Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 17 type PWR fuel cladding tube under LOCA-simulated burst conditions

Furumoto, Kenichiro; Udagawa, Yutaka

Journal of Nuclear Science and Technology, 12 Pages, 2022/00

https://doi.org/10.1080/00223131.2022.2116497

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

https://doi.org/10.1016/j.anucene.2018.06.046

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

https://doi.org/10.1016/j.nucengdes.2018.02.037

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 900C; 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.

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 1717-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 phase in the radial cross section of the cladding, and reduced cladding ductility. Slow-cooling rate decrease increased unit size and hardness of precipitated phase, while phase area fraction and cladding ductility were not significantly changed. 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.

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

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

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

https://doi.org/10.1016/0022-3115(89)90563-1

no abstracts in English

Characterigation of Oxide Scales Containing a Metartalle Tetragonal ZrO (Oxide Scales on the Zircaloy-4)

;

JAERI-M 83-132, 15 Pages, 1983/08

JAERI-M-83-132.pdf:0.66MB

no abstracts in English

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

no abstracts in English