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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
JNC TN9440 2000-008, 79 Pages, 2000/08
JNC-TN9440-2000-008.pdf:2.33MB
This report summarizes the operating and irradiatlon data of the experimental reactor "JOYO" 35th cycle. Irradiation tests in the 35th cycle are as follows: (1)C-type irradiation rig (C4F) (a)High burnup performance test of advanced austenitic stainless steel cladding fuel pins (in collaboration with France) (2)C-type irradiation rig (C6D) (a)Large diameter fuel pins irradiation tests (3)Core Materials Irradiation Rig (CMIR-5) (a)Cladding tube materials irradiation tests for "MONJU" (4)Structure Materials Irradiation Rigs (SMIR) (a)Decision of material design base standard of structure materials for prototype reactor and large scale reactor (5)Upper core structure irradiation Plug Rig (UPR-1-5) (a)Upper core neutron spectrum effect and accelerated irradiation effect (6)SurVeillance un-instrument Irradiation Rig (SVIR) (a)Confimation of surveillance irradiation condition for "JOYO" (b)Material irradiation tests (based on a contract with universities) The maximum burnup driver assembly "PFD253" reached 67,600 MWd/t (pin average).
Tanaka, Toshiyuki; Okubo, Minoru; Fujikawa, Seigo; Mogi, Haruyoshi; Suzuki, Hiroshi
Proc. of PBNC'98, 2, p.1203 - 1210, 1998/00
no abstracts in English
; Kawai, Masashi; ; ; ; Okubo, Toshiyuki;
PNC TN9410 94-094, 69 Pages, 1994/03
As the final step of development of a control rod guide system (rod guider), it has been conducted to display information concerning the rod guider operation and the current plant conditions on a CRT in Japanese, to tell information for operators and to predict more accurately the stroke of each control rod to be driven at a reactor power adjustment operation since 1992, in oder to improve a function of man-machine interface of the rod guider. The development of the rod guider was completed with the following good results as expected. (1)The function of man-machine interface of the rod guider was improved to display information on a CRT in Japanese. (2)The voice guidance contributed to obtain higher operational reliability and to lower the load on the operators. (3)The rod guider provided the same function as operation manuals of Joyo because all operation procedures in the manuals were inputted into the rod guider. And the timely operation guides provided by the rod guider evabled non-skilled operators to control the reactor in the same manner as the experienced ones. (4)The difference of the predicted and actual rod stroke to be driven at the reactor power adjustment operation was reduced to less than 
0.2mm by both the existing inverse multiplication method and the experiences gained in the past five reactor power adjustment operations.
Ishida, Toshihisa; Kusunoki, Tsuyoshi; ; ; ; Inoue, Kimio*
Journal of Nuclear Science and Technology, 30(2), p.116 - 130, 1993/02
Times Cited Count：7 Percentile：60.35(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
;
Nihon Genshiryoku Gakkai-Shi, 11(3), p.172 - 183, 1969/00
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).
