Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Ashikagaya, Yoshinobu; Kawasaki, Tomokatsu; Yoshino, Toshiaki; Ishida, Keiichi
JAERI-Tech 2005-010, 81 Pages, 2005/03
JAERI-Tech-2005-010.pdf:16.65MB
no abstracts in English
Sakaba, Nariaki; Nakagawa, Shigeaki; Furusawa, Takayuki; Tachibana, Yukio
JAERI-Tech 2004-045, 67 Pages, 2004/04
JAERI-Tech-2004-045.pdf:4.74MB
Safety demonstration tests using the HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for the VHTR, which is one of the Generation IV reactors. In the safety demonstration tests, the coolant flow reduction test by tripping one or two out of three gas circulators is being performed between FY2002 and FY 2005 and by tripping all the three gas circulators will be conducted after FY2006. This paper describes the structural integrity assessment of the primary pressurised water cooler after one and two gas circulators run down. Also, the possibility of natural convection in the primary coolant after all the three gas circulator stopped was evaluated by the operation data of the reactor-scram test performed during the rise-to-power tests.
Ueta, Shohei; Emori, Koichi; Tobita, Tsutomu*; Takahashi, Masashi*; Kuroha, Misao; Ishii, Taro*; Sawa, Kazuhiro
JAERI-Research 2003-025, 59 Pages, 2003/11
JAERI-Research-2003-025.pdf:2.53MB
In the safety design requirements for the High Temperature Engineering Test Reactor (HTTR) fuel, it is determined that "the as-fabricated failure fraction shall be less than 0.2%" and "the additional failure fraction shall be small through the full service period". Therefore the failure fraction should be quantitatively evaluated during the HTTR operation. In order to measure the primary coolant activity, primary coolant radioactivity signals the in safety protection system, the fuel failure detection (FFD) system and the primary coolant sampling system are provided in the HTTR. The fuel and fission product behavior was evaluated based on measured data in the rise-to-power tests (1) to (4). The measured fractional releases are constant at 2
10
up to 60% of the reactor power, and then increase to 710 at full power operation. The prediction shows good agreement with the measured value. These results showed that the release mechanism varied from recoil to diffusion of the generated fission gas from the contaminated uranium in the fuel compact matrix.
-energy analysis system for fuel and fission gas behavior during High Temperature Engineering Test Reactor operationUeta, Shohei; Tobita, Tsutomu*; Takahashi, Masashi*; Sawa, Kazuhiro
JAERI-Tech 2002-055, 24 Pages, 2002/07
JAERI-Tech-2002-055.pdf:1.04MB
no abstracts in English
; Kumada, Hiroaki; Kaminaga, Fumito*
Nihon Genshiryoku Gakkai-Shi, 42(4), p.325 - 333, 2000/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Sawa, Kazuhiro; Sumita, Junya; Watanabe, Takashi*
JAERI-Data/Code 99-034, 115 Pages, 1999/06
JAERI-Data-Code-99-034.pdf:3.65MB
no abstracts in English
Kunitomi, Kazuhiko; Tachibana, Yukio; *; Nakano, Masaaki*; Saikusa, Akio; Takeda, Takeshi; Iyoku, Tatsuo; ; Sawahata, Hiroaki; Okubo, Minoru; et al.
JAERI-Tech 97-040, 91 Pages, 1997/09
no abstracts in English
Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Ioka, Ikuo*; *
Nuclear Technology, 99, p.90 - 103, 1992/07
Times Cited Count：9 Percentile：65.12(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Suzuki, Kunihiro; Ioka, Ikuo*; Kunitomi, Kazuhiko;
Nihon Kikai Gakkai Rombunshu, B, 57(542), p.3520 - 3525, 1991/10
no abstracts in English
Inagaki, Yoshiyuki; Fujimoto, Nozomu; Motoki, Yasuo; Iyoku, Tatsuo; Maruyama, So; Shiozawa, Shusaku
JAERI-M 90-223, 30 Pages, 1990/12
no abstracts in English
Suzuki, Katsuo;
JAERI-M 83-191, 22 Pages, 1983/11
no abstracts in English
*; *; *; Okamoto, Yoshizo; *
Journal of Nuclear Science and Technology, 17(6), p.397 - 403, 1980/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
Chitaniumu, Jirukoniumu, 25(4), p.167 - 178, 1977/04
no abstracts in English
JAERI-M 6505, 18 Pages, 1976/04
no abstracts in English
; ; ; ; *; ; ; ; Ikezoe, Yasumasa;
JAERI-M 4630, 17 Pages, 1971/11
no abstracts in English
