The Experts below are selected from a list of 153 Experts worldwide ranked by ideXlab platform
Shurong Ding - One of the best experts on this subject based on the ideXlab platform.
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A new method to simulate the micro-thermo-mechanical behaviors evolution in dispersion Nuclear Fuel Elements
Mechanics of Materials, 2014Co-Authors: Xin Gong, Yunmei Zhao, Shurong DingAbstract:Abstract The large-deformation constitutive relations and stress update algorithms in a co-rotational framework are formulated respectively for the Fuel particles, the matrix and cladding in dispersion Nuclear Fuel Elements undergoing irradiation, with the main irradiation-induced effects within them considered. Their specific consistent tangent stiffness moduli are also developed. Correspondingly, the user subroutines UMAT have been programmed for definition of their mechanical constitutive relations. Besides, the user subroutines UMATHT have been written to define their thermal constitutive relations, in which degradation of the thermal conductivity of Fuel particles are involved. An efficient method is established for modeling the irradiation-induced micro-thermo-mechanical behaviors evolution in dispersion Nuclear Fuel Elements. The developed methodology is validated with the simulation results of the thermo-mechanical behaviors in Fuel Elements under an assumed irradiation condition. This study lays a foundation for optimal design of dispersion Fuel Elements.
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Numerical Simulation Method of radiation damage effects in plate-type dispersion Nuclear Fuel Elements
2013Co-Authors: Yunmei Zhao, Shurong Ding, Xin GongAbstract:A metal-matrix dispersion Nuclear Fuel plate is composed of dispersion Nuclear Fuel meat and metal cladding. The Fuel meat is similar to a kind of particle composite with the Fuel particles embedded in the metal matrix. The extremely harsh irradiation environment results in the complex thermo-mechanical coupling behaviors occurring in the dispersion Fuel plate. Especially, this complexity stems more from the irradiation damage effects, such as irradiation hardening and creep in the metal materials induced by the high-energy fission fragments and neutrons, and the thermal conductivity degradation of Fuel particles as well. In this study, for heterogeneous irradiation conditions, the three-dimensional large deformation constitutive relations and stress update algorithms are built and validated for the homogenized Fuel meat and cladding in the co-rotational coordinate system through forming subroutines in ABAQUS. The obtained results for the whole Fuel plate indicate that when the non-homogeneous irradiation condition introduced: (1) both the mechanical and temperature fields show remarkable non-uniform characters along the length direction; (2) the deformation of the plate surface tends to be an arch, which could affect the normal flow of coolant with increasing burnup. The developed numerical simulation method provides a convenient way to simulate the heterogeneous irradiation damage. This study can lay a basis for establishing failure criteria for metal materials in the irradiation environment.
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Simulation of irradiation hardening of Zircaloy within plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2011Co-Authors: Yijie Jiang, Yongzhong Huo, Qiming Wang, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, the metal matrix and cladding attacked continuously by fast neutrons undergo irradiation hardening, which might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, with the irradiation hardening effect of metal materials mainly considered together with irradiation growth effect of the cladding, the three-dimensional large-deformation constitutive relations for the metal matrix and cladding are developed. The method of virtual temperature increase in the previous studies is further developed to model the irradiation swelling of Fuel particles; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-step-temperature loading is proposed to simulate the coupling features of irradiation-induced swelling of the Fuel particles together with irradiation growth of the cladding. Above all, based on the developed relationship between irradiation growth at certain burnup and the loaded virtual temperatures, with considering that certain burnup corresponds to certain fast neutron fluence, the time-dependent constitutive relation due to irradiation hardening effect is replaced by the virtual-temperature-dependent one which is introduced into the commercial software to simulate the irradiation hardening effects of the matrix and cladding. Numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate that when the irradiation hardening effects are introduced into the constitutive relations of the metal matrix and cladding: (1) higher maximum Mises stresses for certain burnup at the matrix exist with the equivalent plastic strains remaining almost the same at lower burnups; (2) the maximum Mises stresses for certain burnup at the cladding are enhanced while the maximum equivalent plastic strains are reduced; and (3) the maximum first principal stresses for certain burnup at the matrix or the cladding are lower than the ones without the hardening effect, and the differences are found to increase with burnup; and the variation rules of the interfacial stresses are similar.
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Simulation of the coupling behaviors of particle and matrix irradiation swelling and cladding irradiation growth of plate-type dispersion Nuclear Fuel Elements
Mechanics of Materials, 2011Co-Authors: Qiming Wang, Yongzhong Huo, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, besides irradiation swelling of Fuel particles induced by Nuclear fissions, the metal matrix and the cladding are attacked continuously by the fast neutrons released from the Fuel particles. As a consequence, the matrix undergoes a bit irradiation swelling and the cladding takes on irradiation growth, which both might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, the three-dimensional large-strain constitutive relations for the Fuel particles, the metal matrix and cladding are developed; based on them, the method of virtual temperature increase proposed by Ding et al. (2008) is further developed to model the irradiation swelling; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-temperature-loadstep is proposed to simulate the coupling features of the irradiation swellings of both the metal matrix and the Fuel particles together with the irradiation growth of the cladding. In order to clarify the critical factors that affect their mechanical performances and carry out optimal design, with the aid of the research thoughts of particle-reinforced composites, numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate the effects of irradiation swelling of the matrix and irradiation growth of the cladding as that: (1) they might weaken the in-pile mechanical performances at the matrix to some extent; and (2) the former increases interfacial stresses between the Fuel meat and the cladding, while the latter relatively relieve those interfacial stresses; and the interfacial mechanical strength might be improved by getting suitable irradiation growth mode of the cladding.
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Research on the interfacial behaviors of plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2010Co-Authors: Qiming Wang, Shurong Ding, Xiaoqing Yan, Yongzhong HuoAbstract:The three-dimensional constitutive relations are constructed, respectively, for the Fuel particles, the metal matrix and the cladding of dispersion Nuclear Fuel Elements, allowing for the effects of large deformation and thermal-elastoplasticity. According to the constitutive relations, the method of modeling their irradiation behaviors in ABAQUS is developed and validated. Numerical simulations of the interfacial performances between the Fuel meat and the cladding are implemented with the developed finite element models for different micro-structures of the Fuel meat. The research results indicate that: (1) the interfacial tensile stresses and shear stresses for some cases will increase with burnup, but the relative stresses will decrease with burnup for some micro-structures; (2) at the lower burnups, the interfacial stresses increase with the particle sizes and the particle volume fractions; however, it is not the case at the higher burnups; (3) the particle distribution characteristics distinctly affect the interfacial stresses, and the face-centered cubic case has the best interfacial performance of the three considered cases.
Yongzhong Huo - One of the best experts on this subject based on the ideXlab platform.
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Simulation of irradiation hardening of Zircaloy within plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2011Co-Authors: Yijie Jiang, Yongzhong Huo, Qiming Wang, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, the metal matrix and cladding attacked continuously by fast neutrons undergo irradiation hardening, which might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, with the irradiation hardening effect of metal materials mainly considered together with irradiation growth effect of the cladding, the three-dimensional large-deformation constitutive relations for the metal matrix and cladding are developed. The method of virtual temperature increase in the previous studies is further developed to model the irradiation swelling of Fuel particles; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-step-temperature loading is proposed to simulate the coupling features of irradiation-induced swelling of the Fuel particles together with irradiation growth of the cladding. Above all, based on the developed relationship between irradiation growth at certain burnup and the loaded virtual temperatures, with considering that certain burnup corresponds to certain fast neutron fluence, the time-dependent constitutive relation due to irradiation hardening effect is replaced by the virtual-temperature-dependent one which is introduced into the commercial software to simulate the irradiation hardening effects of the matrix and cladding. Numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate that when the irradiation hardening effects are introduced into the constitutive relations of the metal matrix and cladding: (1) higher maximum Mises stresses for certain burnup at the matrix exist with the equivalent plastic strains remaining almost the same at lower burnups; (2) the maximum Mises stresses for certain burnup at the cladding are enhanced while the maximum equivalent plastic strains are reduced; and (3) the maximum first principal stresses for certain burnup at the matrix or the cladding are lower than the ones without the hardening effect, and the differences are found to increase with burnup; and the variation rules of the interfacial stresses are similar.
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Simulation of the coupling behaviors of particle and matrix irradiation swelling and cladding irradiation growth of plate-type dispersion Nuclear Fuel Elements
Mechanics of Materials, 2011Co-Authors: Qiming Wang, Yongzhong Huo, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, besides irradiation swelling of Fuel particles induced by Nuclear fissions, the metal matrix and the cladding are attacked continuously by the fast neutrons released from the Fuel particles. As a consequence, the matrix undergoes a bit irradiation swelling and the cladding takes on irradiation growth, which both might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, the three-dimensional large-strain constitutive relations for the Fuel particles, the metal matrix and cladding are developed; based on them, the method of virtual temperature increase proposed by Ding et al. (2008) is further developed to model the irradiation swelling; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-temperature-loadstep is proposed to simulate the coupling features of the irradiation swellings of both the metal matrix and the Fuel particles together with the irradiation growth of the cladding. In order to clarify the critical factors that affect their mechanical performances and carry out optimal design, with the aid of the research thoughts of particle-reinforced composites, numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate the effects of irradiation swelling of the matrix and irradiation growth of the cladding as that: (1) they might weaken the in-pile mechanical performances at the matrix to some extent; and (2) the former increases interfacial stresses between the Fuel meat and the cladding, while the latter relatively relieve those interfacial stresses; and the interfacial mechanical strength might be improved by getting suitable irradiation growth mode of the cladding.
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Research on the interfacial behaviors of plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2010Co-Authors: Qiming Wang, Shurong Ding, Xiaoqing Yan, Yongzhong HuoAbstract:The three-dimensional constitutive relations are constructed, respectively, for the Fuel particles, the metal matrix and the cladding of dispersion Nuclear Fuel Elements, allowing for the effects of large deformation and thermal-elastoplasticity. According to the constitutive relations, the method of modeling their irradiation behaviors in ABAQUS is developed and validated. Numerical simulations of the interfacial performances between the Fuel meat and the cladding are implemented with the developed finite element models for different micro-structures of the Fuel meat. The research results indicate that: (1) the interfacial tensile stresses and shear stresses for some cases will increase with burnup, but the relative stresses will decrease with burnup for some micro-structures; (2) at the lower burnups, the interfacial stresses increase with the particle sizes and the particle volume fractions; however, it is not the case at the higher burnups; (3) the particle distribution characteristics distinctly affect the interfacial stresses, and the face-centered cubic case has the best interfacial performance of the three considered cases.
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Modeling of the heat transfer performance of plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2009Co-Authors: Shurong Ding, Yongzhong Huo, Xiaoqing YanAbstract:Considering the mutual actions between Fuel particles and the metal matrix, the three-dimensional finite element models are developed to simulate the heat transfer behaviors of dispersion Nuclear Fuel plates. The research results indicate that the temperatures of the Fuel plate might rise more distinctly with considering the particle swelling and the degraded surface heat transfer coefficients with increasing burnup; the local heating phenomenon within the particles appears when their thermal conductivities are too low. With rise of the surface heat transfer coefficients, the temperatures within the Fuel plate decrease; the temperatures of the Fuel plate are sensitive to the variations of the heat transfer coefficients whose values are lower, but their effects are weakened and slight when the heat transfer coefficients increase and reach a certain extent. Increasing the heat generation rate leads to elevating the internal temperatures. The temperatures and the maximum temperature differences within the plate increase along with the particle volume fractions. The surface thermal flux goes up along with particle volume fractions and heat generation rates, but the effects of surface heat transfer coefficients are not evident.
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Reliability analysis of dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2008Co-Authors: Shurong Ding, Xin Jiang, Yongzhong HuoAbstract:Taking a dispersion Fuel element as a special particle composite, the representative volume element is chosen to act as the research object. The Fuel swelling is simulated through temperature increase. The large strain elastoplastic analysis is carried out for the mechanical behaviors using FEM. The results indicate that the fission swelling is simulated successfully; the thickness increments grow linearly with burnup; with increasing of burnup: (1) the first principal stresses at Fuel particles change from tensile ones to compression ones, (2) the maximum Mises stresses at the particles transfer from the centers of Fuel particles to the location close to the interfaces between the matrix and the particles, their values increase with burnup; the maximum Mises stresses at the matrix exist in the middle location between the two particles near the mid-plane along the length (or width) direction, and the maximum plastic strains are also at the above region.
Xin Jiang - One of the best experts on this subject based on the ideXlab platform.
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The Thermal Expansion Coefficient of Dispersion Nuclear Fuel Elements
Advanced Materials Research, 2014Co-Authors: Li Nie, Xin Jiang, Xiaogang Wang, Chang Tao PangAbstract:A representative volume element is chosen to act as the research object to analyze the thermal expansion coefficient of the dispersion Fuel Elements. The thermal analysis is carried out for the thermal behaviors using FEM. The results are compared with several theoretical models.
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The Temperature Field of Dispersion Nuclear Fuel Elements
Advanced Materials Research, 2011Co-Authors: Xin Jiang, Xiao Hang LiuAbstract:A representative volume element is chosen to act as the research object to analyze the temperature field of the dispersion Fuel Elements. The thermal analysis is carried out for the thermal behaviors using FEM. The results indicate that with the volume fraction and the heat generation rate of the Fuel particles increasing, the temperature and the gradient of the temperature in the matrix and the cladding increases markedly.
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Thermal Elastoplastic Behavior of Dispersion Nuclear Fuel Elements
Advanced Materials Research, 2011Co-Authors: Xin Jiang, Xiao Hang LiuAbstract:A representative volume element is chosen to act as the research object to analyze the thermal elastoplastic behavior of the dispersion Fuel Elements. The large strain elastoplastic analysis is carried out for the mechanicalbehaviors using FEM. The results indicate that with the volume fraction of the Fuel particles increasing, the Mises stress and the equivalent plastic strain in the matrix increases, and the first principal stress and the equivalent plastic strain in the cladding increases markedly.
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Reliability analysis of dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2008Co-Authors: Shurong Ding, Xin Jiang, Yongzhong HuoAbstract:Taking a dispersion Fuel element as a special particle composite, the representative volume element is chosen to act as the research object. The Fuel swelling is simulated through temperature increase. The large strain elastoplastic analysis is carried out for the mechanical behaviors using FEM. The results indicate that the fission swelling is simulated successfully; the thickness increments grow linearly with burnup; with increasing of burnup: (1) the first principal stresses at Fuel particles change from tensile ones to compression ones, (2) the maximum Mises stresses at the particles transfer from the centers of Fuel particles to the location close to the interfaces between the matrix and the particles, their values increase with burnup; the maximum Mises stresses at the matrix exist in the middle location between the two particles near the mid-plane along the length (or width) direction, and the maximum plastic strains are also at the above region.
Qiming Wang - One of the best experts on this subject based on the ideXlab platform.
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Simulation of irradiation hardening of Zircaloy within plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2011Co-Authors: Yijie Jiang, Yongzhong Huo, Qiming Wang, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, the metal matrix and cladding attacked continuously by fast neutrons undergo irradiation hardening, which might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, with the irradiation hardening effect of metal materials mainly considered together with irradiation growth effect of the cladding, the three-dimensional large-deformation constitutive relations for the metal matrix and cladding are developed. The method of virtual temperature increase in the previous studies is further developed to model the irradiation swelling of Fuel particles; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-step-temperature loading is proposed to simulate the coupling features of irradiation-induced swelling of the Fuel particles together with irradiation growth of the cladding. Above all, based on the developed relationship between irradiation growth at certain burnup and the loaded virtual temperatures, with considering that certain burnup corresponds to certain fast neutron fluence, the time-dependent constitutive relation due to irradiation hardening effect is replaced by the virtual-temperature-dependent one which is introduced into the commercial software to simulate the irradiation hardening effects of the matrix and cladding. Numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate that when the irradiation hardening effects are introduced into the constitutive relations of the metal matrix and cladding: (1) higher maximum Mises stresses for certain burnup at the matrix exist with the equivalent plastic strains remaining almost the same at lower burnups; (2) the maximum Mises stresses for certain burnup at the cladding are enhanced while the maximum equivalent plastic strains are reduced; and (3) the maximum first principal stresses for certain burnup at the matrix or the cladding are lower than the ones without the hardening effect, and the differences are found to increase with burnup; and the variation rules of the interfacial stresses are similar.
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Simulation of the coupling behaviors of particle and matrix irradiation swelling and cladding irradiation growth of plate-type dispersion Nuclear Fuel Elements
Mechanics of Materials, 2011Co-Authors: Qiming Wang, Yongzhong Huo, Yi Cui, Shurong DingAbstract:Abstract Within plate-type dispersion Nuclear Fuel Elements, besides irradiation swelling of Fuel particles induced by Nuclear fissions, the metal matrix and the cladding are attacked continuously by the fast neutrons released from the Fuel particles. As a consequence, the matrix undergoes a bit irradiation swelling and the cladding takes on irradiation growth, which both might have remarkable effects upon the mechanical behaviors within Fuel Elements. In this paper, the three-dimensional large-strain constitutive relations for the Fuel particles, the metal matrix and cladding are developed; based on them, the method of virtual temperature increase proposed by Ding et al. (2008) is further developed to model the irradiation swelling; the method of anisotropic thermal expansion is introduced to model irradiation growth of the cladding; and a method of multi-temperature-loadstep is proposed to simulate the coupling features of the irradiation swellings of both the metal matrix and the Fuel particles together with the irradiation growth of the cladding. In order to clarify the critical factors that affect their mechanical performances and carry out optimal design, with the aid of the research thoughts of particle-reinforced composites, numerical simulations of the irradiation-induced mechanical behaviors are implemented with the finite element method in consideration of the micro-structure of the Fuel meat. The obtained results indicate the effects of irradiation swelling of the matrix and irradiation growth of the cladding as that: (1) they might weaken the in-pile mechanical performances at the matrix to some extent; and (2) the former increases interfacial stresses between the Fuel meat and the cladding, while the latter relatively relieve those interfacial stresses; and the interfacial mechanical strength might be improved by getting suitable irradiation growth mode of the cladding.
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Research on the interfacial behaviors of plate-type dispersion Nuclear Fuel Elements
Journal of Nuclear Materials, 2010Co-Authors: Qiming Wang, Shurong Ding, Xiaoqing Yan, Yongzhong HuoAbstract:The three-dimensional constitutive relations are constructed, respectively, for the Fuel particles, the metal matrix and the cladding of dispersion Nuclear Fuel Elements, allowing for the effects of large deformation and thermal-elastoplasticity. According to the constitutive relations, the method of modeling their irradiation behaviors in ABAQUS is developed and validated. Numerical simulations of the interfacial performances between the Fuel meat and the cladding are implemented with the developed finite element models for different micro-structures of the Fuel meat. The research results indicate that: (1) the interfacial tensile stresses and shear stresses for some cases will increase with burnup, but the relative stresses will decrease with burnup for some micro-structures; (2) at the lower burnups, the interfacial stresses increase with the particle sizes and the particle volume fractions; however, it is not the case at the higher burnups; (3) the particle distribution characteristics distinctly affect the interfacial stresses, and the face-centered cubic case has the best interfacial performance of the three considered cases.
Xin Gong - One of the best experts on this subject based on the ideXlab platform.
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A new method to simulate the micro-thermo-mechanical behaviors evolution in dispersion Nuclear Fuel Elements
Mechanics of Materials, 2014Co-Authors: Xin Gong, Yunmei Zhao, Shurong DingAbstract:Abstract The large-deformation constitutive relations and stress update algorithms in a co-rotational framework are formulated respectively for the Fuel particles, the matrix and cladding in dispersion Nuclear Fuel Elements undergoing irradiation, with the main irradiation-induced effects within them considered. Their specific consistent tangent stiffness moduli are also developed. Correspondingly, the user subroutines UMAT have been programmed for definition of their mechanical constitutive relations. Besides, the user subroutines UMATHT have been written to define their thermal constitutive relations, in which degradation of the thermal conductivity of Fuel particles are involved. An efficient method is established for modeling the irradiation-induced micro-thermo-mechanical behaviors evolution in dispersion Nuclear Fuel Elements. The developed methodology is validated with the simulation results of the thermo-mechanical behaviors in Fuel Elements under an assumed irradiation condition. This study lays a foundation for optimal design of dispersion Fuel Elements.
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Numerical Simulation Method of radiation damage effects in plate-type dispersion Nuclear Fuel Elements
2013Co-Authors: Yunmei Zhao, Shurong Ding, Xin GongAbstract:A metal-matrix dispersion Nuclear Fuel plate is composed of dispersion Nuclear Fuel meat and metal cladding. The Fuel meat is similar to a kind of particle composite with the Fuel particles embedded in the metal matrix. The extremely harsh irradiation environment results in the complex thermo-mechanical coupling behaviors occurring in the dispersion Fuel plate. Especially, this complexity stems more from the irradiation damage effects, such as irradiation hardening and creep in the metal materials induced by the high-energy fission fragments and neutrons, and the thermal conductivity degradation of Fuel particles as well. In this study, for heterogeneous irradiation conditions, the three-dimensional large deformation constitutive relations and stress update algorithms are built and validated for the homogenized Fuel meat and cladding in the co-rotational coordinate system through forming subroutines in ABAQUS. The obtained results for the whole Fuel plate indicate that when the non-homogeneous irradiation condition introduced: (1) both the mechanical and temperature fields show remarkable non-uniform characters along the length direction; (2) the deformation of the plate surface tends to be an arch, which could affect the normal flow of coolant with increasing burnup. The developed numerical simulation method provides a convenient way to simulate the heterogeneous irradiation damage. This study can lay a basis for establishing failure criteria for metal materials in the irradiation environment.
