Assessment of effective thermal conductivity in U–Mo metallic fuels with distributed gas bubbles

Hu, Sanmei; Casella, Andrew M.; Lavender, Curt A.; Senor, David J.; Burkes, Douglas E.

doi:10.1016/j.jnucmat.2015.03.039

Cited by 44 publications

(21 citation statements)

References 32 publications

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“…Hu et al has determined the effective thermal conductivity of U-Mo metallic fuels with distributed gas bubbles. [10] In this work, the relative impact of irradiation on various microstructural features was assessed. Staicu and Barker have explained the thermal conductivity difference between LWR UO 2 and MOX fuels and have confirmed their conclusions by comparison with in-pile and out-of-pile measurements.…”

Section: Introductionmentioning

confidence: 99%

Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material

Guillen¹,

Harris²

2016

Metallurgical and Materials Transactions E

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A metal matrix composite (MMC) material composed of hafnium aluminide (Al 3 Hf) intermetallic particles in an aluminum matrix has been identified as a promising material for fast flux irradiation testing applications. This material can filter thermal neutrons while simultaneously providing high rates of conductive cooling for experiment capsules. The purpose of this work is to investigate effects of Hf-Al material composition and neutron irradiation on thermophysical properties, which were measured before and after irradiation. When performing differential scanning calorimetry (DSC) on the irradiated specimens, a large exotherm corresponding to material annealment was observed. Therefore, a test procedure was developed to perform DSC and laser flash analysis (LFA) to obtain the specific heat and thermal diffusivity of pre-and post-annealment specimens. This paper presents the thermal properties for three states of the MMC material: (1) unirradiated, (2) as-irradiated, and (3) irradiated and annealed. Microstructure-property relationships were obtained for the thermal conductivity. These relationships are useful for designing components from this material to operate in irradiation environments. The ability of this material to effectively conduct heat as a function of temperature, volume fraction Al 3 Hf, radiation damage, and annealing is assessed using the MOOSE suite of computational tools.

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Section: Introductionmentioning

confidence: 99%

Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material

Guillen¹,

Harris²

2016

Metallurgical and Materials Transactions E

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“…As a consequence, Fig. 9 Calculated effective thermal conductivity of U-10wt%Mo polycrystalline as a function of interface coverage of intergranular gas bubbles and effective thermal conductivity of grains with nano-scale intragranular gas bubbles 106 A review: applications of the phase Y Li et al…”

Section: Discussionmentioning

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%

“…55,91,[102][103][104][105][106] The PF models were used to generate the polycrystalline structure with inter-and intra-granular pores/gas bubbles. The GBs, pores, and gas bubbles results in inhomogeneous thermal conductivity so affect the overall material thermal conductivity.…”

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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Modeling of Microstructure Evolution: Mesoscale Challenges

Stan¹,

Sarrao²

2018

Handbook of Materials Modeling

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Assessment of effective thermal conductivity in U–Mo metallic fuels with distributed gas bubbles

Cited by 44 publications

References 32 publications

Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material

Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material

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

Modeling of Microstructure Evolution: Mesoscale Challenges

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