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Journal Articles

The Effect of base irradiation on failure behaviors of UO$$_{2}$$ and chromia-alumina additive fuels under simulated reactivity-initiated accidents; A Comparative analysis with FEMAXI-8

Udagawa, Yutaka; Mihara, Takeshi; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Amaya, Masaki

Annals of Nuclear Energy, 139, p.107268_1 - 107268_9, 2020/05

AA2019-0372.pdf:0.81MB

 Times Cited Count:3 Percentile:34.82(Nuclear Science & Technology)

Journal Articles

Hydride morphology and hydrogen embrittlement of Zircaloy fuel cladding used in NSRR/HBO experiment

Nagase, Fumihisa; Uetsuka, Hiroshi

Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.677 - 684, 1997/03

no abstracts in English

JAEA Reports

Status and task of the study on the hydrogen embrittlement of zirconium alloys

Nagase, Fumihisa; *; Komatsu, Kazushi*; Furuta, Teruo

JAERI-Review 95-012, 122 Pages, 1995/08

JAERI-Review-95-012.pdf:4.42MB

no abstracts in English

Journal Articles

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

; ;

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

 Times Cited Count:22 Percentile:87.4(Nuclear Science & Technology)

no abstracts in English

Journal Articles

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

; ;

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

 Times Cited Count:39 Percentile:95.7(Nuclear Science & Technology)

no abstracts in English

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