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Takada, Shoji; Iigaki, Kazuhiko; Shinohara, Masanori; Tochio, Daisuke; Shimazaki, Yosuke; Ono, Masato; Yanagi, Shunki; Nishihara, Tetsuo; Fukaya, Yuji; Goto, Minoru; et al.
Nuclear Engineering and Design, 271, p.472 - 478, 2014/05
Times Cited Count：8 Percentile：53.31(Nuclear Science & Technology)JAEA has carried out research and development to establish the technical basis of HTGRs using HTTR. To connect hydrogen production system to HTTR, it is necessary to ensure the reactor dynamics when thermal-load of the system is lost. Thermal-load fluctuation test is planned to demonstrate the reactor dynamics stability and to validate plant dynamics codes. It will be confirmed that the reactor become stable state during losing a part of removed heat at heat-sink. A temperature coefficient of reactivity is one of the important parameters for core dynamics calculations, and changes with burnup because of variance of fuel compositions. Measurement of temperature coefficient of reactivity has been conducted to confirm the validity of calculated temperature coefficient of reactivity. A LOFC test using HTTR has been carried out to verify the inherent safety under the condition of LOFC while the reactor shut-down system disabled.
Ono, Masato; Goto, Minoru; Shinohara, Masanori; Nojiri, Naoki; Tochio, Daisuke; Shimazaki, Yosuke; Yanagi, Shunki
JAEA-Technology 2013-001, 35 Pages, 2013/03
JAEA-Technology-2013-001.pdf:6.04MB
The temperature coefficient measurements of the HTTR have been carried out. In the beginning of the operation, temperature coefficients at the reactor power of 30 kW and 9 MW were obtained through 1999 to 2000. The operation days of the HTTR fuel reached 375 Effective Full Power Days (EFPD), which is over a half of design operation days (660 EFPD). The temperature coefficient measurements were conducted at the same power levels of 30 kW and 9 MW to evaluate burnup effect. Also, to measure temperature coefficient in high accuracy, technique of core temperature control and technique of core temperature homogenization were established.
Takada, Shoji; Yanagi, Shunki; Iigaki, Kazuhiko; Shinohara, Masanori; Tochio, Daisuke; Shimazaki, Yosuke; Ono, Masato; Sawa, Kazuhiro
UTNL-R-0483, p.9_1 - 9_10, 2013/03
no abstracts in English
Shimazaki, Yosuke; Shinohara, Masanori; Ono, Masato; Yanagi, Shunki; Tochio, Daisuke; Iigaki, Kazuhiko
JAEA-Technology 2012-010, 24 Pages, 2012/05
JAEA-Technology-2012-010.pdf:6.92MB
It is necessary to confirm that the temperature of water cooling panel of the vessel cooling system (VCS) is controlled under the allowable working temperature during the safety demonstration test because the water cooling panel temperature rises due to stop of cooling water circulation pumps. Therefore, several temporary thermocouples are relocated to the side cooling panel outlet ring header of VCS and the water cooling panel near the stabilizers of RPV in order to observe the temperature change of VCS. The relocated thermocouples can measure the temperature change with starting of the water circulation pumps of VCS. So it is confirmed that the relocated thermocouples can observe the VCS temperature change in the safety demonstration test.
Ono, Masato; Tochio, Daisuke; Shinohara, Masanori; Shimazaki, Yosuke; Yanagi, Shunki; Iigaki, Kazuhiko
JAEA-Technology 2012-004, 46 Pages, 2012/03
JAEA-Technology-2012-004.pdf:3.17MB
Tohoku-Pacific Ocean Earthquake occurred on March 11th 2011 and the earthquake intensity of an upper 5 on the Japanese scale was observed in Oarai town. HTTR conducted the confirmation test on cold state in order to ensure the facilities/instruments of reactor building operate normally. In this test, the plant data in the facilities/instruments start up phase and continue steady operation phase were measured and compared with the previous operation data, and the soundness of facilities/instruments is evaluated. As a result, the facilities/instruments operate normally and keep safety and performance of the HTTR were ensured. This paper reports the evaluation of the plant data.
Shinohara, Masanori; Yanagi, Shunki; Tochio, Daisuke; Shimazaki, Yosuke; Nojiri, Naoki; Owada, Hiroyuki; Sato, Nao; Sagawa, Hiroshi; Umeda, Masayuki
JAEA-Technology 2011-029, 39 Pages, 2011/12
JAEA-Technology-2011-029.pdf:3.03MB
JAEA plans and performs the safety demonstration test using the HTTR to develop High Temperature Gas Reactor technologies. Cold test of the loss of forced cooling was conducted prior to the safety demonstration test, to check test procedure and plant behavior. Cold test consists of two phases, Phase1, 1 or 2 Vessel Cooling System (VCS) terminates, in the Phase2, all 3 Gas circulators and 1 VCS terminates. Cold test could confirm test process, and obtain data necessary to analysis and 2-dimensional horizontal sectional model analysis was verified to simulate actual measurement value.
Ono, Masato; Tochio, Daisuke; Shinohara, Masanori; Shimazaki, Yosuke; Yanagi, Shunki; Iigaki, Kazuhiko
no journal, ,
Tohoku-Pacific Ocean Earthquake occurred on March 11th 2011 and the earthquake intensity of an upper 5 on the Japanese scale was observed in Oarai town. HTTR conducted the confirmation test on cold state in order to ensure the facilities/instruments of reactor building operate normally. In this test, the plant data in the facilities/instruments start-up phase and continue steady operation phase were measured and compared with the previous operation data, and the soundness of facilities/instruments is evaluated. As a result, in after the earthquake, the facilities/instruments operate normally and the reactor cooling function of the HTTR were ensured.
Shimazaki, Yosuke; Shinohara, Masanori; Ono, Masato; Yanagi, Shunki; Tochio, Daisuke; Iigaki, Kazuhiko
no journal, ,
no abstracts in English
Onishi, Yoshihiro; Kamiya, Koji; Kuramochi, Masaya; Yanagi, Shunki; Honda, Atsushi; Kizu, Kaname; Koide, Yoshihiko; Yoshida, Kiyoshi
no journal, ,
no abstracts in English
Natsume, Kyohei; Murakami, Haruyuki; Yanagi, Shunki; Kizu, Kaname; Yoshida, Kiyoshi
no journal, ,
Valve Boxes (VBs) and Coil Terminal Boxes (CTBs) will be fabricated as magnet shared components and be installed on the cryostat of JT-60SA. VB is for distributing cryogens to superconducting magnets, cryopumps, and thermal shields. CTB includes the interface between high temperature superconducting current leads and power supply bus bars. In this presentation, attachment methods of thermal sensors on the cryogen pipes in vacuum VB or CTB are described. An Experiment to measure the helium in the pipe has been conducted using the two different attachment methods. The experimental results are compared and estimated by considering measurement accuracy and productivity.
