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JAEA Reports

Improvement in oil seal performance of Gas Compressor in HTTR

Oyama, Sunao*; Hamamoto, Shimpei; Kaneshiro, Noriyuki*; Nemoto, Takahiro; Sekita, Kenji; Isozaki, Minoru; Emori, Koichi; Ito, Yoshiteru*; Yamamoto, Hideo*; Ota, Yukimaru; et al.

JAEA-Technology 2007-047, 40 Pages, 2007/08

JAEA-Technology-2007-047.pdf:18.83MB

High-Temperature engineering Test Reactor (HTTR) built by Japan Atomic Energy Agency (JAEA) has commonly used reciprocating compressor to extract helium gas and discharge helium gas into primary/secondary coolant helium loop from helium purification system. Rod-seal structure of the compressor is complicated from a prevention coolant leak standpoint. Because of frequently leakage of seal oil in operation, Rod seal structure isn't as reliable as it should be sustainable in the stable condition during long term operation. As a result of investigations, leakage's root is found in that seal were used in a range beyond limit sliding properties of seal material. Therefore a lip of the seal was worn and transformed itself and was not able to sustain a seal function. Endurance test using materials testing facility and verification test using a actual equipment on candidate materials suggest that a seal of fluorine contained resin mixed graphite is potentially feasible material of seal.

Journal Articles

Present status of HTTR and its operational experience

Iyoku, Tatsuo; Nojiri, Naoki; Tochio, Daisuke; Mizushima, Toshihiko; Tachibana, Yukio; Fujimoto, Nozomu

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 8 Pages, 2007/04

A HTGR is particularly attractive because of its capability of producing high temperature helium gas and its inherent safety characteristics. Hence, the HTTR wasconstructed at the Oarai Research Establishment of the Japan Atomic Energy Agency. The HTTR achieved the full power of 30MW and reactor outlet coolant temperature of about 850$$^{circ}$$C on December 7, 2001. After several operation cycles, the HTTR achieved the reactor outlet coolant temperature of 950$$^{circ}$$C on April 19, 2004. It is the highest coolant temperature outside reactor pressure vessel in the world. Extensive tests are planned in the HTTR and a process heat application system will be coupled to the HTTR, where hydrogen will be produced directly from the nuclear energy.

JAEA Reports

Test results of HTTR control system

Motegi, Toshihiro; Iigaki, Kazuhiko; Saito, Kenji; Sawahata, Hiroaki; Hirato, Yoji; Kondo, Makoto; Shibutani, Hideki; Ogawa, Satoru; Shinozaki, Masayuki; Mizushima, Toshihiko; et al.

JAEA-Technology 2006-029, 67 Pages, 2006/06

JAEA-Technology-2006-029.pdf:3.07MB

The plant control performance of the IHX helium flow rate control system, the PPWC helium flow rate control system, the secondary helium flow rate control system, the inlet temperature control system, the reactor power control system and the outlet temperature control system of the HTTR are obtained through function tests and power-up tests. As the test results, the control systems show stable control response under transient condition. Both of inlet temperature control system and reactor power control system shows stable operation from 30% to 100%, respectively. This report describes the outline of control systems and test results.

JAEA Reports

Report of investigation on malfunction of reserved shutdown system in HTTR

Hamamoto, Shimpei; Iigaki, Kazuhiko; Shimizu, Atsushi; Sawahata, Hiroaki; Kondo, Makoto; Oyama, Sunao; Kawano, Shuichi; Kobayashi, Shoichi; Kawamoto, Taiki; Suzuki, Hisashi; et al.

JAEA-Technology 2006-030, 58 Pages, 2006/03

JAEA-Technology-2006-030.pdf:10.69MB

During normal operation of High Temperature engineering Test Reactor (HTTR) in Japan Atomic Energy Agency (JAEA), the reactivity is controlled by the Control Rods (CRs) system which consists of 32 CRs (16 pairs) and 16 Control Rod Drive Mechanisms (CRDMs). The CR system is located in stand-pipes accompanied by the Reserved Shutdown System (RSS). In the unlikely event that the CRs fail to be inserted, the RSS is provided to insert B$$_{4}$$C/C pellets into the core. The RSS shall be designed so that the reactor should be held subcriticality from any operation condition by dropping in the pellets. The RSS consists of B$$_{4}$$C/C pellets, hoppers which contain the pellets, electric plug, driving mechanisms, guide tubes and so on. In accidents when the CRs cannot be inserted, an electric plug is pulled out by a motor and the absorber pellets fall into the core by gravity. A trouble, malfunction of one RSS out of sixteen, occurred during a series of the pre-start up checks of HTTR on February 21, 2005. We investigated the cause of the RSS trouble and took countermeasures to prevent the issue. As the result of investigation, the cause of the trouble was attributed to the following reason: In the motor inside, The Oil of grease of the multiplying gear flowed down from a gap of the oil seal which has been deformed and was mixed with abrasion powder of brake disk. Therefore the adhesive mixture prevented a motor from rotating.

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.

Journal Articles

Distribution of radiocarbon in the southwestern north pacific

Aramaki, Takafumi; Mizushima, Toshihiko; Kuji, Tomoyuki*; Povinec, P. P.*; Togawa, Orihiko

Radiocarbon, 43(2B), p.857 - 867, 2001/03

no abstracts in English

Journal Articles

The Present condition of a tandetron AMS in JAERI-Mutsu

Kitamura, Toshikatsu; Aramaki, Takafumi; Mizutani, Yoshihiko*; Togawa, Orihiko; Mizushima, Toshihiko; Kabuto, Shoji*; Sudo, Kazuhiko*

JAERI-Conf 2000-019, p.26 - 29, 2001/02

no abstracts in English

Journal Articles

The Dirtribution of $$Delta^{14}$$C in the north pacific and the pursuit of the anthropogenic carbon

Aramaki, Takafumi; Watanabe, Shuichi*; Tsunogai, Shizuo*; Kuji, Tomoyuki*; Mizushima, Toshihiko; Togawa, Orihiko

JAERI-Conf 2000-019, p.73 - 75, 2001/02

no abstracts in English

Journal Articles

The AMS facility at the Japan Atomic Energy Research Institute (JAERI)

Aramaki, Takafumi; Mizushima, Toshihiko; Mizutani, Yoshihiko*; Yamamoto, Tadatoshi; Togawa, Orihiko; Kabuto, Shoji*; Kuji, Tomoyuki*; Gottdang, A.*; Klein, M.*; Mous, D. J. W.*

Nuclear Instruments and Methods in Physics Research B, 172(1-4), p.18 - 23, 2000/10

 Times Cited Count:26 Percentile:82.27(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Installation of a tandem-type accelerator mass spectrometer

Mizushima, Toshihiko; Togawa, Orihiko; Mizutani, Yoshihiko*; Kabuto, Shoji*; Yamamoto, Tadatoshi

JAERI-Tech 2000-004, p.68 - 0, 2000/02

JAERI-Tech-2000-004.pdf:7.24MB

no abstracts in English

JAEA Reports

Journal Articles

Wake of nuclear ship Mutsu, present status of R & D and future plan, Part II; Design of N.S.Mutsu

Yamaki, Jikei; Fujikawa, Seigo; ; Ishida, Toshihisa; Mizushima, Toshihiko; ; Sakamoto, Yukio;

Genshiryoku Kogyo, 38(4), p.13 - 28, 1992/04

no abstracts in English

JAEA Reports

Effects of ships vibration and motion on plant parameters; Report on sea trials of nuclear ship MUTSU made first in Japan

Kakuta, Tsunemi; Kitamura, Toshikatsu; Mizushima, Toshihiko; ; ; ; ; ;

JAERI-M 92-034, 82 Pages, 1992/03

JAERI-M-92-034.pdf:2.36MB

no abstracts in English

JAEA Reports

Japan nuclear ship sea trial

; Kitamura, Toshikatsu; Mizushima, Toshihiko; Kakuta, Tsunemi; ; ; ; ; ;

JAERI-M 91-212, 107 Pages, 1992/01

JAERI-M-91-212.pdf:3.05MB

no abstracts in English

Journal Articles

Gamma irradiation tests of part of connector for nuclear instrumentation of nuclear ship Mutsu

; Mizushima, Toshihiko; Kakuta, Tsunemi; Nakazawa, Toshio

DEI-91-136, p.59 - 68, 1991/12

no abstracts in English

Journal Articles

Gamma irradiation tests of co-axial cables for nuclear instrumentation of nuclear ship Mutsu

; Kakuta, Tsunemi; Mizushima, Toshihiko; Nakazawa, Toshio;

EIM-89-124, p.27 - 36, 1989/12

no abstracts in English

Oral presentation

Operation of the High-Temperature Engineering Test Reactor

Fujimoto, Nozomu; Nojiri, Naoki; Tachibana, Yukio; Mizushima, Toshihiko

no journal, , 

A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive because of its capability of producing high temperature helium gas and its inherent safety characteristics. Hence, the High Temperature Engineering Test Reactor (HTTR) was successfully constructed at the Oarai Research Establishment of the Japan Atomic Energy Agency. The HTTR achieved the reactor outlet coolant temperature of 950$$^{circ}$$C on April 19, 2004. It is the highest coolant temperature outside reactor pressure vessel in the world. This is one of the major milestones in HTGR development of high temperature nuclear process heat application. Extensive tests are planned in the HTTR and a process heat application system will be coupled to the HTTR, where hydrogen will be produced directly from the nuclear energy. This paper gives an overview of the HTTR Project focusing on the latest results from the HTTR test and the future test plan using the HTTR.

Oral presentation

Overhaul of reserved shutdown system in HTTR

Shimizu, Atsushi; Hamamoto, Shimpei; Kobayashi, Shoichi; Ishii, Yoshiki; Iigaki, Kazuhiko; Inoi, Hiroyuki; Kawamoto, Taiki; Mizushima, Toshihiko; Nakazawa, Toshio

no journal, , 

no abstracts in English

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