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Nakagawa, Shigeaki; Sakaba, Nariaki; Takamatsu, Kuniyoshi; Takada, Eiji*; Tochio, Daisuke; Owada, Hiroyuki*
JAERI-Tech 2005-015, 26 Pages, 2005/03
Safety demonstration tests using the HTTR are in progress since 2002 to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to not only the commercial HTGRs but also the research and development for the VHTR one of the Generation IV reactor candidates. This paper describes the reactivity insertion test (SR-3), the coolant flow reduction test by tripping of gas circulators (S1C-3/S2C-3), and the partial flow loss of coolant test (SF-2) planned in March 2005 with their detailed test method, procedure and results of pre-test analysis. From the analytical results, it was found that the negative reactivity feedback effect of the core brings the reactor power safely to a stable level without a reactor scram.
Nakagawa, Shigeaki; Tachibana, Yukio; Takamatsu, Kuniyoshi; Ueta, Shohei; Hanawa, Satoshi
Nuclear Engineering and Design, 233(1-3), p.291 - 300, 2004/10
Times Cited Count:8 Percentile:48.76(Nuclear Science & Technology)The High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high temperature helium gas and due to its inherent safety characteristics. The High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan, was successfully constructed at the Oarai Research Establishment of the Japan Atomic Energy Research Institute. The HTTR achieved full power of 30MW at a reactor outlet coolant temperature of about 850C on December 7, 2001 during the "rise-to-power tests". Two kinds of tests were carried out during the "rise-to-power tests". One is commissioning test to get operation permit by the government and another is test to confirm a performance of the reactor, heat exchanger, control system. From the test results of the "rise-to-power tests" up to 30MW, the functionality of the reactor and the cooling system were confirmed, and it was also confirmed that an operation of reactor facility can be performed safely.
Nakagawa, Shigeaki; Takamatsu, Kuniyoshi; Tachibana, Yukio; Sakaba, Nariaki; Iyoku, Tatsuo
Nuclear Engineering and Design, 233(1-3), p.301 - 308, 2004/10
Times Cited Count:22 Percentile:79.05(Nuclear Science & Technology)Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) are conducted for demonstrating inherent safety features of High Temperature Gas-cooled Reactors (HTGRs) as well as for providing core and plant transient data for validation of HTGR safety analysis codes. The safety demonstration tests are divided to the first phase and second phase tests. In the first phase tests, simulation tests of anticipated operational occurrences and anticipated transients without scram (ATWS) are conducted. The second phase tests will simulate accidents such as a depressurization accident (loss of coolant accident). The first phase tests simulating reactivity insertion events and coolant flow reduction events started in FY 2002. The first phase safety demonstration tests will continue until FY 2005, and the second phase tests will be carried out from FY 2006.
Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Shinozaki, Masayuki
Nucl. Eng. Des., 166(2), p.179 - 190, 1996/00
Times Cited Count:21 Percentile:83.9(Nuclear Science & Technology)no abstracts in English
Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi; Okumura, Keisuke
Journal of Nuclear Science and Technology, 32(9), p.855 - 867, 1995/09
Times Cited Count:4 Percentile:43.23(Nuclear Science & Technology)no abstracts in English
Nakagawa, Shigeaki; Sawa, Kazuhiro; Ohashi, Kazutaka*
Journal of Nuclear Science and Technology, 30(6), p.579 - 588, 1993/06
Times Cited Count:1 Percentile:18.76(Nuclear Science & Technology)no abstracts in English
*; Anoda, Yoshinari; Murata, Hideo; Yonomoto, Taisuke; *; Kukita, Yutaka
JAERI-M 91-076, 34 Pages, 1991/05
no abstracts in English
*; Anoda, Yoshinari; Murata, Hideo; Yonomoto, Taisuke; Kukita, Yutaka; *
Thermal Hydraulics of Advanced Nuclear Reactors, p.85 - 89, 1990/11
no abstracts in English
Kunitomi, Kazuhiko; Nakagawa, Shigeaki; Fujimoto, Nozomu; Shindo, Masami; Sudo, Yukio
The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.281 - 286, 1990/10
no abstracts in English
Yamashita, Kiyonobu; Zinza, Keisuke*
JAERI-M 90-153, 48 Pages, 1990/09
no abstracts in English
C.P.C.Wong*; E.T.Cheng*; R.L.Creedon*; J.A.Leuer*; K.R.Schultz*; S.P.Grotz*; N.M.Ghoniem*; M.Z.Hasan*; R.C.Martin*; F.Najmabadi*; et al.
Proc. of IEEE 13th Symp. on Fusion Engineering, Vol. 2, p.1035 - 1038, 1989/00
no abstracts in English
Koizumi, Yasuo; ; Tasaka, Kanji
UTNL-R-0218, p.40 - 48, 1988/00
no abstracts in English