Effect of oxygen and fabrication variables on the mechanical properties of Zircaloy tubing

Konishi, Takao; Matsuda, Katsuhiko; Teranishi, Hiroshi

doi:10.1179/cmq.1972.11.1.165

Cited by 8 publications

(2 citation statements)

References 3 publications

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“…Microstructural changes that occur during hot working are primarily governed by the strain and temperature. Dynamic recrystallization and recovery processes are the dominating mechanisms which bring about microstructural changes [12][13][14][15]. In addition, precipitation of the intermetallic phases has been noticed in several cases.…”

Section: By Hot Workingmentioning

confidence: 98%

Microstructural evolution in zirconium based alloys

Tewari

Srivastava

Dey

et al. 2008

Journal of Nuclear Materials

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Section: By Hot Workingmentioning

confidence: 98%

Microstructural evolution in zirconium based alloys

Tewari

Srivastava

Dey

et al. 2008

Journal of Nuclear Materials

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“…These components are full tubes, pressure tubes and calandria tubes which form the bulk of the reactor core of the pressurized heavy water reactor. (PHWR) It has been reported that the deformation rate and the temperature are two important parameters which have significant effect on the development of texture, microstructure and mechanical properties [1,2] . It is therefore essential to study the hot deformation behavior of Zr-4 alloy systematically.…”

Section: Introductionmentioning

confidence: 99%

Characterization of Hot Deformation Behavior of Zr-4 Alloy in Material Application Area

Lin

2012

AMR

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The hot deformation behavior of Zr-4 alloy was studied in the temperature range 650-900°C and strain rate range 0.005-50s-1 using processing maps. The processing maps revealed three domains: the first occurs in the temperature range 780-820°C and strain rate range 0.005-0.05s-1, and has a peak efficiency of 45% at 790°C and 0.005s-1; the mechanism is the dynamic recrystallization. The second occurs in the temperature range greater than 900°C and strain rate range 0.05-0.8s-1, and has a peak efficiency of 40% at 900°C and 0.5s-1, which are the domains of dynamic recovery. In addition, the instability zones of flow behavior can also be recognized by the maps in the temperature range 650-780°C and strain rate range 0.01-0.1s-1, which should be strictly avoided in the processing of the material. Zr-4 alloy is the material for pressure tube applications in nuclear reactors and has better strength and a lower rate of hydrogen uptake compared to other materials under similar service conditions.

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Quantitative characterization of crystallographic textures in zirconium alloys

Knorr

Pelloux

1977

Journal of Nuclear Materials

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Effect of oxygen and fabrication variables on the mechanical properties of Zircaloy tubing

Cited by 8 publications

References 3 publications

Microstructural evolution in zirconium based alloys

Microstructural evolution in zirconium based alloys

Characterization of Hot Deformation Behavior of Zr-4 Alloy in Material Application Area

Quantitative characterization of crystallographic textures in zirconium alloys

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