Effect of grain morphology on gas bubble swelling in UMo fuels – A 3D microstructure dependent Booth model

“…97 The model integrated rate theory (Booth model) 139 and PF approach. The rate theory was used to describe the intra-and inter-granular gas bubble evolution while the FP model described the effect of heterogeneous microstructures and inhomogeneous thermodynamic and kinetic properties on generation and diffusion of fission products.…”

Section: Irradiation Effects On Mechanical Thermal and Magnetic Promentioning

confidence: 99%

“…The rate theory was used to describe the intra-and inter-granular gas bubble evolution while the FP model described the effect of heterogeneous microstructures and inhomogeneous thermodynamic and kinetic properties on generation and diffusion of fission products. Figure 8 showed the effect of grain morphology on swelling kinetics obtained from this Mechanical properties-void and gas bubble swelling 65,97,98 Thermal properties-thermal transport and melting 55,91,[102][103][104][105][106] Magnetic hardening 107,108 A review: applications of the phase Y Li et al…”

Section: Irradiation Effects On Mechanical Thermal and Magnetic Promentioning

confidence: 99%

“…96 The PF method also has been used to study the effect of microstructures on material property degradation including radiation-induced void and gas bubble swelling. 55,65,91,[97][98][99][100][101][102][103][104][105][106][107][108] Although the PF method has been used to simulate a large number of radiation-induced microstructure evolution phenomena, direct validation of PF models published in the literatures is difficult because most current PF models only addressed one or a couple of multiple microstructures in irradiated materials. Furthermore, there was very limited experimental data for the validation of specific microstructures and processes.…”

Section: Introductionmentioning

confidence: 99%

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A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials

Sun

et al. 2017

npj Comput Mater

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127

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Complex microstructure changes occur in nuclear fuel and structural materials due to the extreme environments of intense irradiation and high temperature. This paper evaluates the role of the phase field method in predicting the microstructure evolution of irradiated nuclear materials and the impact on their mechanical, thermal, and magnetic properties. The paper starts with an overview of the important physical mechanisms of defect evolution and the significant gaps in simulating microstructure evolution in irradiated nuclear materials. Then, the phase field method is introduced as a powerful and predictive tool and its applications to microstructure and property evolution in irradiated nuclear materials are reviewed. The review shows that (1) Phase field models can correctly describe important phenomena such as spatial-dependent generation, migration, and recombination of defects, radiation-induced dissolution, the Soret effect, strong interfacial energy anisotropy, and elastic interaction; (2) The phase field method can qualitatively and quantitatively simulate two-dimensional and three-dimensional microstructure evolution, including radiation-induced segregation, second phase nucleation, void migration, void and gas bubble superlattice formation, interstitial loop evolution, hydrate formation, and grain growth, and (3) The Phase field method correctly predicts the relationships between microstructures and properties. The final section is dedicated to a discussion of the strengths and limitations of the phase field method, as applied to irradiation effects in nuclear materials. npj Computational Materials (2017) 3:16 ; doi:10.1038/s41524-017-0018-y INTRODUCTIONHigh energy particle (such as neutron, ion, and electron) radiation can create major changes in the shape and thermo-mechanical properties of nuclear fuels and structural components of nuclear reactors. These changes are caused by radiation-induced evolution of compositions and microstructures. The main effects of radiation on reactor materials are: (1) dimensional change associated with gas bubble swelling, void swelling, grain growth, and creep; 1-5 (2) loss of ductility and increase in ductile-brittle transition temperature (DBTT) due to the formation of secondphase precipitates, self-interstitial atomic (SIA) loops, and dislocation networks; 6, 7 (3) oxidation and corrosion accelerated by high temperature, fission products, and radiation damage; 8-10 and (4) local and bulk changes in chemical composition, including irradiation-enhanced segregation of alloy components and phase separation.11-17 Figure 1 shows typical microstructures observed in irradiated materials.9, 18-21 The radiation-induced heterogeneity of the microstructures depends on the initial phase and defect structure of the fresh (non-irradiated) materials and on the type and severity of the radiation environment. Fundamental understanding of heterogeneous three-dimensional microstructure evolution is crucial to the development of advanced radiation tolerant materials that can significa...

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“…As ligas de UMo se encontram em estágio mais avançado de desenvolvimento, com testes de irradiação realizados em laboratórios de diversos países 43,44 , e na fase inicial de construção de um reator que utilizará esse tipo de combustível 45 , possuem boa condutividade térmica e excelente desempenho sob irradiação. Porém, dada a baixíssima solubilidade dos gases de fissão como Xe e Kr nessa liga, esse combustível tende a apresentar significativo inchamento, o que pode comprometer a estrutura do combustível 46 . Além disso, testes de irradiação sugerem que o crescimento da camada de interação com a matriz de alumínio é considerável, podendo provocar não só a redução da espessura do revestimento, mas também descolamento e consequente inchamento, comprometendo a condutividade térmica do EC 47 .…”

Section: Objetivounclassified

Caracterização e quantificação de fases em ligas de urânio-silício para aplicação como combustível nuclear

García¹

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RESUMO GARCIA, Rafael H. L. Caracterização e quantificação de fases em ligas de urânio-silício para aplicação como combustível nuclear. 2019. 200 p. Tese (Doutorado em Tecnologia Nuclear)-Instituto de Pesquisas Energéticas e Nucleares-IPEN-CNEN/SP. São Paulo. A segurança da operação de reatores nucleares depende dos materiais envolvidos em sua construção, pois são submetidos a variações de temperaturas em ambiente corrosivo e avarias causadas por partículas de alta energia. O combustível, que proporciona energia para o reator, possui vida útil muito menor, mas é submetido às mesmas condições. Dentre as ligas de urânio, o U 3 Si 2 é bastante utilizado em reatores de pesquisa, dada a elevada densidade de urânio, boa condutividade térmica e resistência à amorfização induzida por radiação, ao inchamento e à propagação de trincas. Porém, no processo de fabricação da liga U-Si geralmente são formadas duas ou mais fases cristalinas, com comportamentos distintos sob irradiação. Por esse motivo, a especificação do pó de siliceto de urânio utilizado no reator IEA-R1 do IPEN, e do RMB (Reator Multipropósito Brasileiro) é de, pelo menos, 80% em massa de U 3 Si 2. No entanto, as técnicas de caracterização atualmente utilizadas no controle de qualidade não permitem quantificar as fases cristalinas diretamente. Assim, esse trabalho propõe a utilização da difração de raios X (DRX), alinhada a refinamento pelo método de Rietveld para caracterização do pó de siliceto. Para tal, foram produzidas ligas de urânio contendo 33 a 67 mol% de silício, e técnicas de moagem e ajustes de refinamento foram testados. O método desenvolvido inclui cominuição em moinho vibratório e DRX com refinamento automatizado dos dados, permitindo a quantificação das fases cristalinas de maneira confiável, rápida e com mínima interferência do operador. Os resultados obtidos foram corroborados com os de técnicas como análise de imagem obtida por microscópio eletrônica de varredura (MEV), densidade e análises elementares de U e Si.

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Effect of grain morphology on gas bubble swelling in UMo fuels – A 3D microstructure dependent Booth model

Cited by 34 publications

References 34 publications

Effects of porous fuel structure on the irradiation-induced thermo-mechanical coupling behavior in monolithic fuel plates

Effects of porous fuel structure on the irradiation-induced thermo-mechanical coupling behavior in monolithic fuel plates

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials

Caracterização e quantificação de fases em ligas de urânio-silício para aplicação como combustível nuclear

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