Thermal‐hydraulic analysis of UO<sub>2</sub> and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor

Farha, Farhana Islam; Sahadath, Md. Hossain; Nishat, Sadek Hossain

doi:10.1002/htj.22225

Cited by 2 publications

(2 citation statements)

References 17 publications

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“…3. This can be explained by the lower burnupdependent thermal conductivity of MOX fuel than UO 2 fuel [11]. Rests of the observations are similar to previous cases.…”

Section: Temperature Profilesupporting

confidence: 85%

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Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Farha

Sahadath

2022

Dhaka Uni. J. of Applied Sci. and Eng.

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The perturbation in temperature profile and fissile content due to variation in the central gap of an isolated annular cylindrical fuel rod of a pressurized water reactor was studied by analytical calculation. Four different models namely UO2+Zircaloy-4+He, UO2+ Zr-1%Nb +He, MOX+Zircaloy-4+He, and MOX+ Zr-1%Nb +He were considered. The radial temperature profile was generated for different ratios (α) of outer to inner fuel radius. Lower fuel temperature was observed for small values of α and vice versa. The peak fuel temperature and temperature drop across the fuel pellets were calculated. Models of MOX fuel showed higher peak fuel temperature and large temperature drop than the models of UO2 for the same fuel cladding. Zr-1%Nb cladding results in a slightly higher fuel temperature than Zircaloy-4 for the same fuel composition. The faster changes of these parameters with α were found for UO2 than MOX fuel. The change in fissile loading with α was also studied and a sharp increase is observed if exceeds α=2.50. DUJASE Vol. 6 (2) 72-76, 2021 (July)

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“…3. This can be explained by the lower burnupdependent thermal conductivity of MOX fuel than UO 2 fuel [11]. Rests of the observations are similar to previous cases.…”

Section: Temperature Profilesupporting

confidence: 85%

“…2. This is due to the lower thermal conductivity of Zr-1%Nb at the higher temperature [11]. Rests of the observations are similar in both cases.…”

Section: Temperature Profilementioning

confidence: 52%

Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Farha

Sahadath

2022

Dhaka Uni. J. of Applied Sci. and Eng.

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Phase evolution in the UO2–CeO2 system under oxidizing and reducing conditions: X-ray diffraction and spectroscopic studies

Nandi

Grover

Kesari

et al. 2023

Journal of Physics and Chemistry of Solids

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Thermal‐hydraulic analysis of UO₂ and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor

Cited by 2 publications

References 17 publications

Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Phase evolution in the UO2–CeO2 system under oxidizing and reducing conditions: X-ray diffraction and spectroscopic studies

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Thermal‐hydraulic analysis of UO2 and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor

Cited by 2 publications

References 17 publications

Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Analysis of the Effect of Central Gap Size on the Temperature Profile and Fissile Content in the Annular Nuclear Fuel Rod

Phase evolution in the UO2–CeO2 system under oxidizing and reducing conditions: X-ray diffraction and spectroscopic studies

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Thermal‐hydraulic analysis of UO₂ and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor