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Journal Articles

Embrittlement of Zircaloy-4 due to oxidation in environment of stagnant steam

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Journal of Nuclear Science and Technology, 19(2), p.158 - 165, 1982/00

 Times Cited Count:19 Percentile:85.33(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated LOCA condition

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Journal of Nuclear Science and Technology, 18(9), p.705 - 717, 1981/00

 Times Cited Count:39 Percentile:95.72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Ductility loss of zircaloy cladding by inner-surface oxidation during high temperature transient

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Journal of Nuclear Science and Technology, 18(10), p.802 - 810, 1981/00

 Times Cited Count:14 Percentile:83.2(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Hydrogen Absorption by Zircaloy Cladding being Caused by Inner-Surface Oxidation

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JAERI-M 8497, 27 Pages, 1979/10

JAERI-M-8497.pdf:1.1MB

no abstracts in English

JAEA Reports

Journal Articles

Zircaloy-clad fuel rod burst behavior under simulated loss-of-coolant condition in pressurized water reactors

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Journal of Nuclear Science and Technology, 15(10), p.736 - 744, 1978/10

 Times Cited Count:16

no abstracts in English

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