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Journal Articles

Improvement of CAMAC control and data aquisition for JT-60 data processing system

Sato, Minoru; Kiyono, Kimihiro; Oshima, Takayuki; Sakata, Shinya; Ozeki, Takahisa; Matsuda, Toshiaki; Nagasaka, Yasushi*; Obata, Takayoshi*

Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 3 Pages, 2005/03

no abstracts in English

Journal Articles

Association of dissolved radionuclides released by the Chernobyl accident with colloidal materials in surface water

Matsunaga, Takeshi; Nagao, Seiya*; Ueno, Takashi; Takeda, Seiji; Amano, Hikaru; Tkachenko, Y.*

Applied Geochemistry, 19(10), p.1581 - 1599, 2004/10

 Times Cited Count:35 Percentile:55.27(Geochemistry & Geophysics)

The association of dissolved $$^{90}$$Sr, $$^{239,240}$$Pu and $$^{241}$$Am with natural colloids was investigated in surface waters in the Chernobyl nuclear accident area by means of ultrafiltration. Results suggest that Pu and Am isotopes were preferentially associated with dissolved humic substances (HS) of high molecular size. A model calculation of the complexation of Pu and Am with HS also supported the above. This study has expanded our understanding of the general role of natural organic colloids in dictating the chemical form of actinides in the surface aquatic environment.

Journal Articles

Construction of a fast real-time visualization system for JT-60 plasma shape

Hoshi, Y.*; Miura, Yushi; Ouchi, K.*; Kakefuda, Toyokazu*; Akiba, K.*; *; Kawamata, Yoichi; Kurihara, Kenichi

Heisei-12-Nendo Tohoku Daigaku Gijutsu Kenkyukai Hokoku, p.425 - 427, 2001/03

no abstracts in English

Journal Articles

Effects of grain size and PCI restraint on the rim structure formation of UO$$_{2}$$ fuels

Une, Katsumi*; Nogita, Kazuhiro*; Suzaka, Yojiro*; Hayashi, Kimio; Ito, Kunio*; Eto, Yoshinori*

International Topical Meeting on Light Water Reactor Fuel Performance, 2, p.775 - 785, 2000/00

no abstracts in English

JAEA Reports

Development of thermocouple re-instrumentation technique for irradiated fuel rod; Techniques for making center hole into UO$$_{2}$$ pellets and thermocouple re-instrumentation to fuel rod

; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.

JAERI-Tech 95-037, 87 Pages, 1995/07

JAERI-Tech-95-037.pdf:5.14MB

no abstracts in English

Journal Articles

Development of re-instrumentation technology for irradiated fuel rod

Saito, Junichi; ; Oyamada, Rokuro

KAERI-NEMAC/TR-32/95, 0, p.125 - 136, 1995/00

no abstracts in English

JAEA Reports

Basic safety research for high burnup fuels in light water reactors

Furuta, Teruo

JAERI-Tech 94-027, 152 Pages, 1994/11

JAERI-Tech-94-027.pdf:6.45MB

no abstracts in English

Journal Articles

Behavior of light water reactor fuel during transient

Yanagisawa, Kazuaki

Dai-8-Kai "Kaku Nenryo, Kaki Semina" Kogi Tekisuto, 38 Pages, 1993/00

no abstracts in English

JAEA Reports

ROSA-III tests on BWR pump suction-line 200% break LOCAs with partial and total ECCS failure; RUN 924(LPCS and one LPCI pump failure), RUN 902(Two LPCI pump failure) and RUN 905(Total ECCS failure)

Kumamaru, Hiroshige; Suzuki, Mitsuhiro; Anoda, Yoshinari; Nakamura, Hideo; Yonomoto, Taisuke; Murata, Hideo

JAERI-M 91-167, 293 Pages, 1991/10

JAERI-M-91-167.pdf:7.69MB

no abstracts in English

Journal Articles

Some investigation on Halden LWR ramp test by FEMAXI-III(PWR version)

Nakamura, Jinichi; Furuta, Teruo; *; *

HPR-339/13, 22 Pages, 1991/00

no abstracts in English

JAEA Reports

Study on fuel deformation during PCIOMR

Yanagisawa, Kazuaki; D.Chen*

JAERI-M 90-187, 23 Pages, 1990/10

JAERI-M-90-187.pdf:0.81MB

no abstracts in English

JAEA Reports

Behavior of water reacter fuel rod

Yanagisawa, Kazuaki

JAERI-M 90-120, 320 Pages, 1990/08

JAERI-M-90-120.pdf:12.75MB

no abstracts in English

Journal Articles

Behavior of PCI-resistant additive fuel for BWR under reactivity initiated accident conditions

Yanagisawa, Kazuaki; ; A.Negrini*; F.Franco*

Journal of Nuclear Science and Technology, 27(1), p.56 - 67, 1990/01

no abstracts in English

JAEA Reports

Study on pellet-cladding interaction of light water reactor fuel

Yanagisawa, Kazuaki

JAERI-M 87-128, 85 Pages, 1987/08

JAERI-M-87-128.pdf:2.66MB

no abstracts in English

JAEA Reports

JAEA Reports

Evaluation Report on CCTF-II Reflood Test C2-9(Run 68); Effect of LPCI Flow Rate

; ; *; *; ; Murao, Yoshio

JAERI-M 87-002, 77 Pages, 1987/02

JAERI-M-87-002.pdf:1.54MB

no abstracts in English

Journal Articles

In-pile eddy current test on PWR fuel rod failed by pellet-cladding interaction

; T.Johnsen*

Journal of Nuclear Science and Technology, 23(8), p.752 - 755, 1986/00

 Times Cited Count:1 Percentile:28.17(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study of pellet-cladding interaction on light water reactor fuel, (II); BWR type fuel rod

; H.Devold*

Nihon Genshiryoku Gakkai-Shi, 28(8), p.771 - 782, 1986/00

 Times Cited Count:2 Percentile:32.47(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of ECC water injection rate effects on reflood phase of PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 22(2), p.93 - 108, 1985/00

 Times Cited Count:4 Percentile:54.56(Nuclear Science & Technology)

no abstracts in English

34 (Records 1-20 displayed on this page)