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Search Results: Records 1-7 displayed on this page of 7
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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

https://doi.org/10.3327/jnst.19.158
 Times Cited Count：19 Percentile：85.33(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Zircaloy Cladding Embrittlement Due to Inner Surface Oxidation During A LOCA - Inner Surface Oxidation Experiment Using A Simulated Fuel Rod (2) - Influences of UO$$_{2}$$-Steam Reaction and Rapid Cooling

; ;

JAERI-M 9681, 19 Pages, 1981/09

JAERI-M-9681.pdf:0.8MB

no abstracts in English

JAEA Reports

Zircaloy Cladding Embrittlement Due to Inner Surface Oxdation During a LOCA, Inner Surface Oxidation Experiment Using a Simulated Fuel Rod (1)

; ;

JAERI-M 9445, 37 Pages, 1981/04

JAERI-M-9445.pdf:1.82MB

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

https://doi.org/10.3327/jnst.18.705
 Times Cited Count：39 Percentile：95.72(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Zircaloy Cladding Embrittlement by Stream Oxidation in Stagnant Stream Condition

; ;

JAERI-M 8081, 26 Pages, 1979/02

JAERI-M-8081.pdf:1.16MB

no abstracts in English

7 (Records 1-7 displayed on this page)
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