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Search Results: Records 1-20 displayed on this page of 73

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Journal Articles

Oxidation of fuel rod under dry storage condition

Nakamura, Jinichi; ; Kikuchi, Teruo; Kawasaki, Satoru

Journal of Nuclear Science and Technology, 32(4), p.321 - 332, 1995/04

https://doi.org/10.3327/jnst.32.321
 Times Cited Count：13 Percentile：76.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Method for estimating peak temperature reached of the TMI-2 vessel lower head by microstructural examination of 308 stainless steel overlay

Tsukada, Takashi; Suzuki, Masahide; Kawasaki, Satoru

Proceedings of Three Mile Island Reactor Pressure Vessel Investigation Project Open Forum, p.151 - 163, 1994/00

no abstracts in English

Journal Articles

Oxidation of UO$$_{2}$$ under dry storage condition

Nakamura, Jinichi; ; Kawasaki, Satoru

Journal of Nuclear Science and Technology, 30(2), p.181 - 184, 1993/02

https://doi.org/10.3327/jnst.30.181
 Times Cited Count：7 Percentile：68.63(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of oxygen partial pressure on oxidation of Zircaloy

Nakamura, Jinichi; ; ; Kawasaki, Satoru

Journal of Nuclear Materials, 200, p.256 - 264, 1993/00

https://doi.org/10.1016/0022-3115(93)90336-W
 Times Cited Count：14 Percentile：78.06(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Behavior of spent fuels under dry storage in oxidizing atmosphere

Kawasaki, Satoru; Nakamura, Jinichi

Low and Intermediate Level Radioactive Waste Management,Vol. 1, p.619 - 629, 1993/00

no abstracts in English

Journal Articles

Thermal and stress analyses of the reactor pressure vessel lower head of the Three Mile Island Unit 2

Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa

Int. J. Press. Vessels Piping, 52, p.25 - 40, 1992/00

https://doi.org/10.1016/0308-0161(92)90057-M
 Times Cited Count：3 Percentile：53.87(Engineering, Multidisciplinary)

no abstracts in English

Journal Articles

Thermal response analyses of the Three Mile Island Unit 2 reactor pressure vessel

Hashimoto, Kazuichiro; Onizawa, Kunio; Kurihara, Ryoichi; Kawasaki, Satoru; Soda, Kunihisa; *

Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. F, p.123 - 128, 1991/08

no abstracts in English

JAEA Reports

None

Ogata, Yoshiaki; *

PNC TN8600 91-002, 13 Pages, 1991/04

PNC-TN8600-91-002.pdf:2.66MB

no abstracts in English

Journal Articles

Behavior of spent fuels under dry storage conditions; Oxidation behavior of spent fuels in air and inert gas loaded with air

Kawasaki, Satoru; Nakamura, Jinichi

IAEA-SR-171, 27 Pages, 1990/00

no abstracts in English

Journal Articles

LWR fuel safety research with paticular emphasis on RIA/LOCA and other conditions

Ichikawa, Michio; ; Kawasaki, Satoru

Journal of Nuclear Science and Technology, 26(1), p.118 - 125, 1989/01

https://doi.org/10.3327/jnst.26.118

no abstracts in English

Journal Articles

Zircaloy-4 oxidition behavior in steam-hydrogen and steam-argon mixtures from 1000 to 1500$$^{circ}$$C

Uetsuka, Hiroshi; ; Kawasaki, Satoru

Severe Accidents in Nuclear Power Plants, Vol. 2, p.99 - 108, 1988/00

no abstracts in English

Journal Articles

Oxidation of zircaloy cladding in air

;

Journal of Nuclear Materials, 140, p.32 - 43, 1986/00

https://doi.org/10.1016/0022-3115(86)90194-7
 Times Cited Count：14 Percentile：79.15(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Oxidation of zircaloy-4 under limited steam supply from 900 to 1,400$$^{circ}$$C

; ;

Journal of Nuclear Science and Technology, 23(10), p.928 - 930, 1986/00

https://doi.org/10.3327/jnst.23.928
 Times Cited Count：5 Percentile：65.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of conservatism of present embrittlement criteria for zircaloy fuel cladding under LOCA

; ;

Zirconium in the Nuclear Industry, p.734 - 746, 1984/00

no abstracts in English

JAEA Reports

Multi-Rod Burst Test Under a Loss-of-Coolant Accident Condition 〔IV〕; Experimental Result of The No.7808 Bundle

; ; ; ;

JAERI-M 83-083, 68 Pages, 1983/06

JAERI-M-83-083.pdf:4.45MB

no abstracts in English

JAEA Reports

Fracture-Bearing Capability of Zircaloy Cladding on Thermal-Shock During the Reflood Stage of a Loss-of-Coolant Accident in LWRs

; ;

JAERI-M 83-070, 49 Pages, 1983/05

JAERI-M-83-070.pdf:1.89MB

no abstracts in English

JAEA Reports

High Temperature Mechanical Properties of Neutron Irradiated Zircaloy-4

;

JAERI-M 83-068, 18 Pages, 1983/04

JAERI-M-83-068.pdf:1.0MB

no abstracts in English

JAEA Reports

Multi-Rod Burst Test Under a Loss-of-Coolant Accident Condition,3; Experimental Resalt of the Bundle No.7807

; ; ; ;

JAERI-M 83-038, 56 Pages, 1983/03

JAERI-M-83-038.pdf:2.8MB

no abstracts in English

Journal Articles

Effect of burst temperature on coolant channel restriction in multirods burst tests

; ; ; ;

Journal of Nuclear Science and Technology, 20(3), p.246 - 253, 1983/00

https://doi.org/10.3327/jnst.20.246
 Times Cited Count：3 Percentile：44.38(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Failure-bearing capability of oxidized zircaloy-4 cladding under simulated loss-of-coolant condition

; ;

Journal of Nuclear Science and Technology, 20(11), p.941 - 950, 1983/00

https://doi.org/10.3327/jnst.20.941
 Times Cited Count：35 Percentile：93.84(Nuclear Science & Technology)

no abstracts in English

73 (Records 1-20 displayed on this page)