3.2 Cryogenic Convection Heat Transfer
Involves process of heat transfer between q solid material and adjacent cryogenic fluid f = TT mean Classic heat transfer problem (Newton’s law) 2 m& f q(kW/m ) = h (Ts –Tf) Configurations of interest
= TT Internal forced flow (single phase, f mean ) q Free convection (single phase, f = TT ∞ ) Internal two phase flow Pool boiling (two phase) Understanding is primarily empirical leading to correlations based on dimensionless numbers
Issue is relevant to the design of: Liquid T Heat exchangers f Ts Cryogenic fluid storage Superconducting magnets Low temperature instrumentation
USPAS Short Course Boston, MA 6/14 to 6/18/2010 1 Single phase internal flow heat transfer
Forced T D ,Tm f Convection s & Q Classical fluid correlations
The heat transfer coefficient in a classical fluid system is generally correlated in the form where the Nusselt number, hD where, NuD ≡ and D is the characteristic length k f For laminar flow, NuD = constant ~ 4 (depending on b.c.) For turbulent flow (Re > 2000) D μ C mn Pr ≡ pf D = fNu D = C D PrRePr),(Re and (Prandtl number) k f Dittus-Boelter Correlation for classical fluids (+/- 15%) 4 2 5 5 NuD = PrRe023.0 Note that fluid properties should be +TT fs computed at T (the “film temperature”): T ≡ f f 2 USPAS Short Course Boston, MA 6/14 to 6/18/2010 2
Johannes Correlation (1972)
Improved correlation specifically for helium (+/- 8.3%) − 716.0 4 2 ⎛ T ⎞ Nu = 5 PrRe0259.0 5 ⎜ s ⎟ D D ⎜ ⎟ ⎝ Tf ⎠
Last factor takes care of temperature dependent properties Note that one often does not know Tf, so iteration may be necessary.
Example
USPAS Short Course Boston, MA 6/14 to 6/18/2010 3 Application: Cryogenic heat exchangers
Common types of heat exchangers used
in cryogenic systems P1 , T1
P , T Forced flow single phase fluid-fluid 2 2
E.g. counterflow heat exchanger in refrigerator/liquefier
Forced single phase flow - boiling liquid (Tube in shell HX)
E.g. LN precooler in a cooling circuit 2 m
Static boiling liquid-liquid
E.g. Liquid subcooler in a magnet system
USPAS Short Course Boston, MA 6/14 to 6/18/2010 4 Simple 1-D heat exchanger
Ts D & ,Tm f
Differential equation describing the temperature of the fluid in the tube:
dTf & Cm ()TThP Sf =−+ 0 dx
For constant Ts, the solution of this equation is an exponential
Ts -Tf . ⎛ hP ⎞ Increasing m −=− TTTT fsfs 0 exp)( ⎜− x⎟ ⎝ & Cm ⎠
x
USPAS Short Course Boston, MA 6/14 to 6/18/2010 5 He (Ti = 300 K) He (Tf = 80 K) Liquid nitrogen precooler
Ts D & ,Tm f
Assumptions & givens
Ts is a constant @ 77 K (NBP of LN2) LN2 (Ts = 77 K) -6 3 Helium gas (Cp = 5.2 kJ/kg K; μ = 15 x 10 Pa s; ρ = 0.3 kg/m , k = 0.1 W/m K) Allowed pressure drop, Δp= 10 kPa Properties are average values Helium mass flow rate = 1 g/s between 300 K and 80 K Find the length and diameter of the HX (copper tubing) Total heat transfer: = 1 g/s x 5.2 J/g K x 220 K Q = m& C p (Tin −Tout ) = 1144 W Δ Log mean T: ΔT (x = 0)− ΔT (x = L) f f (300-77) –(80-77) K ΔTlm = = ⎛ΔTf ()x = 0 ⎞ ln⎜ ⎟ ln [(300-77)/(80-77)] ⎝ ΔTf ()x = L ⎠ = 51 K USPAS Short Course Boston, MA 6/14 to 6/18/2010 6 Liquid nitrogen precooler (continued)
Q πDLhUA == = 1144 W/51 K = 22.4 W/K ΔTlm
The heat transfer coefficient is a function of ReD and Pr = 0.67 Assuming the flow is turbulent and fully developed, use the Dittus Boelter correlation
hD 3.08.0 4m& NuD == D PrRe023.0 and ReD = k f Dμπ
Substituting the ReD and solving for h 8.0 0.0247 x 0.1 W/m K x (10-3 kg/s)0.8 k f ⎛ 4m& ⎞ 3.0 h = 023.0 ⎜ ⎟ Pr = D ⎝ Dμπ⎠ (15 x 10-6 Pa s)0.8 x D1.8 = 0.07/D(m)1.8
hπDL = 0.224 x (L/D0.8) = 22.4 W/K 0.8 0.2 or L/D = 100 m 1 equation for two unknowns
USPAS Short Course Boston, MA 6/14 to 6/18/2010 7 Liquid nitrogen precooler (continued)
Pressure drop equation provides the other equation for L & D 2 L ⎛ m& ⎞ =Δ fp ⎜ ⎟ ; A = πD2/4 and f ~ 0.02 (guess) 2ρD ⎜ A ⎟ flow ⎝ flow ⎠ 4m Re = & D Dμπ 4 x 0.001 kg/s -6 Substituting for ReD and f π x 0.0062 m x 15 x 10 Pa s 2 ~ 13,700 Lm -3 2 L p ≈Δ 016.0 & 0.016 x (10 kg/s) ⎛ ⎞ 5 = ⎜ 5 ⎟ ρ D 0.3 kg/m3 ⎝ D ⎠ ⎛ L ⎞ 2nd equation for Δp= 5.33 x 10-8 ⎜ ⎟ Substitute: ⎝ D5 ⎠ two unknowns Eq. 1: L = 100 D0.8 Δp= 5.33 x 10-6/D4.2 with Δp = 10,000 Pa
D = [5.33 x 10-6/Δp]1/4.2 = 6.2 mm and L = 100 x (0.0062 m)0.8 = 1.7 m
USPAS Short Course Boston, MA 6/14 to 6/18/2010 8 Single phase free convection heat transfer g g Q L or Q Q
D
Compressible fluid effect: Heat transfer warms the fluid near the heated surface, reducing density and generating convective flow. Free convection heat transfer is correlated in terms of the Rayleigh number, 3 n βΔTLg L = ()GrfNu ~Pr, CRaL where L GrRa Pr =≡ Dthν where g is the acceleration of gravity, β is the bulk expansivity, ν is the kinematic viscosity (μ/ρ) and D is the thermal diffusivity (k/ρC). th L (or D) are the scale length of the problem (in the direction of g)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 9 Free convection correlations
Free convection correlation for low For very low Rayleigh temperature helium number, Nu = 1 corresponding to pure conduction heat transfer For Ra < 109, the boundary layer flow is laminar (conv. fluids) 25.0 NuL ≈ 59.0 RaL
For Ra > 109, the boundary layer is turbulent 33.0 L ≈ 1.0 RaNu L
Example
USPAS Short Course Boston, MA 6/14 to 6/18/2010 10 Pool Boiling Heat Transfer (e.g. Helium)
Factors affecting heat transfer curve Surface condition (roughness, insulators, oxidation) Orientation Channels (circulation) Time to develop steady state (transient heating) Liquid Heated Note: Other cryogenic fluids have basically Surface the same behavior, although the numerical Q values of q and ΔT are different. USPAS Short Course Boston, MA 6/14 to 6/18/2010 11 Nucleate Boiling Heat Transfer
Nucleate boiling is the principal heat transfer mechanism for static liquids below the peak heat flux (q* ~ 10 kW/m2 for helium) Requirements for nucleate boiling Must have a thermal boundary layer of superheated liquid near the surface ΔTk δ = f ~ 1 to 10 μm for helium th q
Must have surface imperfections that act as nucleation sites for formation of vapor bubbles.
USPAS Short Course Boston, MA 6/14 to 6/18/2010 12 Critical Radius of Vapor Bubble
r 2σ Pv PL PP Lv += σ is the surface tension r
Critical radius: For a given T, p, the bubble radius that determines whether the bubble grows of collapses
r > rc and the bubble will grow
r < rc and the bubble will collapse Estimate the critical radius of a bubble using thermodynamics Clausius Clapeyron relation defines the slope of the vapor pressure line in terms of fundamental properties
dp ⎞ Δs hfg fg ph ⎟ = = ≈ 2 If the gas can be approximated as ideal dT ⎠sat Δv ()− vvT Lv RT and vv >> vL
USPAS Short Course Boston, MA 6/14 to 6/18/2010 13 Critical radius calculation
Integrating the Clausius Clapeyron relation between
ps and ps + 2σ/r
2 2 −1 2σ fg Δ RTTh 2σRTs rc = (e 1) ≈− ps sfg ΔTph
Example: helium at 4.2 K (NBP) Empirical evidence indicates that ΔT ~ 0.3 K
This corresponds to rc ~ 17 nm Number of helium molecules in bubble ~ 10,000 Bubble has sufficient number of molecules to be treated as a thermodynamic system Actual nucleate boiling heat transfer involves heterogeneous nucleation of bubbles on a surface. This is more efficient than homogeneous nucleation and occurs for smaller ΔT.
USPAS Short Course Boston, MA 6/14 to 6/18/2010 14 Nucleate Boiling Heat Transfer He I
2.5 Note that hnb is not constant because Q ~ ΔT
USPAS Short Course Boston, MA 6/14 to 6/18/2010 15 Nucleate Boiling Heat Transfer Correlations
The mechanism for bubble formation and detachment is very complex and difficult to model Engineering correlations are used for analysis
Kutateladse correlation
6.0 125.0 2/1 ⎡ 2/1 ⎤ ⎡ 2 2/3 ⎤ 7.0 h ⎛ σ ⎞ qC ρ lpl ⎛ σ ⎞ ⎛ ρ ⎞ ⎛ σ ⎞ ⎛ p ⎞ ⎜ ⎟ ×= 1025.3 −4 ⎢ ⎜ ⎟ ⎥ ⎢ ⎜ l ⎟ ⎜ ⎟ ⎥ ⎜ ⎟ ⎜ ⎟ ⎜ ⎟ × g 2/1 gk ρ ⎢ ρ gkh ρ ⎥ ⎜ μ ⎟ ⎜ gρ ⎟ ⎜ ()gρσ ⎟ ⎝ ll ⎠ ⎣ ⎝ llvfg ⎠ ⎦ ⎣⎢ ⎝ l ⎠ ⎝ l ⎠ ⎦⎥ ⎝ l ⎠
Rearranging into a somewhat simpler form,
2 3125.0 5.1 ⎡ ⎛ ρ ⎞ ⎤ pχ 75.1 ⎛ ρ ⎞ 5.1 −9 l 3 ⎛ ⎞ l ⎛ C p ⎞ ⎛ k ⎞ 5.2 q ×= 1090.1 ⎢g⎜ ⎟ χ ⎥ ⎜ ⎟ ⎜ ⎟ ×⎜ ⎟ ⎜ l ⎟()−TT ⎢ μ ⎥ ⎝ σ ⎠ ρ ⎜ ⎟ ⎜ ⎟ bs ⎣ ⎝ l ⎠ ⎦ ⎝ v ⎠ ⎝ h fg ⎠ ⎝ χ ⎠ 2/1 ⎛ σ ⎞ 2 5.2 where χ = ⎜ ⎟ cmWq 8.5)/( Δ= T For helium at 4.2 K ⎝ gρl ⎠
USPAS Short Course Boston, MA 6/14 to 6/18/2010 16 Peak Heat Flux (theory)
Understanding the peak nucleate boiling heat flux is based on empirical arguments due to instability in the vapor/liquid flow
Instability in the vapor-liquid boundary v vv v v vL vL v vL v
c L vv λ
Instability due to balance between surface energy and kinetic energy
2 2πσ ρ ρvL 2 c = − 2 ()− vv Lv ()+ ρρλvL ()+ ρρvL
Transition to unstable condition when c2 = 0
USPAS Short Course Boston, MA 6/14 to 6/18/2010 17 Peak Heat Flux Correlations
Zuber correlation:
1 1 4 2 * ⎡ ()− ρρσvl g ⎤ ⎡ ρl ⎤ ≈ Khq ρvfg ⎢ 2 ⎥ ⎢ ⎥ ⎣ ρv ⎦ ⎣ + ρρvl ⎦
Empirical based on Zuber Correlation
1 1 * 2 4 ≈ 16.0 vfg []ghq ()− ρρσρvl
~ 8.5 kW/m2 for He I at 4.2 K
Limits:
T Tc; q* 0 since hfg 0 and σ 0 1/2 T 0; q* ~ ρv (decreases)
q*max near 3.6 K for LHe
USPAS Short Course Boston, MA 6/14 to 6/18/2010 18 Film Boiling
Film boiling is the stable condition when the surface is blanketed by a layer of vapor Film boiling heat transfer coefficient is generally much less that that in nucleate boiling
Minimum film boiling heat flux, qmfb is related to the stability of the less dense vapor film under the more dense liquid
liquid
vapor ~ 10 μm
Q
“Taylor Instability” governs the collapse of the vapor layer
USPAS Short Course Boston, MA 6/14 to 6/18/2010 19 Film Boiling Heat Transfer Correlations
Factors affecting the process
Fluid properties: Cp, hfg, σ, ρl, ρv Fluid state: saturated or pressurized (subcooled) Heater geometry (flat plate, cylinder, etc.) Breen-Westwater correlation
8/1 4/1 ⎛ σ ⎞ ⎛ μ ()−TT ⎞ 2/1 h ⎜ ⎟ ⎜ bsv ⎟ ⎛ σ ⎞ fb 3 ⎜ ⎟ ⎜ ⎟ ⎜ ⎟ += 28.037.0 2 ⎝ g()− ρρvl ⎠ ⎝ k ()− vlvv gλρρρ' ⎠ ⎜ ⎟ ⎝ gD ()− ρρvl ⎠
Where, [ + 34.0 ( −TTCh )]2 λ'= fg bspv hfg Simplified form for large diameter
4/1 8/1 3 ⎛ g()− ρρvl ⎞ ⎛ k ()− vlvv gλρρρ' ⎞ 3 h = 37.0 ⎜ ⎟ ⎜ ⎟ 4 fb ⎜ ⎟ ( −≈ TTq fs ) ⎝ σ ⎠ ⎝ μ ()−TT bsv ⎠
USPAS Short Course Boston, MA 6/14 to 6/18/2010 20 Minimum film boiling heat flux
2 LHe @ 4.2 K Minimum film boiling heat Q/S, W/cm flux is less than the peak heat flux ≈ 0.9 Recovery to nucleate Film boiling
boiling state is associated Nucleate boiling with Taylor Instability. Transition boiling ≈ 0.3 1 4 ⎡ ⎤ qmfb g ()− ρρσvl mfb = 16.0 hq ρvfg ⎢ 2 ⎥ ⎣ ()+ ρρvl ⎦ Dimensionless ratio: ≈ 1 ≈ 4 1 (Ts-Tb), K 2 qmfb ⎡ ρv ⎤ ~ 0.36 for LHe @ 4.2 K = * ⎢ ⎥ ~ 0.1 @ 2.2 K q ⎣ + ρρvl ⎦ ~ 1 @ Tc = 5.2 K 2 ~ 0.09 for LN2 @ 80 K where q* ~ 200 kW/m
USPAS Short Course Boston, MA 6/14 to 6/18/2010 21 Prediction of Nucleate/Film Boiling for Helium
USPAS Short Course Boston, MA 6/14 to 6/18/2010 22 Experimental Heat Transfer (Helium)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 23 Prediction of Nucleate/Film Boiling for Nitrogen
USPAS Short Course Boston, MA 6/14 to 6/18/2010 24 Experimental Heat Transfer (Nitrogen)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 25 Internal two phase flow
Heat transfer depends on
various factors & 2 φ , Tm f Ts D Mass flow rate Q Orientation w/r/t gravity & 2 φ , Tm f Flow regime Quality (χ) g Void fraction (α) Total heat transfer rate D = + QQQ bfcT Ts where: Q is convective and Q is fc b Q gravity enhanced boiling.
Depending on factors above, either contribution may dominate
USPAS Short Course Boston, MA 6/14 to 6/18/2010 26 Horizontal flow two phase heat transfer
& 2 φ , Tm f Ts D Q Consider the case where gravitational effects are negligible Horizontal flow at moderate Re so that inertial forces dominate Correlation based on enhanced Nusselt number 9.0 1.0 5.0 Nu2φ ⎛1− x ⎞ ⎛ μ ⎞ ⎛ ρ ⎞ = f ()χ where χ = ⎜ ⎟ ⎜ L ⎟ ⎜ v ⎟ tt tt x ⎜ μ ⎟ ⎜ ρ ⎟ NuL ⎝ ⎠ ⎝ v ⎠ ⎝ L ⎠ (1− xm ) 4.08.0 Re = & and NuL = PrRe023.0 LL ; L μ AflowL Typical correlation (de la Harpe): Nu 2φ ≈ Aχ −m tt 1 for χtt large NuL with m ~ 0.385 and A ~ 5.4
USPAS Short Course Boston, MA 6/14 to 6/18/2010 27 Vertical channel heat transfer
& 2 φ , Tm f Main difference between this problem and pool boiling is that the fluid is confined within channel g D At low mass flow rate and self driven flows (natural Ts circulation) the heat Q transfer is governed by buoyancy effects Process is correlated against classical boiling heat transfer models In the limit of large D the correlation is similar to pool boiling heat transfer (vertical surface)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 28 Vertical channel maximum heat flux
Critical flow in an evaporator 1 Empirical observations 2 * w h ρvfg ⎡ gχ ⎛ []()βχ−+ 11ln ⎞⎤ ρ q = ⎢ c ⎜1− c ⎟⎥ β = l q* ~ w for small w β −12 ⎜ ()βχ−1 ⎟ z ⎣ ⎝ c ⎠⎦ ρv q* ~ z-1/2 for w/z < 0.1 q* ~ constant for w/z m& v ⎞ and χc = ⎟ “Critical quality” >> 1 m& ⎠ max ~ 0.3 for helium
USPAS Short Course Boston, MA 6/14 to 6/18/2010 29 Example: Cryogenic Stability of Composite Superconductors (LTS in LHe @ 4.2 K)
Used in large magnets where flux jumping and other small disturbances are possible and must be arrested General idea: in steady state ensure that cooling rate exceeds heat generation rate (Q > G) Achieved by manufacturing conductor with large copper (or aluminum) fraction and cooling surface
Lower overall current density G/S I2R/S Potentially high AC loss (eddy currents)
Current Fully Sharing normal Composite Conductor
T (K) T (K) T (K) T (K) Copper/Aluminum stabilizer b cs c Insulating spacer (G-10)
NbTi/Nb3Sn Icu Isc
V=IcuR cu
USPAS Short Course Boston, MA 6/14 to 6/18/2010 30 Cryogenic Stability (LHe @ 4.2 K)
Case 1: Unconditional stability, recovery to fully superconducting state occurs uniformly over length of normal zone Case 2: Cold End recovery (Equal area criterion): Excess cooling capacity (area A) > Excess heat generation (area B)
Q/S is the LHe boiling heat Q/S transfer curve for bath cooling or A normalized per surface area G/S 2 B 1 G/S is the two part heat generation Curve for a composite superconductor Tcs is the temperature at which Top = Tc
Tb (K) Tcs (K) Tc (K) Tx (K)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 31 Transient Heat Transfer
Heat transfer processes that occur on time scale short compared to boundary layer thermal diffusion. Why is this important in cryogenics? -4 2 2 (Dth (copper) ~ 10 m /s @ 300 K; ~ 1 m /s @ 4 K) Normal liquid helium has a low thermal conductivity and large heat capacity
k f D = ~ 3 x 10-8 m2/s (LHe @ 4.2 K) f ρC q T(x) π 1 2 -4 1/2 δth = ( f tD ) ~ 3 x 10 t [m] for LHe @ 4.2 K 2 ~ 1.5 t1/2 [m] for copper @ 4.2 K δth hL Lumped capacitance condition: Bi <<= 1 ~ 10L [m] k
Note that this subject is particularly relevant to cooling superconducting magnets, with associated transient thermal processes Important parameters to determine * ΔE = q Δt (critical energy) T – surface temperature during heat transfer USPAS Shorts Course Boston, MA 6/14 to 6/18/2010 32 Transient Heat Transfer to LHe @ 4.2 K
Time evolution of the temperature difference following a step heat input: Steady state is reached after ~ 0.1 s
USPAS Short Course Boston, MA 6/14 to 6/18/2010 33 Critical Energy for Transition to Film Boiling
Hypothesis: The “critical energy” is determined by the amount of energy that must be applied to vaporize a layer of liquid adjacent
to the heated surface. Energy required Δ = ρ hE δ thfgl q* LHe Layer thickness determined by diffusion π 1 2 δth = ( f tD ) 2 δth Critical flux based on heat diffusion:
1 π ⎛ k ⎞ 2 * = ρ hq ⎜ l ⎟ fgl ⎜ * ⎟ 2 ⎝ ρl ΔtC ⎠ ~ 0.09 Δt-1/2 [W/cm2] @ 4.2 K
USPAS Short Course Boston, MA 6/14 to 6/18/2010 34 Surface Temperature (Transient HT)
During transient heat transfer, the surface temperature will be higher than the surrounding fluid due to two contributions: Fluid layer diffusion: transient conduction in the fluid layer will result in a finite temperature difference Kapitza conductance: At low temperatures, there can be a significant temperature difference, ΔTk, due to thermal impedance mismatch (more on this subject later). This process is dominant at very low temperatures, but is small above ~ 4 K, so is normally only important for helium systems. Fluid layer diffusion equation: 2 Δ∂ Tf 1 Δ∂ Tf k 2 = ; D f = ∂ Dx f ∂t ρC p
Boundary conditions:
ΔTf (x,0) = 0; initial condition Solution is a standard second order differential equation with two ΔTf (infinity, t) = 0; isothermal bath spatial and one time boundary q = -k dΔT /dt) ; heat flux condition f f x=0 condition. Solid is isothermal (Bi = hL/k << 1)
USPAS Short Course Boston, MA 6/14 to 6/18/2010 35 Transient diffusion solution
ΔTf Integrating the diffusion equation:
21 q ⎡ ⎛ tD ⎞ ⎛ x2 ⎞ ⎛ x ⎞⎤ q T =Δ ⎢2⎜ f ⎟ exp⎜− ⎟ − xerfc⎜ ⎟⎥ f k ⎜ π ⎟ ⎜ 4 tD ⎟ ⎜ 2()tD 21 ⎟ f ⎣⎢ ⎝ ⎠ ⎝ f ⎠ ⎝ f ⎠⎦⎥
Evaluating at x = 0 (surface of heater) x 21 2 ⎛ tq ⎞ ()xT 0 ==Δ ⎜ ⎟ f ⎜ ⎟ π ⎝ ρ kC fp ⎠
The transient heat transfer coefficient can then be defined 21 q π ⎛ ρ kC fp ⎞ h = = ⎜ ⎟ ΔTf 2 ⎝ t ⎠ 1.0 h ≈ ; kW/m2K for helium near 4 K t
2 2 At t = 10 μs; h ~ 30 kW/m K and for q = 10 kW/m ; ΔTf ~ 0.3 K Note: this value of h >> h (nucleate boiling HT coefficient) USPAS Short Course Bostonnb, MA 6/14 to 6/18/2010 36 Summary Cryogenic Heat Transfer
Single phase heat transfer correlations for classical fluids are generally suitable for cryogenic fluids Free convection Forced convection Two phase heat transfer also based on classical correlations Nucleate boiling Peak heat flux Film boiling Transient heat transfer is governed by diffusive process for ΔT and onset of film boiling
USPAS Short Course Boston, MA 6/14 to 6/18/2010 37