Irradiation growth in zirconium and its alloys

Rogerson, A.

doi:10.1016/0022-3115(88)90084-0

Cited by 105 publications

(44 citation statements)

References 16 publications

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“…Some studies have shown the experimental results of texture effects on growth. Rogerson's results are consistent with a 1-3f volume-conserving growth process at high temperatures [9]. And the influence of alloys appears to be quite complex.…”

Section: Irradiation Growth By Texturementioning

confidence: 54%

“…This is thought to result from the partitioning of irradiationinduced interstitials and vacancies between various point defect sinks, such as dislocations, grain boundaries and solute atom traps. The metallurgical factors (texture, grain size, grain shape and dislocation density) affecting irradiation growth are well known from previous studies [2]. The effect of crystallographic texture on irradiation growth is well established and organized.…”

Section: Introductionmentioning

confidence: 95%

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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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Section: Irradiation Growth By Texturementioning

confidence: 54%

Section: Introductionmentioning

confidence: 95%

Mechanical and Irradiation Properties of Zirconium Alloys Irradiated in Hanaro

Kwon¹,

Eom²,

Kim³

et al. 2011

Nuclear Engineering and Technology

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“…A considerable amount of experimental data has been gathered on this phenomenon (Rogerson, 1988), which will be briefly summarized here. Irradiation growth is influenced by microstructural variables such as amount of cold work, residual stresses and alloying additions, as well as by irradiation variables such as flux and temperature.…”

Section: Irradiation Growthmentioning

confidence: 99%

“…Annealed material has considerably lower strain rates, at least in the initial part of irradiation exposure. However, after a Rogerson (1988). The dashed lines show the growth strain for cold-worked (CW) material: the strain is nearly linear with fluence and increases with temperature.…”

Section: Irradiation Growthmentioning

confidence: 99%

Zirconium Alloys in Nuclear Applications

Lemaignan

Motta

2006

Materials Science and Technology

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“…The basic problems in the operation of zirconium alloys under irradiation are due to the presence of radiation growth and radiation creep due to anisotropy of α -zirconium. Used zirconium alloys differ with radiation growth, radiation creep, corrosion resistance, high temperature strength [2]. The experimental results on the formation of gradient corrosion-resistant structural-phase states in materials and fuel claddings of thermal reactors have been considered and summarized [3].…”

mentioning

confidence: 99%

THE FORMATION OF SURFACE LAYERS IN Zr-Fe ALLOYS UNDER ION IRRADIATION

Kirichenko¹,

Kobylnik²,

Kovalenko³

et al. 2017

EEJP

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The study of phase transformations in intermetallic phases, which are released in the form of fine-dispersed inclusions in binary alloys based on zirconium Zr -1.03 at. % Fe; Zr -0.51 at. % Fe; after ion irradiation and subsequent isothermal annealing was carried out. Mössbauer spectroscopy on 57 Fe nuclei in backscattering geometry with registration of internal conversion electrons, X-ray spectral analysis, X-ray diffraction analysis and electron microscopy were used. As a result, the observed segregation and phase composition of the intermetallic phases in the surface layer change under ion irradiation. Subsequent isothermal annealing after irradiation leads to a change in the concentration of inclusions of intermetallic phases and phase modification in the surface layer. Свободы, 4 В работе проведено исследование фазовых превращений в интерметаллических фазах , которые выделяются в виде мелкодисперсных включений в бинарных сплавах на основе циркония после ионного облучения и последующего изотермического отжига. Использовали мессбауэровскую спектроскопию на ядрах 57 Fe в геометрии обратного рассеяния с регистрацией электронов внутренней конверсии, рентгеноспектральный анализ, рентгеноструктурный анализ и электронную микроскопию. В результате обнаруженная сегрегация и фазовый состав интерметаллических фаз в поверхностном слое изменяется при ионном облучении. Последующий изотермический отжиг после облучения приводит к изменению концентрации включений интерметаллических фаз и модификации фаз в поверхностном слое. КЛЮЧЕВЫЕ СЛОВА: цирконий, сплавы, сегрегация, ион, облучение Zirconium alloys such as E-110M, E-125, E-635, Zry-2, Zry-4, M5, ZIRLO have been widely used in nuclear power engineering [1]. The basic problems in the operation of zirconium alloys under irradiation are due to the presence of radiation growth and radiation creep due to anisotropy of α -zirconium. Used zirconium alloys differ with radiation growth, radiation creep, corrosion resistance, high temperature strength [2]. The experimental results on the formation of gradient corrosion-resistant structural-phase states in materials and fuel claddings of thermal reactors have been considered and summarized [3]. The action by high-temperature pulsed plasma flows is effective for changing the surface layer of materials. For example, as applied to E110 and E635 zirconium alloys, new structural-phase states formed by the method of "ion mixing" [3].Such effects are associated with recently discovered gradient materials with high technological properties [4]. Optimization of gradient materials is realized by introducing nanoparticles into the surface layers. In [5] it is found that an increase in the surface concentration of iron atoms in zirconium alloys in a layer up to 0.3 μm thick is associated with an increase in the size of inclusions with an increase in the annealing temperature of the deformed alloys. The amorphization alloys based on zirconium under ion irradiation was observed [6]. The formation of amorphous intermetallic phases on the surface...

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Irradiation growth in zirconium and its alloys

Cited by 105 publications

References 16 publications

Mechanical and Irradiation Properties of Zirconium Alloys Irradiated in Hanaro

Mechanical and Irradiation Properties of Zirconium Alloys Irradiated in Hanaro

Zirconium Alloys in Nuclear Applications

THE FORMATION OF SURFACE LAYERS IN Zr-Fe ALLOYS UNDER ION IRRADIATION

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