A numerical method for simulating the non-homogeneous irradiation effects in full-sized dispersion nuclear fuel plates

Zhao, Yunmei; Gong, Xuejun; Ding, Shurong; Y, Huo

doi:10.1016/j.ijmecsci.2014.02.012

Cited by 23 publications

(9 citation statements)

References 19 publications

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“…For the numerical implementation of the thermal-mechanical theoretical models on the commercial software ABAQUS, it is necessary to define the location-irradiation time-temperature dependent thermal-mechanical constitutive relations. The solution techniques in this study are similar to those in our previous works Gong et al, 2013;Gong et al, 2014;Zhao et al, 2014;Cui et al, 2015;Kong et al, 2018). Here, the threedimensional mechanical constitutive relation in an incremental form is briefly introduced as follows.…”

Section: Solution Techniques For the Irradiation-induced Thermal-mechanical Fieldsmentioning

confidence: 98%

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

et al. 2021

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To obtain the optimized fuel performance, the effects of U-Mo irradiation creep rate coefficient on the thermo-mechanical behavior of a fuel assembly are investigated. In this study, three cases of creep rate coefficient are considered. The distribution and evolution results of temperature, displacement, stress/strain and fuel foil micro-structure are analyzed. The simulation results indicate that with the increase of creep rate coefficient 1) the temperature field in the fuel assembly changes slightly; 2) the maximum out-of-plane displacements in the side plates decrease slightly; the maximum out-of-plane displacements in the fuel plates adjacent to the outside Al plates rise distinctly, induced by the enhanced bending deformation contributions; 3) the peak values of the first principal stresses and skeleton normal stresses in the fuel foils are reduced, while the through-thickness creep strains are enlarged; 4) with an increase of fuel creep rate coefficient from 500 × 10−22 mm3/(fission MPa) to 2,000 × 10−22 mm3/(fission·MPa), the maximum Von Mises stress in the fuel cladding decreases by ∼24% on the 308th day. This work is helpful for advanced fabrication and optimization design of U-Mo/Al fuel assemblies.

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Section: Solution Techniques For the Irradiation-induced Thermal-mechanical Fieldsmentioning

confidence: 98%

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

et al. 2021

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“…The stress update algorithm is similar as that without considering irradiation growth in our previous work (Zhao et al, 2014).…”

Section: The Three-dimensional Stress Update Algorithms For U-momentioning

confidence: 99%

“…In our previous studies Jiang et al, 2011;Gong et al, 2013;Wang et al, 2011), the microscopic thermal and mechanical behaviors in plate-type dispersion nuclear fuel elements were examined, and the simulation methods were gradually improved to involve effectively the irradiation effects in the nuclear fuels and cladding. Recently, modeling of the macroscopic thermomechanical coupling behaviors in a dispersion nuclear fuel plate were employed allowing for the un-uniform irradiation condition, and the thermal and mechanical constitutive relations were defined conveniently with the user material subroutines UMATHT and UMAT (Zhao et al, 2014). Our previous researches focused on oxide fuels.…”

Section: Introductionmentioning

confidence: 99%

Simulation of the irradiation-induced thermo-mechanical behaviors evolution in monolithic U–Mo/Zr fuel plates under a heterogeneous irradiation condition

Zhao

Gong

Ding

2015

Nuclear Engineering and Design

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“…Recently, several studies have been reported that examined the mechanical behavior of monolithic U-Mo fuel plates [16]- [18], and dispersion fuel plates [19]- [21]. Some modeling tools such as PLATE [22] [23], DART-TM [24] [25], and MAIA [26] predict fuel performance and evaluate fuel integrity during irradiation by adopting a concept of 'homogeneous fuel meat', in which the fuel meat composed of fuel particles, Al matrix, and IL is treated as a homogeneous medium.…”

Section: Introductionmentioning

confidence: 99%

“…Homogeneous fuel meat modeling is advantageous in predicting overall thermo-mechanical behaviors because of its relative simplicity, but it has limitations in simulating the aforementioned irradiation-induced phenomena. Studies of the threedimensional thermo-mechanical behavior of a dispersion fuel plate containing oxide fuel dispersion in a Zircaloy (Zry) matrix clad with Zry are also available [19]- [21]. In these studies, the fuel and matrix were heterogeneously treated by employing FEA (finite element analysis) software to solve the constitutive relations using the representative volume element (RVE) method.…”

Section: Introductionmentioning

confidence: 99%

Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel

Jeong

Kim

Jamison

et al. 2017

Journal of Nuclear Materials

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U-Mo/Al dispersion fuel irradiated to high burnup at high power (high fission rate) exhibited microstructural changes including deformation of the fuel particles, pore growth, and rupture of the Al matrix. The driving force for these microstructural changes was meat swelling resulting from a combination of fuel particle swelling and interaction layer (IL) growth. In some cases, pore growth in the interaction layers also contributed to meat swelling. The main objective of this work was to determine the stress distribution within the fuel meat that caused these phenomena. A mechanical equilibrium between the stress generated by fuel meat swelling and the stress relieved by fission-induced creep in the meat constituents (U-Mo particles, Al matrix and IL) was considered. Test plates with well-recorded fabrication data and irradiation conditions were used, and their post-irradiation examination (PIE) data was obtained. ABAQUS finite element analysis (FEA) was utilized to simulate the microstructural evolution of the plates. The simulation results allowed for the determination of the shear stress, effective stress, and hydrostatic stress exerted on the meat constituents. The effects of fabrication and irradiation variables on the stress distribution that drives microstructural evolutions, such as pore growth in the IL and Al matrix rupture, were investigated.

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A numerical method for simulating the non-homogeneous irradiation effects in full-sized dispersion nuclear fuel plates

Cited by 23 publications

References 19 publications

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

Simulation of the irradiation-induced thermo-mechanical behaviors evolution in monolithic U–Mo/Zr fuel plates under a heterogeneous irradiation condition

Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel

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