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Journal Articles

Fabrication process qualification of TF Insert Coil using real ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06

 Times Cited Count:0 Percentile:0(Engineering, Electrical & Electronic)

Journal Articles

Transient response of charge collection by single ion strike in 4H-SiC MESFETs

Onoda, Shinobu; Iwamoto, Naoya; Ono, Shuichi*; Katakami, Shuji*; Arai, Manabu*; Kawano, Katsuyasu*; Oshima, Takeshi

IEEE Transactions on Nuclear Science, 56(6), p.3218 - 3222, 2009/12

 Times Cited Count:18 Percentile:74.76(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

Handling of HTTR second driver fuel elements in assembling and storage working

Tomimoto, Hiroshi; Kato, Yasushi; Owada, Hiroyuki; Sato, Nao; Shimazaki, Yosuke; Kozawa, Takayuki; Shinohara, Masanori; Hamamoto, Shimpei; Tochio, Daisuke; Nojiri, Naoki; et al.

JAEA-Technology 2009-025, 29 Pages, 2009/06

JAEA-Technology-2009-025.pdf:21.78MB

The first driver fuel of the HTTR (High Temperature Engineering test Reactor) was loaded in 1998 and the HTTR reached first criticality state in the same year. The HTTR has been operated using the first driver fuel for a decade. In Fuel elements assembling, 4770 of fuel rods which consist of 12 kinds of enrichment uranium are loaded into 150 fuel graphite blocks for HTTR second driver fuel elements. Measures of prevention of fuel rod miss loading, are employed in fuel design. Additionally, precaution of fuel handling on assembling are considered. Reception of fuel rods, assembling of fuel elements and storage of second driver fuels in the fresh fuel storage rack in the HTTR were started since June, 2008. Assembling, storage and pre-service inspection were divided into three parts. The second driver fuel assembling was completed in September, 2008. This report describes concerns of fuel handling on assembling and storage work for the HTTR fuel elements.

JAEA Reports

Operating experiences since rise-to-power test in High Temperature Engineering Test Reactor (HTTR)

Tochio, Daisuke; Watanabe, Shuji; Motegi, Toshihiro; Kawano, Shuichi; Kameyama, Yasuhiko; Sekita, Kenji; Kawasaki, Kozo

JAEA-Technology 2007-014, 62 Pages, 2007/03

JAEA-Technology-2007-014.pdf:9.74MB

The rise-to-power test of the High Temperature Engineering Test Reactor (HTTR) was begun in April 2000. The reactor thermal power of 30 MW, which is the maximum thermal power of the HTTR, and the reactor outlet coolant temperature of 850$$^{circ}$$C in normal operation was achieved in middle of December 2001. After that reactor thermal power of 30 MW a reactor outlet coolant temperature of 950$$^{circ}$$C was achieved in the final rise-to-power test at April 2004. After receiving the operation permit, the safety demonstration tests were conducted to demonstrate inherent safety features of the HTGRs. This paper summarizes the HTTR operating experiences for five years since rise-to-power test that were catalogued into three categories, (1) Operating experience pertaining to new gas cooled reactor design, (2) Operating experience for improvement of the performance, (3) Operating experience due to fail of system and components.

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

Power distributions in the High Temperature Engineering Test Reactor (HTTR) by measuring gross gamma ray from the fuel assemblies

Nojiri, Naoki; Shimakawa, Satoshi; Takamatsu, Kuniyoshi; Ishii, Yoshiki; Kawano, Shuichi; Kobayashi, Shoichi; Kawamoto, Taiki; Iyoku, Tatsuo

JAERI-Tech 2003-086, 136 Pages, 2003/11

JAERI-Tech-2003-086.pdf:8.67MB

To provide a basis for determination of the actual core power distribution, The power distribution experiments by measuring gross gamma ray emitted from fission products in the fuel assemblies were performed. The fuel assemblies were not spent condition but in-service condition. The averaged burn up was about 4,400 MWD/t. The gamma ray of a fuel assembly was measured with a GM counter under a temporary fuel withdrawing situation from the core during shutdown state. Uncertainties of the determination were from 3 to 6 percent in axial distribution per one fuel compact and within about 4 percent in radial and axial distribution of the core per one fuel assembly. It was concluded that the power distribution of the HTTR is almost equivalent to the expected power-profile shaping. Calculation of gamma ray distribution was performed by ORIGEN-2 code based the power distribution obtained by the Monte Carlo MVP code. The calculation results show good agreement with the experimental ones. The method, procedure, analysis, correction, determination and comparison are described in this report.

Journal Articles

Test results of the SMES model coil; Cool-down and thermal characteristics

Hamada, Kazuya; Kato, Takashi; Kawano, Katsumi; *; *; *; Imahashi, Koichi*; Otsu, K.*; Tajiri, F.*; Ouchi, T.*; et al.

Teion Kogaku, 33(7), p.467 - 472, 1998/00

no abstracts in English

Journal Articles

Construction and commissioning test results of the test facility for the ITER CS model coil

Nakajima, Hideo; Hiyama, Tadao; Kato, Takashi; Kawano, Katsumi; Isono, Takaaki; Sugimoto, Makoto; Koizumi, Norikiyo; ; Nunoya, Yoshihiko; Matsui, Kunihiro; et al.

Fusion Technology, 30, p.1248 - 1252, 1996/12

no abstracts in English

Journal Articles

Cryogenic system for CS test facility

Kato, Takashi; ; Kawano, Katsumi; Hiyama, Tadao; *; *; *; Otsu, K.*; Matsui, Kunihiro; Tsuji, Hiroshi

NIFS-PROC-28, 0, p.33 - 36, 1996/09

no abstracts in English

Journal Articles

Performance study of the cryogenic system for ITER CS model coil

Kato, Takashi; Hamada, Kazuya; Kawano, Katsumi; Matsui, Kunihiro; Hiyama, Tadao; Nishida, Kazuhiko*; Honda, Tadaaki*; Taneda, Masanobu*; Sekiguchi, Shuichi*; Otsu, Kiichi*; et al.

ICEC16/ICMC Proceedings, p.127 - 130, 1996/00

no abstracts in English

Journal Articles

Design and construction of long cryogenic piping lines

Kawano, Katsumi; Kato, Takashi; ; Matsui, Kunihiro; Hiyama, Tadao; *; *; *; Otsu, K.*; *; et al.

Proc. of 16th Int. Cryogenic Engineering Conf. /Int. Cryogenic Materials Conf., 0, 4 Pages, 1996/00

no abstracts in English

Journal Articles

Final design of a cryogenic system for the ITER CS model coil

; *; Kato, Takashi; Kawano, Katsumi; Hiyama, Tadao; *; *; Otsu, K.*; *; Tsuji, Hiroshi

Cryogenics, 34(Suppl.), p.65 - 68, 1994/00

no abstracts in English

JAEA Reports

None

Haga, Tetsuya; ; ; ; Nagai, Shuichiro; *

PNC TN8410 92-064, 143 Pages, 1992/04

PNC-TN8410-92-064.pdf:7.67MB

None

JAEA Reports

None

; ; ; ; Nagai, Shuichiro; Uno, Hiroki*

PNC TN8410 92-225, 44 Pages, 1992/03

PNC-TN8410-92-225.pdf:1.65MB

None

JAEA Reports

Determination of the long-lived nuclides in biological shielding concrete, ion exchange resine and fuel storage pool water of JPDR

Takeishi, Hideyo; ; ; Kono, Nobuaki; ; Yonezawa, Chushiro; Hatakeyama, Mutsuo;

JAERI-M 89-224, 45 Pages, 1990/01

JAERI-M-89-224.pdf:1.13MB

no abstracts in English

Oral presentation

$$gamma$$-ray irradiation effects on the I-V characteristics of 4H-SiC MESFET

Onoda, Shinobu; Iwamoto, Naoya; Ono, Shuichi*; Katakami, Shuji*; Arai, Manabu*; Kawano, Katsuyasu*; Oshima, Takeshi

no journal, , 

no abstracts in English

Oral presentation

Optimization of V and Nb content of high Cr steel focused on the ductility /toughness for fast reactor and its product performance

Obara, Satoshi; Nagae, Yuji; Asayama, Tai; Kono, Keita*; Funakoshi, Yoshihiko*; Ishikura, Shuichi*; Urata, Kazuhiro*

no journal, , 

no abstracts in English

Oral presentation

Fabrication of insert coil with ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

no journal, , 

no abstracts in English

18 (Records 1-18 displayed on this page)
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