Thermal Properties of Irradiated UO2 and MOX

Staicu, D.

doi:10.1016/b978-0-08-056033-5.00038-0

Cited by 11 publications

(5 citation statements)

References 38 publications

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“…Recommended values of A0 and B for pristine samples of UO2, ThO2, and CeO2 are summarized in Table 1 and representative conductivity profiles as a function of temperature are shown in Figure 24. The simplified formulation, and minor variations thereof, has been used to describe the thermal conductivity of fresh and irradiated UO2 fuel [538,539], mixed uranium-plutonium dioxide (MOX) fuel [540,541,542], and rare-earth doped UO2 [543].…”

Section: Fuel Performance Codes and Thermal Conductivitymentioning

confidence: 99%

Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts seek solid fuels that must withstand unprecedented temperature and radiation extremes. In these advanced fuels, thermal energy transport under irradiation is directly related to reactor performance as well as reactor safety. The science of thermal transport in nuclear fuel is a grand challenge due to both computational and experimental complexities. Here, we provide a comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO2), and one advanced fuel candidate material, thorium dioxide (ThO2). In both materials, 5Concluding Remarks .

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Section: Fuel Performance Codes and Thermal Conductivitymentioning

confidence: 99%

Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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“…(2.12) The thermal conductivity increases in the transition region where the HBS commences to form. [13] attributes the increase in the thermal conductivity in the HBS formation to the decrease in the fission gas concentration dissolved in the matrix. The degradation of the thermal conductivity resumes as a result of the accumulation of fission products for further increase of the burnup.…”

Section: Materials/behavioral Modelsmentioning

confidence: 99%

BISON BWR Fuel Modeling Capability: Material Models (FY2020)

Toptan

Gamble

2020

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Until this year, the BISON fuel performance code has been developed primarily for pressurized water reactor (PWR), accident tolerant fuel (ATF), and advanced reactor (e.g., tri-structural isotropic (TRISO), metallic) analyses. The main focus of this work is to develop and document required material models that would aid predicting cladding failure with a specific hydride distribution to be investigated for boiling water reactor (BWR) applications in the next fiscal year. In terms of materials, the primary differences between a BWR and PWR is the use of gadolinia doping of the UO 2 fuel, the use of Zircaloy-2 for the cladding, and the addition of a liner on the inner surface of the cladding for improved pellet-clad mechanical interaction (PCMI) performance. The liner is typically made of pure zirconium or a lower tin content zirconium alloy (e.g. Zr-0.3%Sn). This work details the development and documentation of material and behavioral models for BWR analysis such as the addition of material and behavior models for gadolinia doped UO 2 , pure zirconium, Zr-0.3%Sn, and Zircaloy-2 as well as the ease-of-use additions to allow internal meshing capabilities to include liners. Another important aspect affecting cladding performance is hydrogen diffusion and hydride precipitation in the cladding. A model was added previously for non-lined, homogeneous claddings. In this work, instructions are provided on how to apply the model the BWR liner cladding. Representative experimental values are provided for the hydrogen diffusion parameters and precipitation-dissolution kinetics for typical liner materials of interest.

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“…The chemical state influences physical properties and response of the fuel including thermal conductivity, heat capacity, swelling, creep, fission product volatility, etc. [2]. As LWR UO 2 fuels are burned, they generate up to sixty transuranic and fission product elements resulting in a complex chemical system [3].…”

Section: Introductionmentioning

confidence: 99%