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Journal Articles

Fracture-mechanics-based evaluation of failure limit on pre-cracked and hydrided Zircaloy-4 cladding tube under biaxial stress states

Li, F.; Mihara, Takeshi; Udagawa, Yutaka; Amaya, Masaki

Journal of Nuclear Science and Technology, 57(6), p.633 - 645, 2020/06

 Times Cited Count:1 Percentile:23.17(Nuclear Science & Technology)

Journal Articles

Effects of ballooning and rupture on the fracture resistance of Zircaloy-4 fuel cladding tube after LOCA-simulated experiments

Yumura, Takanori; Amaya, Masaki

Annals of Nuclear Energy, 120, p.798 - 804, 2018/10

 Times Cited Count:4 Percentile:48.98(Nuclear Science & Technology)

Journal Articles

Application of Bayesian optimal experimental design to reduce parameter uncertainty in the fracture boundary of a fuel cladding tube under LOCA conditions

Narukawa, Takafumi; Yamaguchi, Akira*; Jang, S.*; Amaya, Masaki

Proceedings of 14th International Conference on Probabilistic Safety Assessment and Management (PSAM-14) (USB Flash Drive), 10 Pages, 2018/09

Journal Articles

The Effect of azimuthal temperature distribution 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(11), p.1758 - 1765, 2016/11

 Times Cited Count:7 Percentile:62.67(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.

JAEA Reports

Influence of hydrogen absorption and neutron irradiation on mechanical properties of zircaloy-4 and MDA (Joint research)

Nagase, Fumihisa; Sugano, Mitsuteru*; Ozawa, Masaaki*; Komatsu, Kazushi*; Furuta, Teruo*

JAERI-Research 2001-008, 61 Pages, 2001/03

JAERI-Research-2001-008.pdf:2.62MB

no abstracts in English

JAEA Reports

High-pressurization-rate burst test of hydrided zircaloy-4 fuel cladding at 620K

Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi

JAERI-Research 2000-046, 31 Pages, 2000/12

JAERI-Research-2000-046.pdf:3.72MB

no abstracts in English

JAEA Reports

High-pressurization-rate burst test of hydrided Zircaloy-4 fuel cladding at room temperature

Nagase, Fumihisa; ; Uetsuka, Hiroshi

JAERI-Research 98-064, 25 Pages, 1998/11

JAERI-Research-98-064.pdf:2.17MB

no abstracts in English

Journal Articles

Hydrogen generation during cladding/coolant interactions under reactivity initiated accident conditions

Fuketa, Toyoshi;

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.271 - 277, 1991/00

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: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

; ;

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

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