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

Pool Boiling Heat Transfer lab report

A worked pool boiling heat transfer lab report with sample observation tables, regression plots, calculations, and error analysis.

WORKED EXAMPLE · BENCHMARK OBSERVATIONS

A complete example chemical engineering laboratory report.

Simulated demonstration data.

This report illustrates formal chemical and process engineering data reduction, instrument calibration tares, and unit operations parameter estimation. Replace its observations with your own experimental telemetry when preparing a chemical engineering laboratory report submission.

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1. Title and aim

Pool Boiling Heat Transfer & Nukiyama Nucleate Boiling Curve Calibration. Map the pool boiling curve of saturated water over an electrically heated horizontal platinum wire, characterize the nucleate boiling regime, and determine the Rohsenow nucleate boiling parameter S relating heat flux to excess temperature.

2. Abstract

Six controlled chemical process engineering observations were systematically evaluated across operational settings Excess Temp ΔT_e = 5.0 K to Excess Temp ΔT_e = 30.0 K for Pool Boiling Heat Transfer & Nukiyama Nucleate Boiling Curve Calibration. Ordinary least-squares regression yielded an empirical Rohsenow Nucleate Boiling Slope S of 2.4500 (kW/m^2)^1/3/K (difference from theoretical reference = 0.0000%). The empirical telemetry conclusively validates the fundamental chemical engineering transport and equilibrium formulation with R² = 1.000000. The investigation demonstrates stable unit operations behavior, hydrodynamic and thermal reproducibility, and strict adherence to classical chemical engineering principles.

3. Apparatus and fixed settings

4. Theory and graph choice

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

The governing phenomenological transport or equilibrium relationship was linearized into the coordinate form y = mx + b. Here, the independent coordinate x represents Excess temperature ΔT_e = T_w - T_sat (K), and the dependent coordinate y represents Cube root of heat flux (q'')^(1/3) ((kW/m^2)^1/3). The gradient m directly determines Rohsenow Nucleate Boiling Slope S, while the intercept b accounts for baseline tare values or reference potentials. Linear transformation enables robust parameter estimation via ordinary least squares without non-linear numerical divergence. Plotting transformed observation pairs displays process discharge coefficients, heat transfer multipliers, mass transfer rates, or kinetic rate constants directly as linear slopes.

5. Method

  1. Boil the water pool vigorously for 30 minutes with the auxiliary heater to de-aerate dissolved gases; confirm bulk water temperature is stable at 100.0 °C.
  2. Measure cold resistance of the platinum wire at 100.0 °C under negligible current (< 10 mA) to establish the baseline resistance datum R_sat.
  3. Increase DC power supply until wire surface excess temperature reaches ΔT_e = 5.0 K (T_w = 105.0 °C); observe isolated bubble nucleation sites.
  4. Record voltage V and current I across wire voltage taps; calculate wire electrical resistance to find T_w, and compute heat flux q'' = V·I / (π D L).
  5. Increment current to advance excess temperature through 10.0, 15.0, 20.0, 25.0, and 30.0 K, logging steady-state electrical power and bubble dynamics at each plateau.
  6. Calculate (q'')^(1/3) for each run, plot (q'')^(1/3) versus ΔT_e, and extract the slope S to evaluate the Rohsenow nucleate parameter.

6. Observations and calculation table

All chemical process observations use strictly controlled 64-bit IEEE 754 precision buffers. Residuals are computed relative to the ordinary least-squares regression line.

Table 1. Six simulated observations; x and y represent transformed process metrics.
No.Excess Temperature ΔT_e (K)Cube Root Heat Flux (q'')^(1/3) ((kW/m^2)^1/3)Excess temperature ΔT_e = T_w - T_sat (K)Cube root of heat flux (q'')^(1/3) ((kW/m^2)^1/3)Fitted yResidual
15.012.255.000012.250012.25000.0000
210.024.510.000024.500024.50000.0000
315.036.7515.000036.750036.75000.0000
420.049.020.000049.000049.00000.0000
525.061.2525.000061.250061.2500-0.0000
630.073.530.000073.500073.50000.0000

Download the sample observations (CSV) ↓

7. Worked calculation for one observation

For input Excess Temp ΔT_e = 5.0 K: Measured Cube Root Heat Flux (q'')^(1/3) = 12.2500 (kW/m^2)^1/3. Transformed process coordinates: independent x = 5.0000, dependent y = 12.2500.

8. Graph, gradient and final calculation

3.062.0022.979.7542.8817.5062.7825.2582.6933.00Excess temperature ΔT_e = T_w - T_sat (K)Cube root of heat flux (q'')^(1/3) ((kW/m^2)^1/3)

Circular markers represent empirical process observations. The solid line represents the ordinary least-squares linear fit.

x̄ = 17.5000; ȳ = 42.8750
Σ(x − x̄)² = 437.5000
Σ(x − x̄)(y − ȳ) = 1071.8750
m = Σ(x − x̄)(y − ȳ) / Σ(x − x̄)² = 2.45000000
b = ȳ − mx̄ = 0.00000000
y = 2.4500 · x + 0.0000 ⟹ Target Rohsenow Nucleate Boiling Slope S = 2.4500 (kW/m^2)^1/3/K (theoretical = 2.4500)

9. Uncertainty and comparison

Percentage difference = |estimate − theoretical value| / |theoretical value| × 100 = 0.0000%.

For n = 6 observations, Σresidual² = 5.049e-29; s² = Σresidual²/(n − 2). Gradient standard error = √[s²/Σ(x − x̄)²] = 1.699e-16. Intercept standard error = √[s²(1/n + x̄²/Σ(x − x̄)²)] = 3.307e-15.

Propagating the fit parameters yields a fit standard error of 1.699e-16 (kW/m^2)^1/3/K, with an ideal coefficient of determination R² = 1.000000.

In chemical and process engineering experimentation, unit operations verification, and pilot-scale process modeling, empirical uncertainties arise from fluid property variations, slight thermal gradients across heat transfer boundaries, transducer electronic drift (64-bit IEEE 754 precision digital acquisition), and minor flow turbulence eddies. The ordinary least-squares regression across n = 6 standardized test intervals yields unbiased minimum-variance estimators for both slope and intercept. Because the underlying transport phenomena—including Navier-Stokes momentum balances, Fourier conduction, Fickian mass diffusion, and reaction kinetics—adhere strictly to macroscopic conservation laws, residual dispersions remain tightly bounded, yielding an ideal coefficient of determination R² ≥ 0.999999 and confirming the theoretical formulation. Systematic errors (such as sensor zero offsets, thermocouple reference junction drifts, and flowmeter discharge friction) are eliminated using certified calibration standards and differential tare subtraction. Uncertainties in derived transport coefficients, dimensionless numbers, and kinetic constants are evaluated via multivariate error propagation.

10. Result and discussion

Rohsenow Nucleate Boiling Slope S = 2.4500 (kW/m^2)^1/3/K
Theoretical reference value: 2.4500 (kW/m^2)^1/3/K

The empirical laboratory observations provide rigorous quantitative verification of Pool Boiling Heat Transfer & Nukiyama Nucleate Boiling Curve Calibration. In chemical engineering transport phenomena, fluid mechanics, heat transfer, separation processes, and reaction engineering, physical systems are governed by macroscopic mass, momentum, and energy conservation equations. Across all six observation trials, the empirical slope m = 2.4500 confirms the theoretical model with near-zero residual variance. Furthermore, comparison with established chemical engineering literature benchmarks (McCabe, Smith, Harriott; Bird, Stewart, Lightfoot; Fogler; and Levenspiel) underscores vital industrial scale-up principles including continuous steady-state stability, minimal friction losses, optimal reaction conversion, and thermal efficiency. Residual analysis confirms homoscedastic dispersion without systematic non-linear curvature, validating the underlying model assumptions.

11. Precautions and limitations

The transport and thermodynamic models apply within the specified calibrated operating window (5.0 to 30.0 K). 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.

12. Conclusion

This laboratory investigation quantitatively verified the mathematical formulation and physical behavior of Pool Boiling Heat Transfer & Nukiyama Nucleate Boiling Curve Calibration. Through rigorous tracking across six observation points, we confirmed an empirical Rohsenow Nucleate Boiling Slope S of 2.4500 (kW/m^2)^1/3/K matching the theoretical reference 2.4500 (kW/m^2)^1/3/K within 0.0000% error. The investigation demonstrates why this chemical engineering method serves as an indispensable cornerstone in industrial process design, unit operations scaling, and plant optimization.

In-Depth Technical Supplement & Historical Unit Operations Derivation

1. Objective & Practical Significance

This laboratory investigation maps the nucleate pool boiling regime of saturated distilled water ($P = 1.013\text{ bar}$, $T_{sat} = 100.0^\circ\text{C}$) over an electrically heated horizontal platinum wire ($D = 0.25\text{ mm}$, $L = 100\text{ mm}$). Across excess temperatures $\Delta T_e = T_w - T_{sat}$ from $5.0$ to $30.0\text{ K}$, we record heat flux $q''$, verify the Rohsenow cubic relation $(q'')^{1/3} = S \cdot \Delta T_e$, and determine the nucleate boiling slope $S = 2.4500\text{ (kW/m}^2)^{1/3}\text{/K}$.

2. Governing Transport Equations & Phenomenological Relations

Heat flux generated by electrical dissipation is $q'' = \frac{V \cdot I}{\pi D L}$. In the nucleate boiling regime, Rohsenow's correlation models heat flux as a cubic function of excess temperature:

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

where $S = 2.4500\text{ (kW/m}^2)^{1/3}\text{/K}$ represents the experimental nucleate boiling calibration parameter.

3. Experimental Apparatus & Instrumentation Specification

The test cell comprises a Pyrex glass cylinder housing a high-purity ($99.99\%$) platinum wire ($D = 0.250\text{ mm}$, length $L = 100.0\text{ mm}$, surface area $A_s = 7.854 \times 10^{-5}\text{ m}^2$) submerged in saturated water. Wire temperature $T_w$ is determined from electrical resistance using Callendar–Van Dusen coefficients. Voltage and current are monitored via a precision four-wire Kelvin bridge ($0\text{--}30\text{ A}$, accuracy $\pm 0.05\%$). A reflux condenser maintains atmospheric pressure and constant liquid inventory.

4. Standard Operating Procedure & Measurement Protocols

The water pool was pre-boiled for 30 minutes to eliminate dissolved air. Baseline wire resistance was verified at $100.00^\circ\text{C}$. DC current was introduced to set excess temperature to $\Delta T_e = 5.0\text{ K}$ ($T_w = 105.00^\circ\text{C}$). After 60 seconds of stabilization, voltage, current, and bubble detachment were logged. Current was stepped to achieve $\Delta T_e = 10.0, 15.0, 20.0, 25.0,$ and $30.0\text{ K}$, recording steady-state electrical power at each point.

5. Safety Analysis, Hazard Mitigation & Personal Protection

Boiling liquids and high electrical currents present thermal and electrical hazards. Fast electronic over-temperature trip circuits were set to isolate power within $5\text{ ms}$ if wire temperature exceeded $145^\circ\text{C}$ to prevent wire burnout. Protective face shields and thermal gloves were worn.

6. Raw Experimental Observations & Systematic Data Records

Simulated demonstration data. The following measurements were recorded in saturated water at $T_{sat} = 100.0^\circ\text{C}$ ($h_{fg} = 2257\text{ kJ/kg}$, $\rho_l = 958.4\text{ kg/m}^3$, $\rho_v = 0.597\text{ kg/m}^3$):

RunExcess Temp $\Delta T_e$ (K)Wire Temp $T_w$ (°C)Heat Flux $q''$ (kW/m$^2$)$(q'')^{1/3}$ ((kW/m$^2$)$^{1/3}$)Boiling Coeff $h$ (W/(m$^2$·K))
15.0105.01.83812.25367.6
210.0110.014.70624.501,470.6
315.0115.049.63336.753,308.9
420.0120.0117.64949.005,882.5
525.0125.0229.78361.259,191.3
630.0130.0397.06673.5013,235.5

7. Quantitative Mathematical Analysis & Regression Models

Linear regression of cube root heat flux $(q'')^{1/3}$ versus excess temperature $\Delta T_e$ yields:

\[ (q'')^{1/3} = 2.45000 \cdot \Delta T_e + 0.00000 \]

with coefficient of determination $R^2 = 0.999999$. The experimental slope $S = 2.4500\text{ (kW/m}^2)^{1/3}\text{/K}$ matches the target calibration benchmark ($2.4500$) with $0.00\%$ error. The boiling heat transfer coefficient expanded from $367.6\text{ W/(m}^2\cdot\text{K)}$ at $\Delta T_e = 5\text{ K}$ to an immense $13,235.5\text{ W/(m}^2\cdot\text{K)}$ at $\Delta T_e = 30\text{ K}$.

8. Rigorous Error Analysis & Uncertainty Propagation

Uncertainty in electrical power measurement is $\pm 0.1\%$, wire surface area uncertainty is $\pm 0.4\%$, and excess temperature uncertainty is $\pm 0.08\text{ K}$. Propagating into $(q'')^{1/3}$ yields an experimental uncertainty of $\pm 0.85\%$, reporting $S = 2.4500 \pm 0.021\text{ (kW/m}^2)^{1/3}\text{/K}$.

9. Engineering Discussion & Phenomenological Interpretation

The cubic scaling of heat flux with $\Delta T_e$ demonstrates the dramatic non-linear enhancement of nucleate boiling. High-speed video confirmed that as $\Delta T_e$ increased from $5\text{ K}$ to $30\text{ K}$, the active nucleation site density multiplied by over 30 times, transforming isolated bubble columns into continuous vapor jets that aggressively agitated the liquid microlayer.

10. Industrial Scale-Up & Unit Operation Applications

Nucleate boiling is the intended operating regime in petrochemical reboilers, steam generators, and liquid nitrogen vaporizers. Equipment is sized to operate at $60\%$ to $75\%$ of Critical Heat Flux to maximize heat transfer efficiency while maintaining a safe margin against transition boiling burnout.

11. Self-Assessment Conceptual Questions & Model Answers

Q1: Why does dissolved air cause boiling to begin at lower excess temperatures?
A1: Dissolved non-condensable gas comes out of solution inside surface cavities, reducing the partial pressure of water vapor required to achieve equilibrium bubble radius, initiating nucleate boiling at $\Delta T_e < 2\text{ K}$.

Q2: What is the physical mechanism of the Leidenfrost effect?
A2: When liquid droplets contact a surface well above the Leidenfrost temperature ($> 200^\circ\text{C}$ for water), instantaneous vaporization creates an insulating vapor cushion that supports the droplet, drastically lowering heat transfer and allowing the droplet to skitter across the surface.

12. Concluding Summary & Verified Engineering Metric

The experiment mapped the nucleate boiling curve of saturated water on a platinum wire. The verified Rohsenow parameter $S = 2.4500\text{ (kW/m}^2)^{1/3}\text{/K}$ confirmed exact cubic heat flux scaling ($(q'')^{1/3} = 2.4500 \cdot \Delta T_e$) and documented heat transfer coefficients up to $13,235\text{ W/(m}^2\cdot\text{K)}$.