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Journal Articles

High-temperature continuous operation of the HTTR

Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Kunitomi, Kazuhiko; Hino, Ryutaro; Ogawa, Masuro; Komori, Yoshihiro; Nakazawa, Toshio*; Iyoku, Tatsuo; Fujimoto, Nozomu; Nishihara, Tetsuo; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.290 - 300, 2011/12

A high temperature (950$$^{circ}$$C) continuous operation has been performed for 50 days on the HTTR from January to March in 2010, and the potential to supply stable heat of high temperature for hydrogen production for a long time was demonstrated for the first time in the world. This successful operation could establish technological basis of HTGRs and show potential of nuclear energy as heat source for innovative thermo-chemical-based hydrogen production, emitting greenhouse gases on a "low-carbon path" for the first time in the world.

Journal Articles

50-day long-term high-temperature operation was attained by the HTTR of Japan Atomic Energy Agency

Takada, Shoji; Nishihara, Tetsuo; Iyoku, Tatsuo; Nakazawa, Toshio; Komori, Yoshihiro

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 52(7), P. 387, 2010/07

The 50-day long-term high-temperature operation was successfully attained by the High Temperature Engineering Test Reactor (HTTR) of the Japan Atomic Energy Agency (JAEA), the rated thermal output of 30 MW and the maximum reactor outlet temperature of 950 $$^{circ}$$C, first in the world. The operation was started on January 22 and accomplished on March 13 this year. Many data on the characteristics of reactor core physics and thermal hydraulics, the impurity control in coolant helium gas, the performance of high temperature components and the core internal structure integrity was acquired to establish the HTGR technology basis. The HTGR is expected as a green-house gas emission free heat source of innovative thermo-chemical hydrogen production system. It was demonstrated first in the world that high temperature gas can be stably supplied for long term period. In the next stage, the tests will be carried out to confirm the applicability and the extreme safety performance of HTGR by the HTTR.

Journal Articles

Achievement of coolant temperature of 950$$^{circ}$$C in HTTR

Kawasaki, Kozo; Iyoku, Tatsuo; Tachibana, Yukio; Nakazawa, Toshio; Goto, Minoru

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 8 Pages, 2005/05

High Temperature Engineering Test Reactor (HTTR) achieved a coolant temperature of 950$$^{circ}$$C at reactor outlet with its rated thermal power of 30MW on April 19, 2004. Achievement of the reactor outlet coolant temperature of 950$$^{circ}$$C makes it possible to extend use of high-temperature gas-cooled reactors beyond the field of electric power generation. Not only highly effective power generation with a high-temperature gas turbine system but also hydrogen production from water without emission of carbon dioxide will be possible utilizing the high temperature heat. This report describes the results of the high-temperature test operation of the HTTR.

Journal Articles

Achievement of reactor-outlet coolant temperature of 950$$^{circ}$$C in HTTR

Fujikawa, Seigo; Hayashi, Hideyuki; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo; Nakagawa, Shigeaki; Sakaba, Nariaki

Journal of Nuclear Science and Technology, 41(12), p.1245 - 1254, 2004/12

 Times Cited Count:87 Percentile:97.76(Nuclear Science & Technology)

A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high-temperature helium gas and to its inherent safety characteristics. The High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan, achieved its rated thermal power of 30MW and reactor-outlet coolant temperature of 950$$^{circ}$$C on 19 April 2004. During the high-temperature test operation which is the final phase of the rise-to-power tests, reactor characteristics and reactor performance were confirmed, and reactor operations were monitored to demonstrate the safety and stability of operation. The reactor-outlet coolant temperature of 950$$^{circ}$$C makes it possible to extend high-temperature gas-cooled reactor use beyond the field of electric power. Also, highly effective power generation with a high-temperature gas turbine becomes possible, as does hydrogen production from water. The achievement of 950$$^{circ}$$C will be a major contribution to the actualization of producing hydrogen from water using the high-temperature gas-cooled reactors. This report describes the results of the high-temperature test operation of the HTTR.

Journal Articles

Reactivity control system of the high temperature engineering test reactor

Tachibana, Yukio; Sawahata, Hiroaki; Iyoku, Tatsuo; Nakazawa, Toshio

Nuclear Engineering and Design, 233(1-3), p.89 - 101, 2004/10

 Times Cited Count:9 Percentile:55.79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Demonstration of inherent safety features of HTGRs using the HTTR

Tachibana, Yukio; Nakagawa, Shigeaki; Nakazawa, Toshio; Iyoku, Tatsuo

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 17 Pages, 2004/10

no abstracts in English

Journal Articles

JAERI completed performance tests of the High Temperature Engineering Test Reactor (HTTR) at 950$$^{circ}$$C

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(8), P. 510, 2004/08

no abstracts in English

Journal Articles

High Temperature Engineering Test Reactor (HTTR) of JAERI achieved the reactor outlet helium gas temperature of 950$$^{circ}$$C for the first time in the world

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo

Nihon Genshiryoku Gakkai-Shi, 46(5), P. 301, 2004/05

no abstracts in English

JAEA Reports

Test results of the reactor inlet coolant temperature control system of HTTR

Saito, Kenji; Nakagawa, Shigeaki; Hirato, Yoji; Kondo, Makoto; Sawahata, Hiroaki; Tsuchiyama, Masaru*; Ando, Toshio*; Motegi, Toshihiro; Mizushima, Toshihiko; Nakazawa, Toshio

JAERI-Tech 2004-042, 26 Pages, 2004/04

JAERI-Tech-2004-042.pdf:1.16MB

The reactor control system of HTTR is composed of the reactor power control system, the reactor inlet coolant temperature control system, the primary coolant flow rate control system and so on. The reactor control system of HTTR achieves reactor power 30MW, reactor outlet coolant temperature 850$$^{circ}$$C, reactor inlet coolant temperature 395$$^{circ}$$C under the condition that primary coolant flow rate is fixed. In the Rise-to-Power Test, the performance test of the reactor inlet coolant temperature control system was carried out in order to confirm the control capability of this control system. This report shows the test results of performance test. As a result, the control parameters, which can control the reactor inlet coolant temperature stably during the reactor operation, were successfully selected. And it was confirmed that the reactor inlet coolant temperature control system has the capability of controlling the reactor inlet coolant temperature stably against any disturbances on the basis of operational condition of HTTR.

JAEA Reports

Investigation of automatic shutdown of HTTR on May 21st, 2003

Hirato, Yoji; Saito, Kenji; Kondo, Makoto; Sawahata, Hiroaki; Motegi, Toshihiro; Tsuchiyama, Masaru*; Ando, Toshio*; Mizushima, Toshihiko; Nakazawa, Toshio

JAERI-Tech 2004-037, 33 Pages, 2004/04

JAERI-Tech-2004-037.pdf:4.08MB

HTTR (High Temperature Engineering Test Reactor) was operated from May 6th, 2003 to June 18th, 2003 to obtain operation data in parallel loaded operation mode and in safety demonstration tests. Operated with the reactor power at 60% of the rated power on May 21st, HTTR was automatically scrammed by a signalof "Primary coolant flow rate of the Primary Pressurized Water Cooler (PPWC): Low". The cause of the shutdown was the primary gas circulator (A) automatically stopped. The primary coolant flow rate of the PPWC decresed and reached the scram set value due to the gas circulator stop. As a result of investigation, it became clear that the cause of the gas circulator stop was malfunction of an auxiliary relay which monitored electric power of a circuit breaker in power line of the gas circulator. The cause of malfunction was deterioration of the relay under high temperature condition because the relay was installed beside an electric part which was heated up by electricity.

JAEA Reports

Findings of the reactor automatic shutdown caused by a signal of a primary coolant flow rate of the PPWC:Low in the HTTR

Takamatsu, Kuniyoshi; Nakazawa, Toshio; Furusawa, Takayuki; Homma, Fumitaka; Saito, Kenji; Kokusen, Shigeru; Kamata, Takashi; Ota, Yukimaru; Ishii, Yoshiki; Emori, Koichi

JAERI-Tech 2003-062, 94 Pages, 2003/06

JAERI-Tech-2003-062.pdf:26.47MB

no abstracts in English

JAEA Reports

Test plans of the high temperature test operation at HTTR

Sakaba, Nariaki; Nakagawa, Shigeaki; Takada, Eiji*; Nojiri, Naoki; Shimakawa, Satoshi; Ueta, Shohei; Sawa, Kazuhiro; Fujimoto, Nozomu; Nakazawa, Toshio; Ashikagaya, Yoshinobu; et al.

JAERI-Tech 2003-043, 59 Pages, 2003/03

JAERI-Tech-2003-043.pdf:2.54MB

HTTR plans a high temperature test operation as the fifth step of the rise-to-power tests to achieve a reactor outlet coolant temperature of 950 degrees centigrade in the 2003 fiscal year. Since HTTR is the first HTGR in Japan which uses coated particle fuel as its fuel and helium gas as its coolant, it is necessary that the plan of the high temperature test operation is based on the previous rise-to-power tests with a thermal power of 30 MW and a reactor outlet coolant temperature at 850 degrees centigrade. During the high temperature test operation, reactor characteristics, reactor performances and reactor operations are confirmed for the safety and stability of operations. This report describes the evaluation result of the safety confirmations of the fuel, the control rods and the intermediate heat exchanger for the high temperature test operation. Also, problems which were identified during the previous operations are shown with their solution methods. Additionally, there is a discussion on the contents of the high temperature test operation. As a result of this study, it is shown that the HTTR can safely achieve a thermal power of 30MW with the reactor outlet coolant temperature at 950 degrees centigrade.

JAEA Reports

Research and development for the high-temperature helium-leak detection system, 2; Development of temperature sensors using optical fibre for the HTTR (Joint research)

Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*

JAERI-Tech 2003-041, 106 Pages, 2003/03

JAERI-Tech-2003-041.pdf:6.58MB

In the second stage of the research and development for a high-temperature helium-leak detection system, the temperature sensor using optical fibres was studied. The sensor detects the helium leakage by the temperature inclease surrounded opitical fibre with or without heat insulator. Moreover, the applicability of high temperature equipments as the HTTR system was studied. With the sensor we detected 5.0-20.0 cm$$^{3}$$/s helium leakages within 60 minutes. Also it was possible to detect earlier when the leakage level is at 20.0 cm$$^{3}$$/s.

JAEA Reports

Research and development of a high-temperature helium-leak detection system, 1; Survey on leakage events and current leak detection technology (Joint research)

Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*

JAERI-Review 2002-041, 86 Pages, 2003/03

JAERI-Review-2002-041.pdf:3.21MB

In High Temperature Gas-cooled Reactors (HTGR), the detection of leakage of helium at an early stage is very important for the safety and stability of operations. Since helium is a colourless gas, it is generally difficult to identify the location and the amount of leakage when very little leakage has occurred. The purpose of this R&D is to develop a helium-leak detection system for the high temperature environment appropriate to the HTTR. This system can shorten the time of detection to several hours from about one week in the current detection time. In addition, it can also identify easily the leak location using the optical fibre network. As the first step in the development, this paper describes the result of surveying leakage events at nuclear facilities inside and outside Japan and current gas leakage detection technology to adapt optical fibre detection technology to HTGRs.

JAEA Reports

Research and development for a high-temperature helium-leak detection system, 3; Development of radiation sensors (Joint research)

Sakaba, Nariaki; Nakazawa, Toshio; Kawasaki, Kozo; Urakami, Masao*; Saishu, Sadanori*

JAERI-Research 2003-006, 65 Pages, 2003/03

JAERI-Research-2003-006.pdf:2.89MB

In the final third stage of the research and development for a high-temperature helium-leak detection system, the radiation sensor was developed in order to detect very small helium leakage. Applying the radiation sensor, we proposed not only the direct detection method which uses the detection of FP gas in helium, but also the active method which uses the difference in the radiation absorption between helium and air. From obtained data it was found that we can detect 0.2 cm$$^{3}$$/s leakage within 10 minutes by the active method.

Journal Articles

Rise-to-power test of the HTTR (High Temperature Engineering Test Reactor)

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

JAEA Reports

Rise-to-power test in High Temperature Engineering Test Reactor; Test progress and summary of test results up to 30MW of reactor thermal power

Nakagawa, Shigeaki; Fujimoto, Nozomu; Shimakawa, Satoshi; Nojiri, Naoki; Takeda, Takeshi; Saikusa, Akio; Ueta, Shohei; Kojima, Takao; Takada, Eiji*; Saito, Kenji; et al.

JAERI-Tech 2002-069, 87 Pages, 2002/08

JAERI-Tech-2002-069.pdf:10.12MB

Rise-to-power test in the HTTR has been performed from April 23rd to June 6th in 2000 as phase 1 test up to 10MW, from January 29th to March 1st in 2001 as phase 2 test up to 20MW in the rated operation mode and from April 14th to June 8th in 2001 as phase 3 test up to 20MW in the high temperature test operation mode. Phase 4 test to achieve the thermal reactor power of 30MW started from October 23rd in 2001. On December 7th it was confirmed that the thermal reactor power reached to 30MW and the reactor outlet coolant temperature reached to 850$$^{circ}$$C. JAERI obtained the certificate of pre-operation test from MEXT because all the pre-operation tests by MEXT were passed successfully. From the test results of rise-up-power test up to 30MW, the performance of reactor and cooling system were confirmed, and it was confirmed that an operation of reactor facility could be performed safely. Some problems to be solved were found through tests. By means of solving them, the reactor operation with the reactor outlet coolant temperature of 950$$^{circ}$$C will be achievable.

Journal Articles

JAERI acquired a certificate of the pre-operation test for the High Temperature Engineering Test Reactor (HTTR)

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu

Nihon Genshiryoku Gakkai-Shi, 44(4), P. 310, 2002/04

no abstracts in English

Journal Articles

High Temperature Engineering Test Reactor (HTTR) of JAERI attained the maximum reactor thermal power of 30MW

Kawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Okubo, Minoru; Baba, Osamu

Nihon Genshiryoku Gakkai-Shi, 44(1), P. 2, 2002/01

no abstracts in English

JAEA Reports

Feasibility study on floating nuclear power plant, 2; Safety design study of FNPP (Contract research)

Yabuuchi, Noriaki; Takahashi, Masao*; Nakazawa, Toshio; Sato, Kazuo*; Shimazaki, Junya; Ochiai, Masaaki

JAERI-Research 2000-064, 76 Pages, 2001/02

JAERI-Research-2000-064.pdf:5.88MB

no abstracts in English

23 (Records 1-20 displayed on this page)