Precipitation in Zr-2.5Nb enhanced by proton irradiation

Cann, C.D.; So, C B; Styles, R.C.; Coleman, C.E.

doi:10.1016/0022-3115(93)90089-h

Cited by 51 publications

(23 citation statements)

References 5 publications

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“…For zirconium alloys, irradiation induced defects generally include <a> type dislocation loops (Burgers vector of b ¼ 1=3 < 1120 > ) lying on f1100g planes, and <c> component loops with more complex Burgers vector varieties on the {0002} basal plane [8]. Irradiation can also induce phase transformation such as amorphization of precipitates in Zircaloys and reprecipitation of b or u phases from the a phase [8,10]. However, the generation of dislocation loops probably has the biggest impact on the service life of zirconium components in nuclear reactors.…”

Section: Introductionmentioning

confidence: 98%

Effect of neutron irradiation on deformation mechanisms operating during tensile testing of Zr–2.5Nb

et al. 2016

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Section: Introductionmentioning

confidence: 98%

Effect of neutron irradiation on deformation mechanisms operating during tensile testing of Zr–2.5Nb

et al. 2016

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“…In contrast, in the type i structure, the precipitate size is comparatively constant at around 7 nm at all temperatures except at 500 °C, where perhaps a slight size increase occurs. In some previous reports [23,24], the precipitation of the Nb-rich β phase was observed at irradiation temperatures of 300 °C and 500 °C in α-Zr grains of Zr-2.5Nb pressure tubes by neutron and proton irradiation, respectively. The precipitation of neither β-Nb nor β-Zr is observable in our study.…”

Section: β-Nbmentioning

confidence: 99%

“…To our knowledge, this is the first time the direct dependence of precipitate stability on the surrounding matrix microstructure has been reported. The zirconium alloys used in early studies such as Zircaloy-2 [1][2][3]26], Zircaloy-4 [1,26,27], Zr-2.5Nb [5,7,24,33], and HANA (high performance alloy for nuclear applications) [34] are all in the recrystallized state and do not exhibit martensitic structures. The main differences between type i and type iii structures are the amount of boundaries.…”

Section: Effect Of Structure On the Precipitate Stabilitymentioning

confidence: 99%

Precipitate Stability in a Zr–2.5Nb–0.5Cu Alloy under Heavy Ion Irradiation

Dong

Yao

Wang

et al. 2017

Metals

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Abstract:The stability of precipitates in Zr-2.5Nb-0.5Cu alloy under heavy ion irradiation from 100 • C to 500 • C was investigated by quantitative Chemi-STEM EDS analysis. Irradiation results in the crystalline to amorphous transformation of Zr 2 Cu between 200 • C and 300 • C, but the β-Nb remains crystalline at all temperatures. The precipitates are found to be more stable in starting structures with multiple boundaries than in coarse grain structures. There is an apparent increase of the precipitate size and a redistribution of the alloying element in certain starting microstructures, while a similar size change or alloying element redistribution is not detected or only detected at a much higher temperature in other starting microstructures after irradiation.

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“…5. These particles look like β-Nb particles appearing after either the irradiation of neutron, proton or electron or aging [4][5][6][7]. These needle-like particles appeared on the irradiated Zr-2.5Nb tube independent of the location, which could not be observed in the as-fabricated tube (Fig.…”

Section: Methodsmentioning

confidence: 99%

Microstructure and mechanical property of irradiated Zr−2.5Nb pressure tube in Wolsong unit-1

Kim

Ahn

et al. 2002

Met. Mater. Int.

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With the aim of assessing the degradation of Zr-2.5Nb pressure tubes operating in the Wolsong unit-1 nuclear power plant, characterization tests are being conducted on irradiated Zr-2.5Nb tubes removed after 10-year operation. The examined tube had been exposed to temperatures ranging from 264 to 306 o C and a neutron fluence of 8.9×10 21 n/cm 2 (E>1 MeV) at the maximum. Tensile tests were carried out at temperatures ranging from RT to 300 o C. The density of a-type and c-type dislocations was examined on the irradiated Zr-2.5Nb tube using a transmission electron microscope. Neutron irradiation up to 8.9×10 21 n/cm 2 (E>1 MeV) yielded an increase in a-type dislocation density of the Zr-2.5Nb pressure tube to 7.5×10 14 m −2 , which was highest at the inlet of the tube exposed to the low temperature of 275 o C. In contrast, the c-component dislocation density did not change with irradiation, keeping an initial dislocation density of 0.8×10 14 m −2 over the whole length of the tube. As expected, the neutron irradiation increased mechanical strength by about 17-26% in the transverse direction and by 34-39% in the longitudinal direction compared to that of the unirradiated tube at 300 o C. The change in the mechanical properties with irradiation is discussed in association with the microstructural change as a function of temperature and neutron fluence.

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Precipitation in Zr-2.5Nb enhanced by proton irradiation

Cited by 51 publications

References 5 publications

Effect of neutron irradiation on deformation mechanisms operating during tensile testing of Zr–2.5Nb

Effect of neutron irradiation on deformation mechanisms operating during tensile testing of Zr–2.5Nb

Precipitate Stability in a Zr–2.5Nb–0.5Cu Alloy under Heavy Ion Irradiation

Microstructure and mechanical property of irradiated Zr−2.5Nb pressure tube in Wolsong unit-1

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