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Department of HTTR Project
JAERI-Review 2003-013, 98 Pages, 2003/05
JAERI-Review-2003-013.pdf:4.98MB
The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30 MW and the reactor outlet coolant temperature of 850/950
C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated-particle fuel, graphite for core components, and helium gas for primary coolant. The HTTR, which locates at the south-west area of 5000 m
in the Oarai Research Establishment, had been constructed since 1991 before accomplishing the first criticality on November 10, 1998. Rise to power tests of the HTTR started in September, 1999 and the rated thermal power of 30 MW and the reactor outlet coolant temperature of 850C was attained in December 2001. JAERI received the certificate of pre-operation test, that is, the commissioning license for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R&Ds on HTGRs from FY1999 to 2001.
Fujikawa, Seigo; Okubo, Minoru; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.361 - 372, 2002/12
no abstracts in English
Ashikagaya, Yoshinobu; Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji
JAERI-Tech 2001-092, 76 Pages, 2002/01
JAERI-Tech-2001-092.pdf:11.72MB
no abstracts in English
Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Hisaki
JAERI-Tech 2001-001, 101 Pages, 2001/02
JAERI-Tech-2001-001.pdf:5.15MB
no abstracts in English
Tanaka, Toshiyuki; Okubo, Minoru; Fujikawa, Seigo; Mogi, Haruyoshi; Suzuki, Hiroshi
Proc. of PBNC'98, 2, p.1203 - 1210, 1998/00
no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; ; *; *; Inoue, Kimio*
Journal of Nuclear Science and Technology, 30(2), p.116 - 130, 1993/02
Times Cited Count：7 Percentile：60.37(Nuclear Science & Technology)no abstracts in English
; Miyoshi, Yoshinori; *; *
JAERI-M 92-172, 62 Pages, 1992/11
no abstracts in English
; ; Kitamura, Toshikatsu; *; ; ;
Genshiryoku Kogyo, 38(4), p.32 - 50, 1992/04
no abstracts in English
Umezawa, Hirokazu
Isotope News, 0(453), p.28 - 29, 1992/03
no abstracts in English
JAERI-M 91-113, 52 Pages, 1991/07
no abstracts in English
*; Kyoya, Masahiko; *; *
JAERI-M 91-021, 61 Pages, 1991/03
no abstracts in English
; Ishida, Toshihisa; ; Sakamoto, Yukio; Kyoya, Masahiko;
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.515 - 526, 1991/00
no abstracts in English
Ishida, Toshihisa; Kusunoki, Tsuyoshi; *; *; Inoue, Kimio*; ;
Proc. of the lst JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.521 - 526, 1991/00
no abstracts in English
Japan-USSR on Nuclear Ship, 37 Pages, 1990/11
no abstracts in English
; ; *; *
JAERI-M 8010, 121 Pages, 1978/12
no abstracts in English
Iyoku, Tatsuo
no journal, ,
Since I got employment in the Japan Atomic Energy Agency in 1979, I have consistently engaged in high-temperature gas-cooled reactor development and experienced from HTTR design to its in-service operation. Based on this experience, I will make recommendations for future high-temperature gas-cooled reactor development at the conference. Typical recommendations are as follows: In future HTGR research and developments, HTTR should be positioned as a COF (center of facility).
