Training Nuclear Engineering Reactor Thermal Hydraulics
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Reactor Thermal Hydraulics

25 min Nuclear Engineering

Reactor Thermal Hydraulics

A nuclear reactor is fundamentally a heat source. The fission process converts nuclear binding energy into kinetic energy of fission fragments, which thermalize into heat within the fuel. This heat must be efficiently removed by a coolant and transferred to a power conversion system — typically steam turbines — to generate electricity. The mathematics of this heat removal is called thermal hydraulics, and it is as critical to reactor safety as the nuclear physics itself.

The heat generation in a reactor fuel rod follows the same cosine-shaped flux profile we studied in neutron diffusion. The volumetric heat generation rate q-triple-prime is proportional to the neutron flux, so it peaks at the center of the reactor and falls off toward the edges. For a single fuel rod, the heat must conduct radially outward through the fuel pellet, across the gap between fuel and cladding, through the cladding itself, and finally into the flowing coolant.

Each of these steps involves a temperature drop governed by thermal resistance. The fuel centerline temperature is the highest temperature in the reactor, and ensuring it stays below the fuel melting point (about 2800 degrees Celsius for uranium dioxide) is a primary safety constraint. The total temperature drop from fuel center to coolant is the sum of the drops across each layer — fuel conduction, gap conductance, cladding conduction, and convective heat transfer to the coolant.

The coolant temperature rises as it flows upward through the core, absorbing heat. The enthalpy rise of the coolant equals the thermal power extracted, following the simple energy balance Q equals m-dot times c-p times delta-T. For a pressurized water reactor operating at about 155 bar, the coolant enters at roughly 290 degrees Celsius and exits at about 325 degrees Celsius, a modest 35-degree rise that carries away gigawatts of thermal power.

Coolant Energy Balance

$$Q = \dot{m} \, c_p \, \Delta T$$

where $Q$ = thermal power (W), $\dot{m}$ = coolant mass flow rate (kg/s), $c_p$ = specific heat capacity (J/kg·K), $\Delta T = T_{out} - T_{in}$.

Radial Temperature Distribution in Fuel Rod

$$T_{\text{center}} - T_{\text{coolant}} = \frac{q'}{4\pi k_f} + \frac{q'}{2\pi r_{gap} h_{gap}} + \frac{q' \ln(r_c/r_f)}{2\pi k_c} + \frac{q'}{2\pi r_c h_{\text{conv}}}$$

where $q'$ = linear heat rate (W/m), $k_f$ = fuel thermal conductivity, $h_{gap}$ = gap conductance, $k_c$ = cladding conductivity, $h_{\text{conv}}$ = convective heat transfer coefficient.

Example 1

A PWR core produces 3000 MW of thermal power. Coolant enters at 290°C and exits at 325°C. Find the required mass flow rate. ($c_p = 5500$ J/kg·K for water at 155 bar)

Step 1: Apply the energy balance.

$$\dot{m} = \frac{Q}{c_p \Delta T} = \frac{3 \times 10^9}{5500 \times 35}$$

Step 2: Calculate.

$$\dot{m} = \frac{3 \times 10^9}{192{,}500} = 15{,}584 \text{ kg/s} \approx 15{,}600 \text{ kg/s}$$

That's about 15,600 liters per second of high-pressure water circulating through the core.

Example 2

A fuel rod has a linear heat rate of $q' = 40$ kW/m, fuel conductivity $k_f = 3$ W/m·K, and the coolant temperature is 310°C. If only fuel conduction is considered, what is the fuel centerline temperature?

Step 1: The temperature drop across the fuel pellet:

$$\Delta T_{\text{fuel}} = \frac{q'}{4\pi k_f} = \frac{40{,}000}{4\pi(3)} = \frac{40{,}000}{37.70} \approx 1061°\text{C}$$

Step 2: Fuel center temperature:

$$T_{\text{center}} \approx 310 + 1061 = 1371°\text{C}$$

This is well below UO₂ melting point (~2800°C), providing a comfortable safety margin.

Example 3

If the reactor thermal efficiency is 33%, what is the electrical output from a 3000 MWth core?

Step 1: $$P_{\text{elec}} = \eta \times Q = 0.33 \times 3000 = 990 \text{ MWe}$$

A 3 GW thermal reactor produces about 1 GW of electricity — enough for roughly 1 million homes.

Interactive Explorer: Reactor Coolant Energy Balance
Mass flow rate = 15584 kg/s
Electrical output = 990 MWe
Waste heat = 2010 MW
0Efficiency100%

Practice Problems

1. A small modular reactor produces 250 MWth. Coolant $\Delta T = 30°$C, $c_p = 5400$ J/kg·K. Find $\dot{m}$.
2. If the thermal efficiency is 31%, what is the electrical output of the 250 MWth reactor?
3. A fuel rod has $q' = 45$ kW/m and $k_f = 2.5$ W/m·K. What is $\Delta T$ across the fuel pellet?
4. UO₂ melts at 2800°C. If coolant is 300°C and total $\Delta T$ from coolant to centerline is 2200°C, does the fuel melt?
5. A CANDU reactor uses heavy water ($c_p = 4200$ J/kg·K), $\dot{m} = 7700$ kg/s, $\Delta T = 33°$C. Find $Q$.
6. What happens to required $\dot{m}$ if $c_p$ doubles (at same $Q$ and $\Delta T$)?
7. A boiling water reactor has $\eta = 34\%$ and produces 1400 MWe. What is the thermal power?
8. If $q'$ is doubled, by what factor does $\Delta T_{\text{fuel}}$ increase?
9. Explain why the temperature distribution in a cylindrical fuel rod has a parabolic profile.
10. A reactor rejects 2000 MW of waste heat to a river. If the river flow is $50{,}000$ kg/s ($c_p = 4186$), what is the river temperature rise?
Show Answer Key

1. $\dot{m} = 250 \times 10^6 / (5400 \times 30) = 1543$ kg/s.

2. $P_e = 0.31 \times 250 = 77.5$ MWe.

3. $\Delta T = 45000/(4\pi \times 2.5) = 45000/31.42 \approx 1432°$C.

4. $T_{\text{center}} = 300 + 2200 = 2500°$C $ < 2800°$C. No, the fuel does not melt, but the margin is only 300°C.

5. $Q = 7700 \times 4200 \times 33 = 1.067 \times 10^9$ W $= 1067$ MW.

6. $\dot{m} = Q/(c_p \Delta T)$. If $c_p$ doubles, $\dot{m}$ is halved.

7. $Q = P_e/\eta = 1400/0.34 = 4118$ MWth.

8. $\Delta T \propto q'$, so it doubles.

9. For uniform volumetric heat generation in a cylinder with constant conductivity, the heat equation gives $T(r) = T_{\text{center}} - \frac{q'''}{4k}r^2$, which is a parabola in $r^2$.

10. $\Delta T = Q/(\dot{m} c_p) = 2 \times 10^9/(50000 \times 4186) = 9.56°$C.