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Dmitry Terentyev

Publications and source records attributed to Dmitry Terentyev.

2 recordsLinked to original sources

CuCrZr heat-sink irradiation performance reveals new challenges for thermonuclear fusion reactors

Commercial fusion energy requires materials that survive intense neutron bombardment whilst extracting extreme heat loads for conversion to electricity. The CuCrZr alloy, the leading heat-sink material for fusion reactors, derives its strength from a fine dispersion of nano-precipitates formed during prime-ageing heat-treatment. Whether this precipitation-hardening strategy can withstand fusion-relevant irradiation remains untested. Here we show, combining in situ transmission electron microscopy under heavy-ion irradiation and He implantation with thermodynamic and transmutation modelling, that the hardening precipitates dissolve under two opposing kinetic regimes: ballistic dissolution dominates at low temperatures, whilst dissolution and re-precipitation dominate at high temperatures. Although the accelerated dose rates inherent to ion irradiation shift the balance between ballistic mixing and thermal back-diffusion relative to reactor conditions, precipitate degradation at both kinetic extremes indicates that the prime-aged microstructure is unlikely to remain unaltered under prolonged neutron exposure. He bubbles and Kr-rich voids nucleate once vacancies become mobile, and transmutation over five service years irreversibly redirects the alloy chemistry towards Ni-Zr intermetallics. These three independent mechanisms converge to challenge the strategy on which CuCrZr performance depends, suggesting that the long-term performance of age-hardenable Cu-based heat-sink alloys in fusion reactors warrants further assessment. Our findings reveal a new materials challenge for fusion reactor design and commercialisation: the need for new Cu-based heat-sink alloys able to retain engineered strength whilst their chemistry is irreversibly rewritten - thermodynamically and ballistically - by the fusion neutron spectrum.

cond-mat.mtrl-sci

Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental-numerical approach

The hostile condition in a fusion tokomak reactor poses the main challenge in the development and design of in-vessel components such as divertor and breeding blanket due to fusion relevant irradiation conditions (14 MeV) and large thermal loads. The current work describes the employment of an integrated experimental-numerical approach to assess the microstructure evolution of dislocation loops and voids in tungsten proposed for fusion application. Cluster dynamics (CD) model is implemented and simulations are performed on the irradiated tungsten Disk shape Compact Tension (DCT) specimen used in the experimental test. TEM characterisation is performed on the DCT specimen irradiated at 400 °C and 600 °C with around 1 dpa, respectively. The dpa rate and cascade overlap rate from the experiments and SPECTRA-PKA code, respectively, are implemented in the CD model. Based on the comparison between experimental and computational results, the dose and temperature dependence of irradiation-induced defects (dislocation loops, voids, c15 clusters) are clearly observed. Trap mediated diffusion is studied and the impact of cascades with the pre-existing defects is analysed through full cascade overlap mode and the consequent influence on the defect concentration is evaluated. The exchange of self-interstitial atoms (SIAs) and the change in the size of loops through reaction between <111> and <100> loops are studied in detail by means of the transfer rate of the SIAs.

math.NA