Effect of neutron irradiation on the tensile properties of zircaloy-2 and zircaloy-4

Higgy, H.R.; Hammad, F.H.

doi:10.1016/0022-3115(72)90099-2

Cited by 64 publications

(29 citation statements)

References 9 publications

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“…This result is larger than the 570-MPa yield strength reported for the as-received material in the annealed condition and is greater than most values reported in the literature for unirradiated Zircaloy-4. [5][6][7][8][15][16][17] However, it is worth noting that in a study using burst tests, Yagnik et al 18 reported hoop strength similar to those measured here for room temperature tests of unirradiated Zircaloy-4. A more detailed analysis of cladding deformation will be addressed in future efforts.…”

Section: Estimates Of Stress and Strainsupporting

confidence: 77%

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Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

Jaramillo¹,

Hendrich²,

Packan³

2007

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Section: Estimates Of Stress and Strainsupporting

confidence: 77%

“…[5][6][7] Higgy and Hamad 5 reported results for tensile testing of irradiated Zircaloy-2 and Zircaloy-4. Specimens were irradiated at low temperature (<100°C) up to a fluence of 1.43 × 10 20 neutrons/cm 2 (>1 MeV) and at elevated temperature (320-360°C) up to 1.53 × 10 21 neutrons/cm 2 (>1 MeV).…”

Section: Introductionmentioning

confidence: 99%

Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

Jaramillo¹,

Hendrich²,

Packan³

2007

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“…Based on the defects and clusters theory in zirconium alloys, the strength tends to depend on fluence after low temperature irradiation. The hardening effect caused by elevated temperature irradiation showed a reduced dependence on fluence [7]. Some studies have shown that yield strength increases as the fluence increases at each temperature [8].…”

Section: Mechanical Properties Of Zirconium Alloysmentioning

confidence: 99%

“…Some studies have shown that yield strength increases as the fluence increases at each temperature [8]. And with regard to the alloying element difference, the changes in yield strength for zircaloy-2 and zircaloy-4 are shown as a function of the square root of the fluence [7]. The differences between zircaloy-2 and zircaloy-4 in yield strength are within 10%.…”

Section: Mechanical Properties Of Zirconium Alloysmentioning

confidence: 99%

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Mechanical and Irradiation Properties of Zirconium Alloys Irradiated in Hanaro

Kwon¹,

Eom²,

Kim³

et al. 2011

Nuclear Engineering and Technology

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Microstructure, mechanical and biological properties of zirconium alloyed with niobium after severe plastic deformation

Sharkeev

Eroshenko

Kulyashova

et al. 2013

Materialwissenschaft Werkst

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A comparative investigation of microstructure, mechanical and biological properties for zirconium alloyed with niobium in coarse-grained and ultra-fine grained states is presented. The temperature and deformation regimes of multi-stage abc-pressing resulted in ultra-fine grained states with an average size of the structural elements in the range of 0.28 -0.55 lm, depending on the accumulated strain during pressing. The increase of the accumulated strain at each stage of pressing increased the uniformity of the structure. The microhardness increased by 50% with increased accumulated strain during the severe plastic deformation. Between the microhardness and the average size of the structural elements, a linear dependence was found, indicating a Hall-Petch relationship. The alloy had a good biocompatibility as shown by an MTT test with osteoblasts (MG-63 cell line). The good mechanical properties (microhardness) of zirconium alloyed with niobium in the ultra-fine grained state make it suitable for medical applications, e. g. as implant material.Keywords: plastic deformation / microstructure / mechanical properties / biomaterials / alloys / Eine vergleichende Untersuchung der Mikrostruktur sowie der mechanischen und biologischen Eigenschaften einer Zirkonium-Niob-Legierung im grobkörnigen und ultrafeinkörnigen Zustand werden vorgestellt. Durch kombinierte Wärmebehandlung und Deformation beim mehrstufigen ABC-Pressen wurde ein ultrafeinkörniges Material mit durchschnittlichen Abmessungen der Strukturbestandteile von 0,28 -0,55 lm erhalten, je nach akkumulierter mechanischer Spannung. Die Zunahme der akkumulierten mechanischen Spannung bei jedem Pressschritt erhöhte die Einheitlichkeit der Struktur. Die Mikrohärte nahm um 50% mit zunehmender akkumulierter Pressspannung zu. Ein linearer Zusammenhang zwischen der Mikrohärte und der Größe der Strukturelemente spricht für eine Hall-Petch-Beziehung. Die gute biologische Verträglichkeit wurde durch einen MTT-Test mit Osteoblasten (MG-63 Zelllinie) gezeigt. Die guten mechanischen Eigenschaften (insbesondere die Mikrohärte) sprechen für eine gute Anwendbarkeit der Zirkonium-Niob-Legierung im ultrafeinkörnigen Zustand, z.B. als Implantatmaterial.Schlüsselwörter: Plastische Verformung / Mikrostruktur / mechanische Eigenschaften / Biomaterialien /

show abstract

Effect of neutron irradiation on the tensile properties of zircaloy-2 and zircaloy-4

Cited by 64 publications

References 9 publications

Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

Tensile Hoop Behavior of Irradiated Zircaloy-4 Nuclear Fuel Cladding

Mechanical and Irradiation Properties of Zirconium Alloys Irradiated in Hanaro

Microstructure, mechanical and biological properties of zirconium alloyed with niobium after severe plastic deformation

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