Nuclear Fuel Pin Radial Temperature Calculator

Fuel Rod Performance: Compute radial temperature gradients across $\text{UO}_2$ ceramic pellets, helium gas gap, and Zircaloy cladding to determine centerline melting margins.

Fuel Rod Geometry & Operating Power

Linear Power $q^{\prime}$ (kW/m):

Cladding Outer Temp $T_{co}$ (°C):

Pellet Radius $r_p$ (mm):

Clad Inner Radius $r_{ci}$ (mm):

Clad Outer Radius $r_{co}$ (mm):

Clad Cond. $k_{\text{clad}}$ (W/m·K):

Gap Conductance $h_{\text{gap}}$ (W/m²·K):

Average UO₂ $k_f$ (W/m·K):

Radial Temperatures & Margins

Fuel Centerline Temp ($T_{\text{center}}$)

-- °C

-- °F

Melting Safety Margin

-- °C

UO₂ Melting Point: 2,805 °C

Pellet Surface Temp ($T_{\text{ps}}$)

-- °C

Gap Drop: -- °C

Clad Inner Temp ($T_{\text{ci}}$)

-- °C

Clad Gradient: -- °C

Thermal Density Breakdown:

• Volumetric heat generation $q^{\prime\prime\prime}$: -- MW/m³

• Heat flux at clad outer surface $q^{\prime\prime}_{co}$: -- kW/m²

• Cladding thickness: -- mm

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Nuclear Fuel Pin Radial Temperature Calculator

Fuel Rod Geometry & Operating Power

Radial Temperatures & Margins

Frequently Asked Questions