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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:0 Percentile:100(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:3 Percentile:44.17(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

Uncertainty quantification of fracture boundary of pre-hydrided Zircaloy-4 cladding tube under LOCA conditions

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

Nuclear Engineering and Design, 331, p.147 - 152, 2018/05

 Times Cited Count:1 Percentile:77.66(Nuclear Science & Technology)

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:6 Percentile:33.74(Nuclear Science & Technology)

JAEA Reports

Effect of solid boric acid on the high temperature oxidation behavior of Zircaloy-4

Komiyama, Daisuke; Amaya, Masaki

JAEA-Research 2016-013, 20 Pages, 2016/08

JAEA-Research-2016-013.pdf:6.05MB

The boric acid in the coolant may precipitate on the fuel cladding surface in the case that the blockage of coolant flow path etc. occurs and/or the cooling of fuel becomes insufficient during a LOCA (Loss-Of-Coolant Accident) in PWRs. While there is much knowledge about the compatibility between Zircaloy-4 and boric acid under normal operation conditions, such knowledge under high temperature condition, e.g. LOCA, has not been sufficient. In this study, isothermal heating tests were carried out by using Zircaloy-4 plates with solid boric acid in various atmospheres at up to 900$$^{circ}$$C; and the stability of boric acid, the reaction between Zircaloy-4 and boric acid and the effect of solid boric acid on the high temperature oxidation behavior of Zircaloy-4 were investigated. From the results obtained, it was suggested that, if boric acid anhydride remained on the surface of Zircaloy-4, the boric acid anhydride prevented the surface of Zircaloy-4 from contacting oxidizing atmosphere and mitigated the high-temperature oxidation of Zircaloy-4. In the case that solid boric acid adhered to the surface of pre-oxidized Zircaloy-4 and they have been heated up to high temperature, it was indicated that the solid boric acid penetrated into the gaps in the pre-oxide layer and the penetrated solid boric acid mitigated the oxidation of Zircaloy-4 thereafter.

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:49.49(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

JAEA Reports

Interaction between silver and zircaloy-4 at high temperatures

Nagase, Fumihisa; ; Uetsuka, Hiroshi; Furuta, Teruo

JAERI-M 92-179, 31 Pages, 1992/11

JAERI-M-92-179.pdf:2.66MB

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

酸素/アルゴン混合気中におけるジルカロイ-4の高温酸化速度論

Uetsuka, Hiroshi; P.Hofman*

Journal of Nuclear Materials, 168, p.47 - 57, 1989/00

 Times Cited Count:19 Percentile:13.27(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Zircaloy-4 oxidition behavior in steam-hydrogen and steam-argon mixtures from 1000 to 1500$$^{circ}$$C

Uetsuka, Hiroshi; ; Kawasaki, Satoru

Severe Accidents in Nuclear Power Plants, Vol. 2, p.99 - 108, 1988/00

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:15 Percentile:20.17(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects of rod pre-pressurization on light water reactor fuel behavior during reactivity accident conditions

; ; ;

Journal of Nuclear Science and Technology, 19(4), p.289 - 306, 1982/00

 Times Cited Count:10 Percentile:28.06(Nuclear Science & Technology)

no abstracts in English

29 (Records 1-20 displayed on this page)