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Journal Articles

Using LiF crystals for high-performance neutron imaging with micron-scale resolution

Faenov, A.*; Matsubayashi, Masahito; Pikuz, T.*; Fukuda, Yuji; Kando, Masaki; Yasuda, Ryo; Iikura, Hiroshi; Nojima, Takehiro; Sakai, Takuro; Shiozawa, Masahiro*; et al.

High Power Laser Science and Engineering, 3, p.e27_1 - e27_9, 2015/10

 Times Cited Count:10 Percentile:49.69(Optics)

Journal Articles

Evaluation of water distribution in a small operating fuel cell using neutron color image intensifier

Yasuda, Ryo; Nitto, Koichi*; Konagai, Chikara*; Shiozawa, Masahiro*; Takenaka, Nobuyuki*; Asano, Hitoshi*; Murakawa, Hideki*; Sugimoto, Katsumi*; Nojima, Takehiro; Hayashida, Hirotoshi; et al.

Nuclear Instruments and Methods in Physics Research A, 651(1), p.268 - 272, 2011/09

 Times Cited Count:7 Percentile:48.91(Instruments & Instrumentation)

Neutron radiography is one of useful tools to visualize water behavior in fuel cells under operation. In order to observe the detailed information about the water distribution in MEA and GDL in fuel cells, a high spatial resolution and high sensitivity neutron imaging system are required. We developed an imaging system using the neutron color imaging intensifier and continuously observed water distribution in operating a fuel cell. By using the system, a small type fuel cell under operation was continuously observed at the TNRF in every 20 sec. In the results, the water area was appeared from GDL and MEA, and expanded to the channel of the cathode side. On the other hand, voltage was gradually reduced with the operation time, and steeply dropped. It is considered that voltage drop was caused by blockage of gas flow due to the piling up water in the channel of the cathode side.

Journal Articles

Evaluation of water distribution in a small-sized PEFC by neutron radiography

Yasuda, Ryo; Shiozawa, Masahiro*; Katagiri, Masaki*; Takenaka, Nobuyuki*; Sakai, Takuro; Hayashida, Hirotoshi; Matsubayashi, Masahito

Denki Kagaku Oyobi Kogyo Butsuri Kagaku, 79(8), p.614 - 619, 2011/08

 Times Cited Count:1 Percentile:2.43(Electrochemistry)

Journal Articles

Acceptance test of graphite components in nuclear reactor

Ishihara, Masahiro; Hanawa, Satoshi; Iyoku, Tatsuo; Shiozawa, Shusaku

Tanso, 2001(196), p.39 - 48, 2001/02

no abstracts in English

Journal Articles

Present status of the innovative basic research on high-temperature engineering using the HTTR

Sudo, Yukio; Hoshiya, Taiji; Ishihara, Masahiro; Shibata, Taiju; Ishino, Shiori*; Terai, Takayuki*; Oku, Tatsuo*; Motohashi, Yoshinobu*; Tagawa, Seiichi*; Katsumura, Yosuke*; et al.

Proceedings of OECD/NEA 2nd Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering, p.39 - 50, 2001/00

no abstracts in English

Journal Articles

Application of ultrasonic testing as acceptance test for the graphite component of HTTR

Ishihara, Masahiro; Iyoku, Tatsuo; Shiozawa, Shusaku; *

Transactions of the 13th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT),Vol. I, 0, p.575 - 580, 1995/00

no abstracts in English

Journal Articles

New approach for fracture assessment of graphite

Ishihara, Masahiro; Iyoku, Tatsuo; Shiozawa, Shusaku

Transactions of the 13th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT),Vol. II, 0, p.491 - 496, 1995/00

no abstracts in English

JAEA Reports

Fracture mechanical evaluation of allowable surface flaw for core support graphite components in the HTTR

Ishihara, Masahiro; Iyoku, Tatsuo; Shiozawa, Shusaku; *

JAERI-Tech 94-035, 61 Pages, 1994/12

JAERI-Tech-94-035.pdf:2.89MB

no abstracts in English

JAEA Reports

Eddy current testing on structures of nuclear-grade PGX graphite for acceptance test in HTTR

Ishihara, Masahiro; Saikusa, Akio; Iyoku, Tatsuo; Shiozawa, Shusaku; Ooka, Norikazu; *; *

JAERI-M 93-252, 39 Pages, 1994/01

JAERI-M-93-252.pdf:0.82MB

no abstracts in English

JAEA Reports

Eddy current testing on structures of nuclear-grade IG-110 graphite for acceptance test in HTTR

Ishihara, Masahiro; Saikusa, Akio; Iyoku, Tatsuo; Shiozawa, Shusaku; Ooka, Norikazu; *; *; *; *; *

JAERI-M 93-197, 44 Pages, 1993/09

JAERI-M-93-197.pdf:1.06MB

no abstracts in English

Journal Articles

Development of irradiation-induced stress analysis code-system for graphite components in gas-cooled reactor

Ishihara, Masahiro; Iyoku, Tatsuo; Shiozawa, Shusaku; *; Takikawa, Noboru*

Proc. of the 12th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. C; SMiRT 12, p.167 - 172, 1993/00

no abstracts in English

Journal Articles

Coupling effect of core-bottom structure and core graphite blocks in HTTR

Iyoku, Tatsuo; Futakawa, Masatoshi; Shirai, Hiroshi*; Shiozawa, Shusaku; Ishihara, Masahiro; Takikawa, Noboru*

Proc. of the 12th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. K; SMiRT 12, p.97 - 102, 1993/00

no abstracts in English

JAEA Reports

Verification of thermal-irradiation stress analytical code VIENUS of graphite block

Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku; Minato, Kazuo

JAERI-M 92-019, 64 Pages, 1992/02

JAERI-M-92-019.pdf:1.31MB

no abstracts in English

JAEA Reports

An Explication of design data of the graphite structural design code for core support components of High Temperature Engineering Test Reactor

Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku

JAERI-M 91-154, 39 Pages, 1991/10

JAERI-M-91-154.pdf:0.73MB

no abstracts in English

JAEA Reports

An Explication of design data of the graphite structural design code for core components of High Temperature Engineering Test Reactor

Ishihara, Masahiro; Iyoku, Tatsuo; *; ; Shiozawa, Shusaku

JAERI-M 91-153, 51 Pages, 1991/10

JAERI-M-91-153.pdf:1.0MB

no abstracts in English

JAEA Reports

An Inspection standard of graphite for the High Temperature Engineering Test Reactor

Toyota, Junji; Iyoku, Tatsuo; Ishihara, Masahiro; Takikawa, Noboru; Shiozawa, Shusaku

JAERI-M 91-102, 61 Pages, 1991/07

JAERI-M-91-102.pdf:1.49MB

no abstracts in English

JAEA Reports

An Explication of the graphite structural design code of core components for the High Temperature Engineering Test Reactor

Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku

JAERI-M 91-083, 31 Pages, 1991/05

JAERI-M-91-083.pdf:1.04MB

no abstracts in English

JAEA Reports

An Explication of the graphite structural design code of core support components for the High Temperature Engineering Test Reactor

Iyoku, Tatsuo; Ishihara, Masahiro; *; Shiozawa, Shusaku

JAERI-M 91-070, 32 Pages, 1991/05

JAERI-M-91-070.pdf:0.94MB

no abstracts in English

Journal Articles

Graphite core structures and their structural design criteria in the HTTR

Iyoku, Tatsuo; Shiozawa, Shusaku; Ishihara, Masahiro; ; Oku, Tatsuo*

Nucl. Eng. Des., 132, p.23 - 30, 1991/00

 Times Cited Count:23 Percentile:89.72(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Visualization of water distribution in fuel cell using neutron radiography

Hayashida, Hirotoshi; Yasuda, Ryo; Honda, Mitsunori; Nojima, Takehiro; Iikura, Hiroshi; Sakai, Takuro; Matsubayashi, Masahito; Shiozawa, Masahiro*; Nitta, Takahiro*; Isogai, Yuji*

no journal, , 

no abstracts in English

25 (Records 1-20 displayed on this page)