Modeling of the heat transfer performance of plate-type dispersion nuclear fuel elements

Ding, Shurong; Y, Huo; Yan, Xiaojun

doi:10.1016/j.jnucmat.2009.04.015

Cited by 20 publications

(19 citation statements)

References 10 publications

(12 reference statements)

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“…Actually, the in-pile temperature of the typical dispersion fuel element in this study is around 600 K [8][9][10][11][12]. The temperature within the matrix is much lower than 0.5 T m (the melting temperature T m of Zircaloy is about 2123 K [13]).…”

Section: Introductionmentioning

confidence: 79%

“…According to the previous study [9], it can be obtained that the thermal effects at the increasing stage of burnup are relatively weak in normal operation, so in this study the real thermal effects at the increasing stage of burnup are ignored. In the previous studies [10][11][12], in considering the similarity between the irradiation swelling and the thermal expansion, the irradiation swelling of the fuel particles was simulated with the method of virtual temperature increase.…”

Section: The Simulation Methodsmentioning

confidence: 99%

“…According to previous studies [8,9], considering the similarity between the thermal expansion and the irradiation swelling, the method of virtual temperature increase is further developed to simulate the irradiation swelling behaviors.…”

Section: The Simulation Methods Of the Irradiation Swelling Of Fuel Pamentioning

confidence: 99%

“…The thermal expansion coefficient [22] [8][9][10][11][12]. While in this work this expression should be adjusted by a factor to predict the effect of the fast neutron fluence.…”

Section: The Materials Modelsmentioning

confidence: 99%

“…Van Duyn [1] studied the PuO 2 -Zr dispersion rod-like fuel element with FEM, considering the distribution of the fuel particles more actually, while the simulation of the mechanical behaviors was relatively simple. Shurong Ding et al [9,10] studied the thermal and mechanical behaviors in the plate-type dispersion nuclear fuel element, but they did not consider the actual cladding structure. Qiming Wang and Shurong Ding [11,12] further studied the in-pile mechanical performances under different microstructures with allowing for the mechanical interactions between the fuel meat and the cladding; whereas, the synergistic effects of irradiation hardening of the Zircaloy with other irradiation behaviors were not yet considered.…”

Section: Introductionmentioning

confidence: 99%

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Simulation of irradiation hardening of Zircaloy within plate-type dispersion nuclear fuel elements

Jiang

Wang

Cui

et al. 2011

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 79%

Section: The Simulation Methodsmentioning

confidence: 99%

Section: The Simulation Methods Of the Irradiation Swelling Of Fuel Pamentioning

confidence: 99%

“…The thermal expansion coefficient [22] [8][9][10][11][12]. While in this work this expression should be adjusted by a factor to predict the effect of the fast neutron fluence.…”

Section: The Materials Modelsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Simulation of irradiation hardening of Zircaloy within plate-type dispersion nuclear fuel elements

Jiang

Wang

Cui

et al. 2011

Journal of Nuclear Materials

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Rheological behaviors of plasticized polyvinyl chloride thermally conductive composites with oriented flaky fillers: A case study on graphite and mica

Zhang

2022

J of Applied Polymer Sci

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In this study, two oriented flaky fillers in plasticized polyvinyl chloride (P‐PVC) matrix were respectively compared on some rheological behaviors such as dynamic rheological behavior, melt flow rate, and Barus effect. By comparing and analyzing the rheological behaviors and thermal conductivity of P‐PVC/graphite and P‐PVC/mica composites with oriented fillers, it is found that the P‐PVC/graphite composites have obvious percolation thresholds of viscosity, modulus and thermal conductivity at 23.6 vol%. However, P‐PVC/mica composites did not show similar phenomenon. Moreover, the variable parameter K′ in the modified Kerner–Nielson equation was used to relate the rheological behavior, percolation concentration and thermal conductivity of the composites, and the formation of the filler network was analyzed through the rheological behavior to explain the influence of the percolation threshold in the composites caused by the change of internal structure on the thermal conductivity. It has important guiding significance for the mechanism research and comprehensive performance improvement of the filled composites.

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Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel

Kowsar¹,

Zolfaghari²,

Zamzamian³

2023

Annals of Nuclear Energy

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Modeling of the heat transfer performance of plate-type dispersion nuclear fuel elements

Cited by 20 publications

References 10 publications

Simulation of irradiation hardening of Zircaloy within plate-type dispersion nuclear fuel elements

Simulation of irradiation hardening of Zircaloy within plate-type dispersion nuclear fuel elements

Rheological behaviors of plasticized polyvinyl chloride thermally conductive composites with oriented flaky fillers: A case study on graphite and mica

Performance evaluation of thermal conductivity models for fission gases with application to UO2-zirconium dispersion fuel

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