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Journal Articles

High-temperature test for BGaN semiconductor neutron detectors

Okita, Shoichiro; Sakurai, Tatsuhiro*; Ezaki, Iwao*; Takagi, Katsuyuki*; Nakano, Takayuki*; Hino, Masahiro*

KURNS Progress Report 2023, P. 97, 2024/07

Journal Articles

Stress corrosion cracking growth behavior of in-core materials

Kaji, Yoshiyuki

Proceedings of KNS-AESJ Joint Summer School 2005 for Students and Young Researchers, 2, p.221 - 228, 2005/08

For core internals, the main research items are intergranular stress corrosion cracking (IGSCC) of low carbon stainless steel in core shrouds and primary loop recirculation pipes in boiling water reactor (BWR), and irradiation assisted stress corrosion cracking (IASCC) which is caused by the synergistic effects of neutron and gamma-ray radiation, corrosion by high temperature water, and the residual and/or applied stresses. This paper describes the current status and typical results of fundamental study for mechanistic understanding of IGSCC and IASCC, development of IASCC evaluation technology for BWR plants based on post-irradiation IASCC test data as a part of METI's national project, in-pile IASCC tests.

JAEA Reports

Results and future plans for the innovative basic research on high temperature engineering

HTTR Utilization Research Committee

JAERI-Review 2001-016, 232 Pages, 2001/05

JAERI-Review-2001-016.pdf:12.01MB

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

Development of a new method for high temperature in-core characterization of solid surfaces

Yamawaki, Michio*; Suzuki, Atsushi*; Yokota, Toshihiko*; Luo, G.*; Yamaguchi, Kenji*; Hayashi, Kimio

Proceedings of 1st Information Exchange Meeting on Basic Studies on High-Temperature Engineering, p.357 - 364, 1999/09

no abstracts in English

Journal Articles

Transient behavior of low enriched uranium silicide plate type fuel for research reactors during reactivity initiated accident conditions

Yanagisawa, Kazuaki; ; Horiki, Oichiro; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo

Journal of Nuclear Science and Technology, 30(8), p.741 - 751, 1993/08

 Times Cited Count:4 Percentile:44.63(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Pre-pulse irradiation examination, NSRR pulse irradiation and post-pulse irraditaiton examination of MH-1 fuel rod

Yanagisawa, Kazuaki; Sasajima, Hideo; Katanishi, Shoji; ; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.

JAERI-M 91-220, 186 Pages, 1992/01

JAERI-M-91-220.pdf:7.02MB

no abstracts in English

Journal Articles

An Evaluation of the influence of fuel design parameters and burnup on pellet/cladding interaction for boiling water reactor fuel rod through in-core diameter measurement

Nuclear Technology, 73, p.361 - 377, 1986/00

 Times Cited Count:2 Percentile:32.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Study on the Behaviors of Resistance Strain Gages in Nuclear Radiation Environments

; ; Kitahara, Tanemichi;

JAERI-M 6200, 22 Pages, 1975/08

JAERI-M-6200.pdf:0.79MB

no abstracts in English

JAEA Reports

In-core Neutron Flux Measurement with a Fission Chamber

; ; Shiraishi, Tadao; ; ; ; ;

JAERI-M 4566, 23 Pages, 1971/09

JAERI-M-4566.pdf:0.76MB

no abstracts in English

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