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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

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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

uT0

T

dT

L

U¥, T¥, P¥

Solid Wall

d

uC0

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

6

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