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1
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Utilization of Analogy Experimental Method for the
Preliminary Verification of the Safety System with
Highly Buoyant or Extreme Test Condition
June 6. 2017
Hae-Kyun Park
Kyung Hee University, Republic of Korea
2
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Introduction
• Cooling performance of the system must be verified during design and licensing
periods of the nuclear power plant.
• However, safety verification of the nuclear systems is not easy.
– Huge systems in nuclear power plant (High buoyancy force)
– Extreme condition when severe accident occurs
Emergency Passive Containment Cooling System
3
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Introduction
• Heat transfer experiments have been conducted to verify nuclear safety systems.
– Huge facility to simulate high buoyancy force
– Hard to establish steady-state
– Preventing heat leakage from the facility
– Considering radiation heat transfer
– High cost
We propose mass transfer experimental method to overcome these problems
4
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Solid Wall
d
U¥
uT0
T
T¥
dT
L
U¥, T¥, P¥
Solid Wall
d
U¥
uC0
C
C¥
L
U¥, C¥, P¥
dc
Heat and Mass Transfer Analogy
Mass transfer Heat transfer
2DCD C
Dt 2DT
TDt
2 2
2 2
Du P u uX
Dt x x y
0u
x y
• Boundary Layers
• Governing Equations
Heat transfer Mass transfer
Nu Sh
Pr Sc
Ra Ra
hx
k
m
m
h x
D
mD
3g Tx
3
m
gx
D
• Dimensionless Numbers
5
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Analogy Experimental Methodology (AEM)
Heat Transfer Problem (Solution) ↔ Mass Transfer Problem (Solution)
• CuSO4-H2SO4 Electroplating System
– Easy achievement of high Rayleigh number with compact test rig
– Easy to establish steady-state
– High accuracy in measurement
– No heat leakage
– Free from radiation heat transfer
– Low cost
Heat Transfer
Problem
Mass Transfer
Problem
Heat Transfer
Solution
Mass Transfer
Solution
Analogy
concept
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Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Mass Transfer in Electroplating System
2
2
2 : Anode reaction
2 : Cathode reaction
Cu Cu e
Cu e Cu
Schematic of mass transfer phenomena in copper sulfate-sulfuric acid solution.
-+
Electric
migration
Diffusion
Convection
Cu2+
H+ SO4
2-
• Mass transfer can be measured
easily and correctly by measuring
the current. : Heat transfer = Mass(Cu2+) Transfer
• The electric migration can be
suppressed by increasing the
conductivity of the solution.
7
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
300 400 500 600 700 800
200
250
300
350
400
450
500
550 0.66(Gr Sc)1/4
Present Experiment
Sh
Gr Sc1/4
Heat transfer correlations
Mass transfer correlations
Application – Simple geometries Sang-Hyuk Ko et al., Nuclear Engineering and Technology, Vol. 38, pp. 251-258, 2006.
⇒ Be in good agreement between Correlation and Experiment data
0 100000 200000 300000 400000 500000 600000
20
30
40
50
60
70
80
90
100
110
120
130
Sh
Re Sc d/L
1.467(Re Sc d/L)1/3
Present Experiment
Natural convection on a vertical plate Forced convection (Poiseuille flow)
1/40.67L LNu Ra
1/40.66L LSh Ra
″Analogy concept″
1/3
1.467av
dNu RePr
L
1/3
1.467 Reav
dSh Sc
L
8
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
VHTGR Mixed Convection Heat Transfer
Water
Air
RPV
AirChimney
RuptureDisc
• VHTGR: Mixed convection heat transfer
• RCCS: Chimney effect
• SFR-AHX: Heat transfer of the helical tube
• IVR-ERVC: Internal and external vessel phenomena
9
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
VHTGR Mixed Convection Heat Transfer
Mixed convection regions
Correlation Development
Heat Transfer in a Vertical Pipe
Transition Criteria for a Vertical Pipe
10
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Buoyancy-opposed and aided mixed convection
Turbulent Mixed Convection of Vertical Pipe
VHTGR – Mixed Convection (1/2)
Bong-Jin Ko et al., Nuclear Engineering and Design, Vol. 240, pp. 3967-3973, 2010.
Bong-Jin Ko and Bum-Jin Chung, Transactions of the KSME B, Vol. 34, pp. 481-489, 2010.
Comparisons of the forced convection correlation
Di = 0.032 m Di = 0.02 m Test apparatus
<Maximum height = 0.89 m> Starting point to mixed convection
Laminar Mixed Convection of Vertical Pipe
Test apparatus
<Maximum height = 0.24 m> Aiding and opposing flow with existing correlations Comparison between NuH and NuD
11
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
VHTGR – Mixed Convection (2/2)
Gyeong-Uk Kang and Bum-Jin Chung, Heat and Mass Transfer, Vol. 48, pp. 1183-1191, 2012.
Correlation dependence of the H/Di
Correlations varying the Diameter and Height
2 3 3where, ( / ) 205.95( / ) 7.89 10 ( / ) 3.45 10i i if H D H D H D
0.522
1 ( / )i
f f
Sh Shf H D Bo
Sh Sh
Opposed flow
Aided flow
12
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Water
Air
RPV
AirChimney
RuptureDisc
Fin
Plate-fin
Chimney Chimney Height
Chimney Cross-section
Chimney Width
VHTGR – RCCS Performance Enhancement
13
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Chimney Height, Diameter and Pr effects
VHTGR RCCS – Chimney effect Myeong-Seon Chae and Bum-Jin Chung, International Communications in Heat and Mass Transfer, Vol. 66, pp. 196-202, 2015.
Seung-Min Ohk and Bum-Jin Chung, International Journal of Thermal Sciences, Vol. 115, pp. 54-64, 2017.
Compare to existing correlation Test results with respect to duct lengths and diameters
Natural Convection Inside an Open Vertical Pipe
Velocity profiles with respect to Pr Compare to existing correlation
Test apparatus
<Maximum height = 0.2 m>
Test apparatus
<Maximum height = 1 m>
14
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Natural Convection on a Vertical Finned Plate
Test apparatus
<Maximum height = 0.05 m>
Finned plate correlations Optimal fin spacing
Chimney width on a Vertical Finned Plate
Vertical finned plate correlations Experimental results and developed correlation
VHTGR RCCS – Fin and Chimney effects Seung-Hyun Hong and Bum-Jin Chung, International Journal of Thermal Sciences, Vol. 101, pp. 1-8, 2016.
Je-Young Moon et al., Nuclear Engineering and Design, Vol. 293, pp. 503-509, 2015.
Test apparatus
<Maximum height = 0.86 m>
15
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Chimney width on a Vertical Finned Plate
Vertical finned plate correlations Experimental results and developed correlation
VHTGR RCCS – Fin and Chimney effects Je-Young Moon et al., Nuclear Engineering and Design, Vol. 293, pp. 503-509, 2015.
Test apparatus
<Maximum height = 0.86 m>
Heat transfer enhances as H↑, S↓ and TC ↓
Fin chimney Duct chimney
16
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Scaling Analysis
Horizontal cylinder Inclined plate In-lined cylinder
Inclined cylinder Staggered cylinder
17
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Separate Effects
18
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Separate Effects
19
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Separate Effects
20
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Separate Effects
21
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Natural Convection on an Inclined Cylinder
Visualization of flow separation
SFR – AHX Separate Effect Tests (1/2)
Chul-Kyu Lim and Bum-Jin Chung, Heat and Mass Transfer, Vol. 51, pp. 713-722, 2015.
Jeong-Hwan Heo and Bum-Jin Chung, Chemical Engineering Science, Vol. 73, pp. 366-372, 2012.
Natural Convection on Inclined Plates
Test apparatus
<Maximum height = 0.35 m>
Critical lengths for angles NuL measured with respect to angle
Test apparatus
<Maximum height = 0.45 m> Single cylinder correlations Developed correlation for inclined angle
Visualization of flow separation
compared with heat transfer experiment
22
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Separate Effect Tests (2/2)
Jeong-Hwan Heo and Bum-Jin Chung, Heat and Mass Transfer, Vol. 50, pp. 769-777, 2014.
Myeong-Seon Chae and Bum-Jin Chung, Chemical Engineering Science, Vol. 66, pp. 5321-5329, 2011.
Two in-lined cylinders
Natural Convection on In-lined Horizontal Cylinders
Visualization of the natural convection Temperature contours (a) Velocity (b) Temperature
Test results with existing correlations
Natural Convection on Staggered Horizontal Cylinders
The velocity and temperature fields Single cylinder correlations Horizontal pitch effects Staggered cylinders
23
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
SFR – AHX Parametric effects (2/2) Joo-Hyun Park et al., International Communications in Heat and Mass Transfer, Vol. 59, pp. 11-16, 2014.
Natural Convection on an Inclined Helical tube in a Duct
NuD according to inclination for helical tube in a duct
(b) P/D = 1.3 (a) P/D = 5
Pitch
Near vertical
Near horizontal
24
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
IVR-ERVC strategy
Oxide Pool
- Natural convection
- Heat ratio (Top and Bottom)
- Angular heat flux distribution
Metallic layer
- Rayleigh-Benard convection
- Focusing effect
External Reactor Vessel Cooling
- Boiling heat transfer
- Critical heat flux
- Bottleneck effect
25
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
IVR-ERVC – Metallic layer Je-Young Moon and Bum-Jin Chung, International Journal of Thermal Sciences, 2017 (Submitted).
Pr effect on Laminar Natural Convection in a Rectangular Enclosure
Test apparatus
<Maximum height = 0.04 m>
Comparison of mean Nu with existing studies
Temperature and velocity contours according to Pr
Cell patterns of R-B convection
0.2510.46H HNu Ra
26
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Effect of Volumetric Heat Source on 2-layer 2D Oxide Pool Configuration
IVR-ERVC – Oxide Pool (1/2) Su-Hyeon Kim and Bum-Jin Chung, Nuclear Engineering and Design, Vol. 308, pp. 1-8, 2016.
Hae-Kyun Park and Bum-Jin Chung, Nuclear Engineering and Technology, Vol. 48, pp. 906-914, 2016.
Test apparatus
<Maximum height = 0.1 m> Comparison of mean and local Nu with existing studies
Test apparatus
<Maximum height = 0.1 m>
Comparison of mean and local Nu with existing studies
Effect of Volumetric Heat Source on 2-layer 3D Oxide Pool Configuration
27
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Comparison of 2D and 3D Configuration of 2-layer Oxide pool with different Ra′H
IVR-ERVC – Oxide Pool (2/2) Su-Hyeon Kim et al., Nuclear Engineering and Technology, 2017 (Submitted).
Su-Hyeon Kim and Bum-Jin Chung, Progress in Nuclear Energy, 2017 (Submitted).
Comparison of mean Nu with existing studies Development of correlations and multiplier
Test apparatus
<Maximum height = 0.167 m>
Comparison of Oxide Pool of 3-layer Configuration with Different Aspect ratio
Comparison of upward heat ratio according H/R
Test apparatus
<Maximum height = 0.078 m> Comparison of angular and top plate Nu subject to H/R
28
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
IVR-ERVC – Oxide Pool (2/2) Su-Hyeon Kim and Bum-Jin Chung, Progress in Nuclear Energy, 2017 (Submitted).
Comparison of Oxide Pool of 2 and3-layer Configuration with Different Aspect ratio
Pr > 1
Pr < 1
Comparison of mean and local Nu with existing studies
Comparison of angular and top plate Nu subject to H/R
2-layer configuration 3-layer configuration
29
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Two-phase flow (Heat transfer) ↔ Two-component flow (Mass transfer)
• Basic idea
– Hydrodynamic behaviors between two-phase and two-component system are analogous under identical gas volume condition.
• Non-heating CHF simulation methodology using H2SO4 solution
– Experimental easiness
– Less fatigue and able to avoid mechanical failure of test rig
– Less hazardous during experiment
SO42- O2- Cu2+
H+
H2SO4 solution
Copper Anode
H2
2
2
2 : Anode
2 2 : Cathode
Cu Cu e
H e H
Non-heating CHF Simulation Methodology (1/2)
Copper cathode
30
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Heat transfer experiment (Just after CHF) Mass transfer experiment (Just after CCD)
Preliminary Study for Simulating ERVC situation (1/2)
Critical Current Density on the Horizontal upward Disk
Similarity between Critical Heat Flux and Critical Current Density
Test apparatus for mass transfer experiment Test circuit Measured current with applied potential
31
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Mass transfer (Just after CCD)
175º 135º 90º
Heat transfer (Just after CHF)
Mass transfer results for downward facing plate (Just after CCD)
Preliminary Study for Simulating ERVC situation (2/2)
32
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
• Safety verification of the nuclear safety system were conducted using
mass transfer experiments
– VHTGR, SFR, RCCS, IVR-ERVC etc.
– Well agreed with existing heat transfer correlations
• Advantages in utilization of CuSO4-H2SO4 electroplating system
‒ Easy achievement of high Rayleigh number with compact test rig ‒ Easy to establish steady-state ‒ High accuracy in measurement ‒ No heat leakage ‒ Free from radiation heat transfer ‒ Low cost
• Expanding analogy experimental methodology
– Easy to achieve CHF regime with non-heating system
– Measurement of cupric ion concentration using interferometer
Summary
33
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Appendix
34
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Appendix – Limiting Current Curve
0 150 300 450 600 750 900
0.0
1.5
3.0
4.5
6.0
7.5
9.0
10.5Rayleigh number = 3.645 X 10
10
CuSO4 = 0.1 M , H
2SO
4 = 1.5 M
AR ~ 1 (H/L = 6/6 cm)
Electrode type : 11.8 X 6 (cm2)
Cu
rre
nt
de
ns
ity
(mA
/cm
2)
Potential (mV)
Ilim
Limiting
current
• Cathode reaction
1) Transport of copper ion from bulk to cathode (N1)
2) Electroplating reaction (N2)
• For Steady-state,
⇒
Where, k = Reaction rate constant
→ Large increase in reaction rate constant,
following applied potential : Cs ~ 0
⇒ Finally, mass transfer coefficient :
1 ( )m b sN h C C
2 sN k C
( ) m b s sh C C k C m bs
m
h CC
h k
lim(1 )nm
b
t Ih
nFC
35
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Natural Convection on Outside of an Vertical Cylinder with High Pr
VHTGR – Natural Convection in a Vertical Pipe Gyeong-Uk Kang and Bum-Jin Chung, International Journal of Heat and Mass Transfer, Vol. 79, pp. 4-14, 2014.
Gyeong-Uk Kang and Bum-Jin Chung, International Journal of Heat and Mass Transfer, Vol. 87, pp. 390-398, 2015.
Test apparatus
<Maximum height = 0.28 m> Test results with existing correlations Developed correlations for laminar and turbulent regime
Effects of the Vertical Cavities with Active and Inactive Top and Bottom Disks
Test apparatus
<Maximum height = 0.6 m> Test results with existing correlations All surfaces active Only vertical surface active
36
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Local Heat Transfer according to the Height
VHTGR – Mixed Convection (2/2)
Myeong-Seon Chae and Bum-Jin Chung, NTHAS10, Kyoto, Japan, N10P1005, 2016.
Gyeong-Uk Kang and Bum-Jin Chung, Heat and Mass Transfer, Vol. 48, pp. 1183-1191, 2012.
0 500 1000 1500 2000 2500 3000
0
200
400
600
800
1000
Laminar forced correlation [Kays, 1955]
Fitted correlation
Current data
RaH=1.710
8, H=0.01 m, D=0.063 m, Re
D= 210, 985, 1,999
Nu
D
ReD
4000 6000 8000 10000 12000 14000 16000 18000
500
1000
1500
2000
2500
3000 Turbulent forced correlation [Petukhov et al., 1972]
Current data
RaH=1.710
8, H=0.01 m, D=0.063 m, Re
D=4,026, 6,285, 9,992, 12,773, 16,050
Nu
D
ReD
108
109
1010
1011
1012
1013
1014
0.0
0.5
1.0
1.5
2.0Previous studies
Vilemas et al.
RaH=1.4510
13, Re
D=8,850
RaH=1.5610
13, Re
D=11,400
RaH=1.7910
13, Re
D=12,400
Parlatan et al.
RaH=5.4310
13, Re
D=4,578
Current experiments, RaH=2.1110
13
ReD=4,026 Re
D=6,285
ReD=9,992 Re
D=12,773
ReD=16,050
Nu/N
ufc
Rax
Test apparatus
<Maximum height = 0.5 m> Existing laminar and turbulent correlation Buoyancy aided mixed convection results
Existing data and experiments Correlation dependence of the H/Di
Correlations varying the Diameter and Height
2 3 3
where, ( / )
205.95( / ) 7.89 10 ( / ) 3.45 10
i
i i
f H D
H D H D
Correlation developed via mass transfer experiments
0.522
1 ( / )i
f f
Sh Shf H D Bo
Sh Sh
37
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Visualization of heat transfer on a sphere (Top view)
Test apparatus
<Maximum height of packed bed = 0.15 m>
Heat Transfer Visualization on a Sphere
VHTGR – Natural Convection on Packed Bed Dong-Young Lee and Bum-Jin Chung, Heat and Mass Transfer (Submitted).
Dong-Young Lee, Myeong-Seon Chae and Bum-Jin Chung.
Results with existing correlations
Natural Convection Heat Transfer of Heated Packed bed
Test apparatus
<Maximum diameter = 0.12 m> Comparisons with existing correlation
Nud depending on position of heat source
D = 2 cm D = 4 cm
D = 6 cm D = 12 cm
38
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
Natural Convection on a Helical tube
SFR – AHX Parametric effects (1/2)
Jeong-Hwan Heo and Bum-Jin Chung, International Journal of Heat and Mass Transfer, Vol. 55, pp. 2829-2834, 2012.
Je-Young Moon et al., Heat and Mass Transfer, Vol. 51, pp. 1229-1236, 2015.
A
B
C
P/D≒2.6
P/R > 2.3 P/R < 2.3
Effect of P/D and N Nu subject to the D and L Effect of P/R Schematic of the test apparatus
<Maximum height = 0.29 m>
Natural Convection on an Inclined Helical tube
NuD for P/D = 2.0 NuD ratio according to P/D at θ = 90°, 40° Test apparatus
<Maximum height = 0.29 m>
39
Department of Nuclear Engineering
Kyung Hee University
International Conference on Topical Issues in Nuclear
Installation Safety, Vienna, Austria, June 6, 2017
CHF h fg gq A h
• The measured current can be transformed to the CHF by
Unit transformation factors
(m3/s → kW/m2) Gas generation rate (m3/s)
Non-heating CHF Simulation Methodology (2/2)
• Hydrogen generation rate on the cathode can be calculated by the measured current.
Unit transform
(A → mol/s)
273.15STP
A
I TV
neN
Temperature correction
applying Charles’s law
Unit transform
(mol/s → m3/s)
1
3
: Electric charge ( )
: Current ( )
: Number of electrons in charge transfer reaction
: Avogadro number ( )
: Temperature ( )
: Volume at standard temperautre and pressure ( )
: Gas genearation rat
A
STP
e C
I A
n
N mol
T K
V m
3e ( /s)m
2
2
3
: Heated area ( )
: Latent heat ( / )
: Critical heat flux ( / )
: Gas density (kg/ )
h
fg
CHF
g
A m
h kJ kg
q kW m
m