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Journal Articles

Journal Articles

Oxidation kinetics of silicon carbide in steam at temperature range of 1400 to 1800$$^{circ}$$C studied by laser heating

Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Bottomley, D.; Furumoto, Kenichiro*

Journal of Nuclear Materials, 529, p.151939_1 - 151939_8, 2020/02

AA2019-0197.pdf:1.61MB

 Times Cited Count:7 Percentile:81.95(Materials Science, Multidisciplinary)

Journal Articles

Oxidation of silicon carbide in steam studied by laser heating

Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Furumoto, Kenichiro*; Sato, Hisaki*; Ishibashi, Ryo*; Yamashita, Shinichiro

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), p.670 - 674, 2019/09

Journal Articles

Oxidation kinetics of Zry-4 fuel cladding in mixed steam-air atmospheres at temperatures of 1273 - 1473 K

Negyesi, M.; Amaya, Masaki

Journal of Nuclear Science and Technology, 54(10), p.1143 - 1155, 2017/10

 Times Cited Count:6 Percentile:59.69(Nuclear Science & Technology)

Journal Articles

The Effect of oxidation and crystal phase condition on the ballooning and rupture behavior of Zircaloy-4 cladding tube-under transient-heating conditions

Narukawa, Takafumi; Amaya, Masaki

Journal of Nuclear Science and Technology, 53(1), p.112 - 122, 2016/01

 Times Cited Count:4 Percentile:42.19(Nuclear Science & Technology)

JAEA Reports

Effects of temperature history during cooling process on cladding ductility reduction under lost of coolant accident conditions

Udagawa, Yutaka; Nagase, Fumihisa; Fuketa, Toyoshi

JAERI-Research 2005-020, 40 Pages, 2005/09

JAERI-Research-2005-020.pdf:4.63MB

In order to investigate effects of quenching temperature and cooling rate before quench on cladding ductility reduction under LOCA conditions, samples cut from non-irradiated 17$$times$$17-type Zircaloy-4 cladding tubes for PWRs were oxidized in steam at 1373 and 1473 K, cooled at 2 to 7 K/s, and quenched at 1073 to 1373 K. The quenched samples were subjected to ring compression test, microstructure observation, and Vickers hardness test. Quenching temperature decrease obviously increased area fraction of $$alpha$$ phase in the radial cross section of the cladding, and reduced cladding ductility. Slow-cooling rate decrease increased unit size and hardness of precipitated $$alpha$$ phase, while $$alpha$$ phase area fraction and cladding ductility were not significantly changed. $$alpha$$ phase is harder than the surrounding region in the metallic layer and has higher oxygen content, indicating its low ductility. Consequently, increase in the area fraction in the cladding is a main cause of the reduction in cladding ductility with decrease in the quenching temperature.

Journal Articles

Oxidation kinetics of low-Sn Zircaloy-4 at the temperature range from 773 to 1573 K

Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi

Journal of Nuclear Science and Technology, 40(4), p.213 - 219, 2003/04

 Times Cited Count:60 Percentile:95.9(Nuclear Science & Technology)

Isothermal oxidation tests in flowing steam were performed on low-Sn Zircaloy-4 cladding tubes over the wide temperature range from 773 to 1573 K in order to obtain oxidation kinetics applicable to various loss-of-coolant accident conditions of LWRs. The oxidation generally obeys a parabolic rate law for the examined time range up to 3600s at temperatures from 1273 K to 1573K, and for a limited time range up to 900s from 773 to 1253 K. A cubic rate law is preferable for evaluating the longer-term oxidation at 1253 K and below. The parabolic rate law constant and the cubic rate law constant for measured weight gain were evaluated at every examined temperature, and Arrhenius-type equations were determined in order to describe the temperature dependence of the rate constants. It was indicated that the change of the oxidation kinetics from the cubic to the parabolic rate and the discontinuities in the temperature dependence of the rate constants are caused by the monoclinic/tetragonal phase transformation of ZrO$$_{2}$$.

Journal Articles

Steam annealing effects on CV characteristics of MOS structures on (11$$bar{2}$$0) face of 4H-SiC

Yoshikawa, Masahito; Oshima, Takeshi; Ito, Hisayoshi; Takahashi, Kunimasa*; Kitabatake, Makoto*

Materials Science Forum, 353-356, p.635 - 638, 2001/00

no abstracts in English

Journal Articles

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

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

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

no abstracts in English

Journal Articles

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

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

 Times Cited Count:33 Percentile:93.07(Nuclear Science & Technology)

no abstracts in English

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

JAEA Reports

Extent of Oxide Layer at the Inner Surface of Burst Cladding

; ; ; ;

JAERI-M 9475, 22 Pages, 1981/05

JAERI-M-9475.pdf:0.99MB

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

Products at the surface of zircaloy cladding under a LOCA condition

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Journal of Nuclear Materials, 95(3), p.303 - 306, 1980/00

 Times Cited Count:13 Percentile:93.77(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Acceleration of zircaloy-steam reaction rate by deformation under high temperature transient

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Journal of Nuclear Science and Technology, 17(3), p.243 - 245, 1980/00

 Times Cited Count:5 Percentile:70.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Prospects of alloy design for zircaloy cladding

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Zairyo Kagaku, 16(4,5), p.173 - 179, 1979/00

no abstracts in English

Journal Articles

Oxidation of zircaloy-4 under high temperature steam atmosphere and its effect on ductility of cladding

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Journal of Nuclear Science and Technology, 15(8), p.589 - 596, 1978/08

 Times Cited Count:57

no abstracts in English

27 (Records 1-20 displayed on this page)