000/12
Times Cited Count：10 Percentile：50.12(Energy & Fuels)no abstracts in English
Huang, Z.*; Ohashi, Hirofumi; Inagaki, Yoshiyuki
JAERI-Tech 2000-022, p.30 - 0, 2000/03
JAERI-Tech-2000-022.pdf:1.24MB
no abstracts in English
Miyamoto, Yoshiaki; Shiozawa, Shusaku; Ogawa, Masuro; Inagaki, Yoshiyuki; Nishihara, Tetsuo; Shimizu, Saburo
Proceedings of International Hydrogen Energy Forum 2000, 2, p.271 - 278, 2000/00
no abstracts in English
Inaba, Yoshitomo; Inagaki, Yoshiyuki; Hayashi, Koji; *
JAERI-Data/Code 99-009, 93 Pages, 1999/03
JAERI-Data-Code-99-009.pdf:2.74MB
no abstracts in English
*; Miyamoto, Yoshiaki; Akino, Norio; Shiina, Yasuaki; Hishida, Makoto*; Ogawa, Masuro; Fumizawa, Motoo; Inagaki, Yoshiyuki; Takeda, Tetsuaki; Takada, Shoji; et al.
JAERI-Review 98-024, 403 Pages, 1999/01
JAERI-Review-98-024.pdf:17.17MB
no abstracts in English
Inagaki, Yoshiyuki; Takeda, Tetsuaki; Nishihara, Tetsuo; Hada, Kazuhiko; Hayashi, Koji
Nihon Genshiryoku Gakkai-Shi, 41(3), p.250 - 257, 1999/00
Times Cited Count：10 Percentile：60.66(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Nishihara, Tetsuo; Takeda, Tetsuaki; Hada, Kazuhiko; Hayashi, Koji
Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00
no abstracts in English
Inagaki, Yoshiyuki; Haga, Katsuhiro; ; Sekita, Kenji; *; Hino, Ryutaro
Nihon Genshiryoku Gakkai-Shi, 40(1), p.59 - 64, 1998/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro
JAERI-Tech 97-050, 125 Pages, 1997/10
no abstracts in English
Inaba, Yoshitomo; Fumizawa, Motoo; Hishida, Makoto*; *; Takenaka, Yutaka*; Tonogochi, Makoto*
JAERI-Tech 96-057, 132 Pages, 1997/01
no abstracts in English
