Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries

Huang, Yan; Maier, Benjamin; Allen, Todd R.

doi:10.1016/j.nucengdes.2014.06.001

Cited by 20 publications

(6 citation statements)

References 18 publications

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“…Examination after bulk proton irradiations at 800 • C to 0.7 and 1.5 dpa showed that both defect diameter and density increased with dose, matching the present results for that dose range [7]. Bulk proton irradiations performed at 800 • C [10], however, resulted in defect densities that were an order of magnitude lower and defect diameters that were twice as large for ZrC 0.9 than those found in the present study. A couple of differences between the two experiments may account for the differences in results.…”

Section: Discussionsupporting

confidence: 86%

“…Some investigation into the effects of ZrC x stoichiometry on the irradiation response have been conducted using bulk proton irradiations at 800 • C to 1-3 dpa [10] and 1125 • C to 2 dpa [11]. However, there has been no systematic investigation into the effect of temperature on the accumulation of radiation damage in ZrC, and no irradiations have been performed at cryogenic temperatures where athermal reactions can be studied.…”

Section: Introductionmentioning

confidence: 99%

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In situ ion irradiation of zirconium carbide

Ulmer

Motta

Kirk

2015

Journal of Nuclear Materials

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Zirconium carbide (ZrC) is a candidate material for use in one of the layers of TRISO coated fuel particles to be used in the Generation IV high-temperature, gas-cooled reactor, and thus it is necessary to study the effects of radiation damage. The microstructural evolution of ZrC x under irradiation was studied in situ using the Intermediate Voltage Electron Microscope (IVEM) at Argonne National Laboratory. Samples of nominal stoichiometries ZrC 0.8 and ZrC 0.9 were irradiated in situ using 1 MeV Kr 2+ ions at various irradiation temperatures (T = 20 K-1073 K). In situ experiments made it possible to continuously

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Section: Discussionsupporting

confidence: 86%

Section: Introductionmentioning

confidence: 99%

In situ ion irradiation of zirconium carbide

Ulmer

Motta

Kirk

2015

Journal of Nuclear Materials

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“…They noted that the sub-stoichiometric ZrC samples (C/Zr<1) had an improved irradiation resistant microstructure compered to hyper-stoichiometric ZrC samples (C/Zr>1). Huang et al [26] reported that ZrCx material after a proton irradiation at 800 °C was highly decorated with dislocation loops. The loop size and density depended both on dose and stoichiometry with ZrC 1.2 showing quite different behaviour compared to the lower C-ratio stoichiometries.…”

Section: Zrcmentioning

confidence: 99%

Optimisation of the synthesis of ZrC coatings in a radio frequency induction-heating chemical vapour deposition system using response surface methodology

et al. 2017

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A chemical vapour deposition process using radio frequency induction heating operating at atmospheric pressure was developed for the deposition of ZrC coatings. The precursors utilised in this process were zirconium tetrachloride and methane as zirconium and carbon sources respectively, in an excess of hydrogen. Additionally, a stream of argon was used to, first, remove oxygen from the reactor and then to sweep the vapourised ZrCl 4 at 300 °C to the reaction chamber. The ZrC coatings were deposited on graphite substrates at substrate temperatures in the range of 1200 °C-1600 °C. The molar ratio of CH 4 /ZrCl 4 was varied from 6.04 to 24.44. Before the start of the deposition process, thermodynamic feasibility analysis for the growth of ZrC at atmospheric pressure was also carried out. Response surface methodology was applied to optimise the process parameters for the deposition of ZrC coatings. A central composite design was used to investigate the effects of temperature and molar ratio of CH 4 /ZrCl 4 on the growth rate, atomic ratio of C/Zr and crystallite size of ZrC 2 coatings. Quadratic statistical models for growth rate and crystallite size were established. The atomic ratio of C/Zr followed a linear trend. It was found that an increase in substrate temperature and CH 4 /ZrCl 4 ratio resulted in increased growth rate of ZrC coatings. The carbon content (and concomitantly the atomic ratio of C/Zr) in the deposited coatings increased with temperature and molar ratio of CH 4 /ZrCl 4. The substrate temperature of 1353.3°C and the CH 4 /ZrCl 4 molar ratio of 10.41 was determined as the optimal condition for growing near-stoichiometry ZrC coatings. The values were 1.03, 6.05 µm/h and 29.8 nm for C/Zr atomic percentage ratio, growth rate and average crystallite size respectively.

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“…It was found that the dislocation loops transitioned from Frank to prismatic loops in ZrC at higher temperatures. Some investigations on the effects of stoichiometry on the irradiation response in ZrC x have been carried out using proton irradiations to 1–3 dpa at 800 °C [19] and 2 dpa 1125 °C [20]. In our previous study [21], we found that the superstructure modulation of the ordered carbon vacancies for Zr 2 C in ZrC 0.6 was destroyed under Au ion irradiation.…”

Section: Introductionmentioning

confidence: 99%

Microstructure Evolution in ZrCx with Different Stoichiometries Irradiated by Four MeV Au Ions

Wei

Wang

et al. 2019

Materials

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ZrCx ceramics with different stoichiometries were irradiated under a four MeV Au ion beam in doses of 2 × 1016 ions/cm2 at room temperature, corresponding to ~130 dpa. Grazing incidence, X-ray diffraction and transmission electron microscopy were performed to study the radiation damage and microstructure evolution in ZrCx ceramics. With the decrease in C/Zr ratio, the expansion of ZrCx lattice became smaller after irradiation. Some long dislocation lines formed at the near-surface, while, in the area with the greatest damage (depth of ~400 nm), large amounts of dislocation loops formed in ZrC, ZrC0.9 and ZrC0.8. With the increase in carbon vacancy concentration, the size of the dislocation loops gradually decreased. Few dislocation loops were found in ZrC0.7 after irradiation, and only black-dot defects were found in the area with the greatest damage. For the non-stoichiometric ZrCx, with the increase of the intrinsic vacancies, the number of C interstitials caused by irradiation decreased, and the recombination barrier of C Frenkel pairs reduced. The above factors will reduce the total number of C interstitials after cascade cooling, suppressing the formation and growth of dislocation loops, which is significant for the enhancement of the tolerance of radiation damage.

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Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries

Cited by 20 publications

References 18 publications

In situ ion irradiation of zirconium carbide

In situ ion irradiation of zirconium carbide

Optimisation of the synthesis of ZrC coatings in a radio frequency induction-heating chemical vapour deposition system using response surface methodology

Microstructure Evolution in ZrCx with Different Stoichiometries Irradiated by Four MeV Au Ions

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