Chemical & Process Engineering / Pool Boiling Heat Transfer
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LABORATORY 15 · CHEMICAL & PROCESS ENGINEERING

Pool Boiling Heat Transfer theory

Understand pool boiling heat transfer: governing transport equations, heat and mass balances, reaction kinetics, and unit operations.

Chemical engineering transport & equilibrium foundations of Pool Boiling Heat Transfer.

Boiling heat transfer constitutes one of the most effective thermal transport mechanisms in chemical process engineering, delivering heat transfer coefficients orders of magnitude higher than single-phase convection. In steam boilers, thermosiphon reboilers, evaporators, and nuclear reactor cooling cores, boiling occurs when a solid heating surface is maintained at a temperature T_w above the liquid saturation temperature T_sat; the temperature difference ΔT_e = T_w - T_sat is termed the excess temperature. In 1934, Shiro Nukiyama experimentally mapped the complete pool boiling curve of water using an electrically heated platinum wire, identifying four distinct regimes: natural convection, nucleate boiling, transition boiling, and film boiling. In the nucleate boiling regime (typically 5 K < ΔT_e < 30 K for water at atmospheric pressure), vapor bubbles nucleate at microscopic surface cavities, grow, and detach into the liquid pool. Bubble departure pumps cold liquid directly to the wall while latent heat absorption drives immense heat flux. Warren M. Rohsenow (1952) established the foundational correlation for nucleate pool boiling: q'' = μ_l · h_fg · [g (ρ_l - ρ_v) / σ]^0.5 · [c_p,l · ΔT_e / (C_sf · h_fg · Pr_l^n)]^3. Crucially, Rohsenow's relation reveals that nucleate boiling heat flux q'' scales with the cube of excess temperature: q'' ∝ (ΔT_e)^3, meaning (q'')^(1/3) scales linearly with ΔT_e. In this laboratory investigation, an instrumented platinum wire boiling cell is operated across excess temperatures from 5.0 to 30.0 K to measure heat flux q'', verify Rohsenow cubic scaling, and determine the nucleate boiling parameter S.

(q'')^(1/3) = S · ΔT_e = 2.4500 · ΔT_e

1. The Classical Nukiyama Boiling Curve

Boiling heat transfer involves liquid-to-vapor phase transformation at a heated solid surface. In 1934, Shiro Nukiyama published his seminal investigation mapping heat flux $q''$ as a function of wall excess temperature $\Delta T_e = T_w - T_{sat}$ for pool boiling of water at atmospheric pressure, identifying four regimes:

  1. Natural Convection Regime ($\Delta T_e < 5\text{ K}$): Liquid adjacent to the wire superheats slightly and circulates by natural buoyancy without bubble formation; heat transfer follows single-phase convection ($q'' \propto \Delta T_e^{1.25}$).
  2. Nucleate Boiling Regime ($5\text{ K} < \Delta T_e < 30\text{ K}$): Vapor bubbles nucleate at microscopic cavities, expand, and detach. Agitation by departing bubbles and evaporation of liquid microlayers yield immense heat transfer coefficients ($q'' \propto \Delta T_e^3$).
  3. Critical Heat Flux (CHF) & Burnout: At the upper limit of nucleate boiling, bubble generation becomes so dense that vapor blankets the wire, causing a catastrophic jump to film boiling.
  4. Film Boiling Regime ($\Delta T_e > 120\text{ K}$): A continuous vapor film insulates the heating surface, and heat transfer occurs via conduction and radiation across the vapor layer.

2. The Rohsenow Nucleate Boiling Correlation

Warren M. Rohsenow (1952) correlated nucleate pool boiling data by modeling bubble pumping as an intensified turbulent convection process:

\[ \frac{c_{p,l} \Delta T_e}{h_{fg}} = C_{sf} \left[ \frac{q''}{\mu_l h_{fg}} \sqrt{\frac{\sigma}{g (\rho_l - \rho_v)}} \right]^{0.33} Pr_l^{1.0} \]

where $C_{sf}$ is an empirical surface-fluid parameter ($C_{sf} \approx 0.013$ for water on platinum). Cubing both sides demonstrates that heat flux scales with excess temperature to the third power:

\[ q'' = \left[ \frac{\mu_l h_{fg}}{\sqrt{\sigma / [g (\rho_l - \rho_v)]}} \left( \frac{c_{p,l}}{C_{sf} h_{fg} Pr_l} \right)^3 \right] (\Delta T_e)^3 \]

Taking the cube root of heat flux yields a strictly linear relationship:

\[ (q'')^{1/3} = S \cdot \Delta T_e \]

where $S$ is the Rohsenow nucleate boiling parameter in $(\text{kW/m}^2)^{1/3}\text{/K}$.

Viva voce questions & analytical theory

What is the Critical Heat Flux (CHF) and why is it known as the burnout point?

CHF is the maximum heat flux achievable in nucleate boiling; beyond CHF, vapor bubbles coalesce into an insulating continuous vapor blanket (film boiling), causing surface temperature to spike catastrophically by hundreds of degrees, which melts or burns out metal elements.

How does surface roughness impact the nucleate boiling heat transfer coefficient?

Rougher surfaces contain a higher density of microscopic re-entrant cavities that trap vapor and serve as active nucleation sites, initiating boiling at lower excess temperatures and yielding higher heat flux for a given ΔT_e.

Why does heat flux scale with the cube of excess temperature (q'' ∝ ΔT_e^3) in nucleate boiling?

Increasing ΔT_e not only increases the thermal driving force across the liquid microlayer, but also activates progressively smaller nucleation cavities, causing active bubble site density to multiply rapidly ($N/A ∝ ΔT_e^2$).

What is the difference between pool boiling and forced convection boiling?

Pool boiling occurs in a stagnant liquid pool driven purely by natural buoyancy of vapor bubbles; forced convection boiling involves fluid pumped through a conduit, combining nucleate boiling with convective shear mechanisms.

What is the role of the surface-fluid parameter C_sf in the Rohsenow correlation?

C_sf is an empirical factor (typically 0.006 to 0.015 for water on clean metals) that accounts for liquid-solid wettability (contact angle) and microscopic cavity geometry of specific fluid-surface pairs.

Why does transition boiling exhibit a negative slope on the Nukiyama boiling curve?

In transition boiling, the surface alternates unstably between wetting (nucleate boiling) and dryout (film boiling); as surface temperature rises, the fraction of dry vapor blanket expands, reducing effective heat transfer.

Experimental precautions and process safety

  • De-aerate the water pool completely prior to testing, as dissolved air forms non-condensable gas bubbles that artificially lower nucleation thresholds.
  • Ensure electronic over-temperature trip limits are active to prevent wire burnout if Critical Heat Flux is inadvertently approached.
  • Maintain pool water level strictly above the wire to prevent exposed dry sections.
  • Verify water purity using deionized distilled water to prevent mineral scale deposition on the platinum wire.

Theoretical assumptions & boundary condition limits

  • The transport and thermodynamic models apply within the specified calibrated operating window (5.0 to 30.0 K).
  • Assumes ideal continuum flow and homogeneous phase mixing without unmodeled parasitic wall losses.
  • Continuous sensor readings reflect ordinary least-squares regression across successive observations.
  • High-temperature or extreme concentration excursions require non-ideal equation-of-state corrections.
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Connect transport theory to empirical process plant data.

Evaluated using a 0.25 mm diameter platinum wire submerged in saturated water at 100.0 °C (P = 1.013 bar). Linear regression models (q'')^(1/3) versus ΔT_e to extract Rohsenow slope S = 2.4500 (kW/m^2)^1/3/K.