Thermofluids Data Book

30
M EC6422 Nucl ear Thermal H ydrauli cs and H e at Tr ans fer DA TA BOOK S. H e (2012) 1 MEC6422 Nuclear Thermal Hydraulics and Heat Transfer (2012-2013) DATA BOOK Chapters 1, 2 & 3 Nuclear Power Generation Fundamentals

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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MEC6422

Nuclear Thermal Hydraulics and Heat Transfer 

(2012-2013)

DATA BOOK

Chapters 1, 2 & 3 Nuclear Power Generation Fundamentals

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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Power density

 

√   

Specific power 

   

 

   

 

   

Energy generation ∑    

∑  

where  

 

 

Decay heat

 

     

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Chapter 4 Thermal analysis of fuel elements

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Thermal conductivity of fuel:

k ,

Loeb equation:

 

Modified Loeb equation: , where is between 2 and 5.

Biancharia model: , where α2=1.5.

Temperature distribution in solid and annular fuel:

 

 

     

where () 

Fuel restructure- Three zone distribution:

Zone 3:

 

Zone 2:

 

Zone 1

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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where

 

Two zone modelZone 2:

 

Zone 1:

 

Gapping effect

 

 

   

Overall temperature distribution in fuel

 

Chapter 5 Heat transfer to coolant – single phase

Governing equations  

 

 

Laminar flow

 

 

   

 

Turbulent flow

 

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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     Blasius relation (Re<30,000):

 

 

McAdams relation (30,000<Re<1,000,000):   The Karman-Nikuradse:

   (  ) The empirical Colebrook equation:

      

Bare rod bundles    

where

 

Pressure drop at spacers

DeStordeur model:

   

where Cs can be obtained from Figure 9-26.

Rehme model:

   

where Cv is the modified drag coefficient, which is again a function of Re. Rehme’ data show Cv = 9.5 for Re=104 and Cv=6.5 at Re=105.

Expansion and contraction:

 

 

 

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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Laminar heat transfer 

 

∫ ∫  

   

 for q’’=const.  for Tw=const.

The length of the thermal developing region:  

An alternative expression due to Bhatti and Savery:  

 

 

Turbulent heat transfer  

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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Non-metallic fluids:

(1) For circular pipe the following expressions are often been used:

  Dittus-Boelter equation:

 

where n = 0.4 when fluid is heated and n=0.3 when fluid is cooled; 0.7<Pr<100 and Re > 10,000 and L/D>60.  Seider and Tate equation:

 

0.7<Pr<120 and Re > 10,000 and L/D>60.

  Colburn equation:

 0.7<Pr<100 and Re > 10,000 and L/D>60

(2) Rod bundles

General expression:  where Nuc.t. is correlation for a circular tube, say, Dittus-Boelter.

Presser for infinite arrays:

 

for triangular array and 1.05≤P/D≤2.2, and

 

for square array and 1.05≤P/D≤1.9.

Weisman [51] for water in infinite arrays:

 and  

for triangular array and and 

for square array and .

Markocz for a finite array (Fig 10-14): where Re is based on the hydraulic diameter defined as:

∑  ∑  

and B=De/D and D is the diameter of the rod

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(3) Entrance effectEntrance length:

 

 Mean Nusselt number (McAdams):

 for Re >10,000, 0.7<Pr<120 and square-edge entries,

Local Nusselt number:For uniform velocity and temperature at the inlet:

 

 

For abrupt entrance:

 

 

Metallic fluids:

(1)  Circular tube with constant heat flux along and around the tube:

 

(2)  Circular tube with constant axial wall temperature and uniform radial heat flux:

 (3)  Parallel plate with constant heat flux through one wall and adiabatic in the other:

 

(4)  Concentric annuli with fully developed flow and the boundary condition of uniform heat flux in the inner

wall, D2/D1>1.4:

 

(5)  Rod bundlesWestinghouse [25]

 

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For 1.1≤P/D≤1.4, 10≤Pe≤5000, where P is pitch and D is diameter of the rod. 

Schad-modified [25]

 

For 1.1≤P/D≤1.5, 150≤Pe≤1000 and 

 

For Pe<150.

Chapter 6. Two-phase flow

6.1 Fundamentals of two phase flows

 f   g  W W W  .

 AW G / ,  AW G f   f  / ,  AWg G

 g / .

G

G

W  x

g  g  ,

G

G

W  x

f   f  1  

 A

 A g   ,

 A

 A f   f      1 .

 f  

 g 

u

u K  ,

 

  

 

 

 

 

  

  

 

 

 

  

   1

1  g 

 f  

 x

 x K   

 f   g  R uuu  

 H  g  D uuu  

 g  g  g  g  u AW     

 f   f   f   f   u AW     

 f   g 

 g 

v x K  xv

 xv

)1(    

 f   g 

 f  

v x K  xvv x K )1(

)1(1

   

 A

Q j

 g  , A

Q j

f  

 f    

 g  g  g  u AQ ,  f   f   f   u AQ  

 f   g 

 g 

QQ

Q

   ,

 f   g 

 g 

v x xv

 xv

)1(   

 Av M u g  g 

 g  

, ])1([  f   g  g  v x K  xvGu  

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

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 A

v M u

f   f  

 f  )1(  

, ])1([  f   g  f   v x K  xv K 

Gu .

 

 g 

 g 

 ju ,

 1

 f  

 f  

 ju .

])1([  f   g  H  v x xvGu  

 f   g m       )1(  

 f   g m

 x K  x

 x K  x

      

/)1(/

)1(

 

 f   g  H 

 x x        

/)1(/

1

 

)1(

)1(

 x K  x

v x K  xv

v

f   g 

m

 

 f   g  H  v x xvvv )1(  

222

0

 g 

 Fg 

 f  

 Ff  

 fo

 Ff   F  dz 

dp

dz 

dp

dz 

dp

dz 

dp   

 

  

 

 

  

 

 

  

 

 

  

  1

 

0

2

0

 Ff   F 

 f  dz 

dp

dz 

dp 

  

  

  

   , where

 

  

 

 D

vG f  

dz 

dp f   fo

 Ff  

2

0

 Ff   F 

 f  dz dp

dz dp

  

  

  

  

2  , where

  

  

 Dv xG f  

dz dp f   f  

 Ff  

2

)]1([2  

 Fg  F 

 g dz 

dp

dz 

dp 

  

  

  

 

2  , where

 

  

 

 D

vGx f  

dz 

dp g  g 

 Fg 

2][2

 

4/1Re079.0

fo fo f   ,

4/1Re079.0

f   f   f   ,

4/1Re079.0

g  g  f    

 f   fo GD  /Re ,  f   f   f   DG  /Re ,  g  g  g  DG  /Re ,

 Fg 

 Ff  

 f  

 g 

dz dp

dz dp

 X  /

/2

2

2

 

 .

1  Note that in the lecture notes, ‘sf’ and ‘f’ were both used to refer to ‘liquid’, e.g,

 Ff   sf   F  dz dpdz dp //, and

similarly, ‘sg’=’g’ referring to gas, e.g.,  Fg  sg  F  dz dpdz dp // ,  

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6.2 Flow Patterns

(1) Verti cal flow - Hewitt and Roberts (1969)

 f  

 f   f   xG j

    

2

2 )1(  

 g 

 g  g 

 xG j

    

22  

Figure 1. Hewitt and Roberts (1969) map for 

vertical flow

(2) Hori zontal f low - Baker (1954)2/1

 

  

  

  

 

w

 f  

 A

 g 

  

  

  

    ,

3/12

 

 

 

  

  

  

  

 

 f  

w

w

 f  w

  

  

 

 

 

    

where ρw= 1000 kg/m3; ρA,=1.23 kg/m

3; μw = 0.001 Ns/m

2 and σw = 0.072 N/m.

Figure 2. Two-phase flow pattern map of Baker (1954) for horizontal tubes

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(3) Taitel and Dukler (1976) uni fi ed flow pattern for hori zontal fl ows 

 Fsg 

 Fsf  

dz dp

dz dp X 

/

/2 ,

     

  

cos Dg 

 j Fr 

 g  f  

 g 

,

2/1

cos)(

)/(

      g 

dz dpT 

 g  f  

 sf  ,

2/1

2/1

Re sf  

 f  

 f    Fr v

 j D Fr  K   

 

 

   

Figure 3 Taitel and Dukler (1976) flow pattern for horizontal flows

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6.3 The homogeneous and separated flow model

(1) The homogeneous model

Governing equations:

u AW     

dz ud 

 AW  g 

dz  F d 

 Adz dp     sin1  

dz  g u

d diwq     sin2

2

 

  

   

where dpvdE di .

Relationships for homogeneous fluid mixture:

 f   g  uuu ,

 jvGu ,

    v

 xv g  

  

1][])1([

G

 j xvvv x xv

Qv  fg  f   f   g   

Static pressure drop:

 

  

 

 

 

 

 

 

 

 

 

 

  

 

dp

dv xG

vv xv

 g 

dz 

dx

v

vvG

v

v x

 D

vG f  

dz 

dp

 g 

 f   fg  f   f  

 fg 

 f  

 f  

 fg  f  TP 

2

2

2

1

)]/(1[

sin1

2  

 

Frictional pressure gradient

2

0

 fo

 Ff   F  dz 

dp

dz 

dp 

 

  

 

 

  

   

where D

vG f  

dz 

dp f   f  

 Ff  

2

0

0

2

 

  

  and

 

 

 

 

 f  

 fg  fo

v

v x1

2  (method 1) or 

4/1

211

 

 

 

 

 

 

 

 

 g 

 gf  

 f  

 fg 

 fo xv

v x

 

   (method 2)

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(2) The separated flow model

(i ) Static pressure gradient 

 

 

 

 

 

  

 

 

 

 

 

  

  

 

  

 

 

  

 

2

2

2

222

2

2

2

22

2

2

)1(

)1(1

)1(

)1(

)1(

)1(22

sin)]1([2

  

 

 

  

 

  

        

 g  f  

 x

 g 

 g  f  

 p

 f   g 

 f   g  fo

 f   fo

v xv x

 pdp

dv x

dz 

dpG

v xv x

 x

v x xv

dz 

dxG

 g  D

vG f  

dz 

dp

 

(ii ) The Lockhart-Martinelli (1949) correlation 

1) Graphic form

Figure 4. Lockhart-Martinelli (1949) correlation

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2) Analytical form

2

2 11

 X  X 

C  f     ,

221 X CX  g     

where the value of C is given below for the various flow regimes:

liquid gas Cturbulent turbulent (tt) 20

viscous turbulent (vt) 12

turbulent viscous (tv) 10

viscous viscous (vv) 5

Table 1 Lockhart-Martinelli (1949) correlation constants

(ii i) The Fri edel correlation (1979) 

035.0045.0

321

2 24.3We Fr 

 A A A fo    

where

 

 

 

 

 fo g 

 go f  

 f  

 f   x x A

  

  22

1 )1(  

224.078.0

2 )1( x x A  

7.019.091.0

31

 

 

 

 

 

 

 

 

 

 

 

 

 f  

 g 

 f  

 g 

 g 

 f   A

 

 

 

 

  

   

2

2

   gD

G Fr   

   

 DGWe

2

 

 f   g  x x      

/)1(/

1

 

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(iv) The Mar tinell i-Nelson (1948) corr elation 

(a) value of 2

 fo  as function of pressure and mass quality

(b) Void fraction as a function of quality α and absolute pressure for steam water  

Figure 5. Martinelli-Nelson 1948 Correlation

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(v) The Thom corr elation (1964)  

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(iv) The Baroczy correlation (1965) 

 

  

  )1356(

22

2G fo

 f   fo

 F  D

vG f  

dz 

dp   

Baroczy (1965) model – 

Graph (a)

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Graph (b)

Figure 6 Baroczy (1965) model

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(v) Two-phase flow in inclined pipes - Beggs and Brill (1973) model

4/1/079.0

 GD f   where ])1([  f   f   g  g  v x xv        

Figure 7 Beggs and Brill (1973) model for two-phase flow in inclined pipes

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Chapter 7 Heat transfer with phase change

Vapour bubbles  

( )

 

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Chapter 8 Core thermal-hydraulics analysis

1. One – dimensional analysis  

    ||

:

       ||  

Single phase:

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MEC6422 Nuclear Thermal Hydrauli cs and Heat Transfer DATA BOOK S. He (2012) 

Pressure

 ||  

Temperature (for power rating )

 

 

 

Two-phase:

Location of onset of boiling:

( ) 

Mixture properties:

 

 

 

Pressure drop:  

where  

 

 

[ ] ||  

||  

2. Sub-channel analysis

(1) Continuity equation

 

 

(2) Single phase energy equation:

  [ ]

 

(3) Axial momentum equation

( )

{} 

(4) Transverse momentum equation

() () () { }