Steady-state and transient analysis of two-phase natural circulation systems

Steady-state and transient analysis of two-phase natural circulation systems

Chapter 5 Steady-state and transient analysis of two-phase natural circulation systems 5.1 Introduction Two-phase natural circulation (NC) is relevan...

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Chapter 5

Steady-state and transient analysis of two-phase natural circulation systems 5.1 Introduction Two-phase natural circulation (NC) is relevant to a large number of industrial systems such as thermosyphon reboilers, thermosyphon evaporators, fossil-fueled power plants, and advanced nuclear reactors such as advanced heavy water reactor (AHWR) and economic simplified boiling water reactor (ESBWR). In addition, two-phase NC occurs in BWRs following pumping power failures. Two-phase NC is also relevant to PWRs following a small break loss of coolant accident (SBLOCA). In view of the above, analysis of two-phase NC assumes significance and this chapter deals with the steadystate and transient analysis of the same along with a parametric analysis.

5.2 Steady-state analysis of two-phase natural circulation systems There are several mathematical models available in the literature for the analysis of two-phase NC starting from the homogeneous equilibrium model. The homogeneous model is also known as the three-equation model as well as the EVET (equal velocity and equal temperature) model. The four- and five-equation drift flux model (DFM) is an advancement over the homogeneous model which can account for the differences in velocity and temperature of the two phases. Most codes used for analysis of the nuclear reactor systems today use the six-equation two-fluid model (TFM), which is also known as the UVUT (unequal velocity unequal temperature for the liquid and gas phase) model. Currently the multifield three-dimensional models are under development and are being used for reactor system analysis. As already stated in Chapter 3, only the homogeneous equilibrium model is considered here. This is required to remain within an acceptable range of complexity for the analysis of transient and stability problems associated with two-phase NC. The main purpose of the analysis is to derive analytical Single-phase, Two-phase and Supercritical Natural Circulation Systems. DOI: https://doi.org/10.1016/B978-0-08-102486-7.00005-6 © 2019 Elsevier Ltd. All rights reserved.

187

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Single-phase, Two-phase and Supercritical Natural Circulation Systems

equations for the steady-state flow rate and enthalpy distribution for the twophase natural circulation loop (NCL).

5.2.1

Development of flow equation

One of the problems with two-phase NC is that an explicit equation for flow rate like that for single-phase loops is not readily available, even with the homogeneous equilibrium model. For example, Ishii and Kataoka (1983) provide an explicit equation for the flow rate in single-phase NCL, whereas such an equation for two-phase NC is not provided although it describes scaling laws applicable for both single-phase and two-phase NCLs. Similarly, Todreas and Kazimi (1990) present an explicit equation for the steady-state flow rate in single-phase natural circulation system (NCS) but not for two-phase NCSs, although the methodology to estimate flow rate is presented. However, it is possible to find approximate dimensional equation for flow rate (Dimmick et al., 2002; Duffey, 2000). The development of an explicit equation for the flow rate is given separately for closed and open two-phase NCLs in this section.

5.2.1.1 Closed loops Fig. 5.1 shows a closed-loop rectangular two-phase NCS with a horizontal heat source and a horizontal heat sink. The theoretical treatment is limited to a 1-D approach where the only coordinate runs around the loop with the origin at the beginning of the heater. The heater is assumed to be supplied with a uniform heat flux (qh) and the heat removal from the heat sink is also by a constant heat flux (qc). The working fluid enters the heater at subcooled conditions and becomes saturated at some point. The length beyond this point is designated as the boiling length (LB) and before this point it is designated as single-phase length (Lsp) or nonboiling length. The two-phase steamwater mixture produced in the heater flows through the adiabatic riser and enters FIGURE 5.1 Two-phase NCS model.

(L tp)c (L sp)c Cooler S = Shl

S = Sc

H

LB

L sp

Heater qh S = Sh

S = 0, L t

Steady-state and transient analysis Chapter | 5

189

the heat sink where complete condensation of the two-phase mixture is assumed and the primary fluid may also get subcooled. Hence, a singlephase length (Lsp)c and a two-phase condensing region of length (Ltp)c also exists in the cooler. The governing conservation equations for such a system can be written as @ρ 1 @w 1 50 @t Ai @s

ð5:1Þ

The momentum equation for a segment of the loop can be rewritten in terms of the mass flow rate as   1 @w 1 @ w2 1 2 A @t A @s ρ !  "  # 2 2 @P f f φLO f φ2LO w 2 1 Ks 1 1 K tp 1 1 Ktp 2 ρgsin θ 52 @s D D D 2ρA2 ð5:2Þ where Ks ; φ2LO and Ktp are, respectively, the single-phase loss coefficient two-phase friction multiplier and the two-phase loss coefficient. Also, 2 φ LO and K tp are evaluated at the mean quality for the heated or cooled segments to account for the variation of quality. Alternatively, the approach 2 described in Chapter 3 can be used to evaluate φ LO : The above equation is a general representation of the momentum equation for a segment in the loop. For a single-phase pipe segment, the second term on the right-hand side (RHS) representing frictional pressure drop will have only the first term, whereas a heated pipe segment with subcooled inlet will have the first two terms and an adiabatic two-phase pipe segment will have only the last term among the three listed in square brackets. Note that in the case of singlephase incompressible fluids, the continuity equation was @w=@s 5 0; which means that the mass flow rate is a constant independent of the space coordinate, enabling us to use the integral momentum equation for both steadystate and transient analyses. In the case of two-phase loops, the transient mass flow rate can be different in different segments of the loop, which requires a momentum equation for each segment of the loop as shown above. The energy equation in terms of the enthalpy, i, can be written as 9 8 4qh > > > > heater for 0 , s # L h > > > > D > > > > = < @ðρiÞ 1 @ðwiÞ pipes for Lh , s # Lhl and Lc , s # Lt 1 5 0 > > @t Ai @s > > > > 4qc > > > > cooler for L 2 , s # L hl c > > ; : D ð5:3Þ

190

Single-phase, Two-phase and Supercritical Natural Circulation Systems

Note that the density ρ, the mass flow rate w, and the enthalpy i refer to the two-phase mixture such that      i 1 xifg for x $ 0 for x $ 0 1= vf 1 xvfg and i 5 f ρ5 iðP; ρÞ for x , 0 ρðP; iÞ for x , 0 ð5:4Þ Thus the dependent variables are ρ, w, i, and P. For evaluating these four unknowns we have the four equations given above. It may be noted that Eq. (5.4) is essentially an equation of the state for the two-phase mixture. Neglecting the transient terms, the steady-state equations can be written as @w 50 @s

ð5:5Þ

The above equation states that in the case of steady state, the mass flow rate is independent of the location in the loop, enabling us to switch to the integral momentum equation for the steady-state case. !   I f L w2 fLs fL 1 w2 2 fLB 2 tp hl 2 c dv 1 1 1 φ 1 1 K φ φ 1 K 1 K s tp tp LO LO LO A2 2ρ0 A2 D D D D I 2 gρ0 β h i@z 5 0 ð5:6aÞ where Ls, LB, Lhl, and (Ltp)c are, respectively, the lengths of the single-phase, boiling, two-phase hot leg, and two-phase cooler. The entire single-phase length starting from the single-phase region in the cooler, adiabatic cold leg, and single-phase region in the heater are accounted for by the length Ls. Note that the density in the buoyancy force term  was replaced by ρ 5 ρ0 1 2 β h ði 2 i0 Þ as shown in Chapter 3 to obtain the above equation. The above momentum equation is written for a uniform diameter loop. For a nonuniform diameter loop, the momentum equation becomes I I w2 Rw2 dv 1 ð5:6bÞ 2 gρ0 β h idz 5 0 2ρ0 A2i where the total hydraulic resistance of the loop is given by R5

Ns  X fLs

  NL h  Ks fLB K tp 2 X 1 φ 1 LO DA A2 i DA2 A2 i i5Ns i51   Ntp  Nhl  X fLhl Ktp K tp;c 2 X fLtp;c 1 φ2LO 1 1 φ 1 LO DA2 A2 i DA2 A2 i i5NL i5Nhl 1 2

h

ð5:7aÞ

Steady-state and transient analysis Chapter | 5

191

Replacing the local losses with an equivalent length such that Leff 5 Li 1 Leq as in single-phase NC, we can write the above equation as  !   ! NL h Ns X f Leff s 2 X f Leff B R5 1 φLO DA2 DA2 i5Ns i51 i i   !   ! Ntp Nhl X X f Leff tp;c f L eff hl 2 2 1 φLO 1 φLO ð5:7bÞ 2 DA DA2 i5NL i5Nhl i

h

i

If the local losses are negligible, then R5

 Ns  X fLs i51

DA2

 NL h  fLB 2 X 1 φLO DA2 i i i5Ns

1 φ2LO

  Ntp  Nhl  X fLhl 2 X fLtp;c 1 φLO DA2 i DA2 i i5NL i5Nhl h

ð5:7cÞ The steady-state energy equation is 9 8 4qh > > > > heater for 0 , s # L h > > > > D > > > > = < w di pipes for Lh , s # Lhl and Lc , s # Lt ð5:8Þ 5 0 > A ds > > > > > 4q c > > > > cooler for Lhl , s # Lc > > ; :2 D H For a closed loop, dv 5 0, hence the momentum equation neglecting the local loss coefficient becomes I Rw2 ð5:9Þ 2 gρ0 β h idz 5 0 2ρ0 The extent of single-phase heated length, Lsp, boiling length, LB, the twophase cooler length, (Ltp)c, and single-phase cooler length, (Lsp)c, would be known only after solving the energy equation. From the energy equation for the heater, we get i 5 icl 1

4qh Ah s wD

ð5:10Þ

The single-phase length in the heater is calculated by setting the LHS to the saturation enthalpy and rearranging   wD Lsp 5 if 2 icl 4qh Ah

ð5:11Þ

The boiling length is calculated by subtracting the single-phase length from the heater length (i.e., LB 5 LhLsp). The enthalpy at the heater outlet is obtained by setting s 5 shl in the above equation. The heater outlet

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Single-phase, Two-phase and Supercritical Natural Circulation Systems

enthalpy is the same as the enthalpy of the adiabatic hot leg, since heat losses are neglected. Hence, ihl 5 icl 1

4qh Ah Lh wD

ð5:12Þ

For the cooler, a similar equation is obtained as i 5 ihl 2

4qc Ac ðs 2 shl Þ wD

ð5:13Þ

The two-phase length in the cooler is obtained by setting the LHS equal to the saturation enthalpy and rearranging.     ihl 2 if wD Ltp c 5 ð5:14Þ 4qc Ac The single-phase length in the cooler is obtained by subtracting the twophase length [i.e., (Lsp)c 5 Lc(Ltp)c]. The enthalpy at the cooler outlet is obtained as icl 5 ihl 2

4qc Ac Lc wD

ð5:15Þ

H Using this, the integral in the momentum equation can be obtained as idz 5 H ðihl 2 icl Þ for the loop shown in Fig. 5.1. Since ihl 2 icl 5 Qh =w; (where w is the steady-state flow rate), the momentum equation (5.9) can be rearranged as

2ρ20 gβ h Qh H w5 R

13 ð5:16Þ

Similarly, the steady-state enthalpy rise (Δih) over the heater is given by Δih 5 Qh =w. Hence " #13 RQ2h Δih 5 ð5:17Þ 2ρ20 gβ h H where R is the total hydraulic resistance of the loop obtained from Eq. (5.7). 1=3 Thus the steady-state mass flow rate is found to be proportional to Qh as in single-phase flow. Similarly, the enthalpy rise over the heater is found to be 2=3 proportional to Qh .

5.2.1.2 Open loops As already mentioned in Chapter 2, two types of open loops are of interest to us. The first is a physically closed loop with a heat source (boiler) and the other is literally an open loop with a boiler. Fig. 5.2A illustrates an open loop of the former type, whereas Fig. 5.2B illustrates an open loop of the

Steady-state and transient analysis Chapter | 5

193

Steam ws, hs

Baffle

Riser

H

LB Exit orifice

s=Lh

Lsp

Heater

Downcomer

Steam drum Feed

W z=H

S=Lh

qh

h

Lsp Li

z=0 s=0

Inlet orifice Lo

(A)

LB

S=0

(B)

FIGURE 5.2 Different open-loop two-phase natural circulation systems. (A) Physically closed loop; (B) physically open loop.

latter type. Analytically, for the physically closed loop of the type shown in H Fig. 5.2A, dP 5 0: In contrast, in a physically open loop (Fig. 5.2B), H dP 6¼ 0: Hence, while analyzing a physically closed loop, we can use the integral momentum Eq. (5.6b). The energy equation can be written as 8 9 4qh < = heater for 0 , s # L w di h D 5 ð5:18Þ ; A ds : 0 pipes for Lh , s # Lt The enthalpy distribution in the heater is given by integrating the above equation i 5 iin 1

4qh A s Dw

ð5:19Þ

where iin is the enthalpy at the heater inlet. The single-phase length in the heater is obtained as   Dw Lsp 5 if 2 iin 4qh A

ð5:20Þ

The enthalpy at the heater outlet is obtained as ie 5 iin 1

4qh A Lh Dw

ð5:21Þ

The steam drum (SD) in Fig. 5.2A is considered in two parts, with the baffle separating the two parts. To the left of the baffle, two-phase fluid exists, while only single-phase fluid exists on the right of the baffle. Assuming 100% steamwater separation in the two-phase part of the steam drum, the inlet enthalpy is obtained by a heat balance on the right side of the baffle.

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Single-phase, Two-phase and Supercritical Natural Circulation Systems

iin 5

wð1 2 xe Þif 1 wF iF w

ð5:22Þ

where xe, if, wF, and iF are the heater exit quality, saturated liquid enthalpy, feed mass flow rate, and feed enthalpy, respectively. At steady state, the steam flow rate equals the feed water flow rate. Hence,   iin 5 if 2 xe if 2 iF ð5:23Þ With this, the integral in the momentum equation can be evaluated as I 4qh AHLh Qh H ð5:24Þ 5 idz 5 H ðie 2 iin Þ 5 w Dw H The integral on the LHS of the momentum equation can be evaluated as dv 5 ve 2 vin where ve and vin are the specific volumes at the exit and the inlet of the open loop, respectively. Using this and Eq. (5.24) in the momentum equation (5.6b), the steady-state flow rate can be obtained as " #13 gρ0 β h Qh H w 5 ðve 2vin Þ ð5:25Þ 1 2ρR A2 0

Note that the total hydraulic resistance R for the loop in Fig. 5.2A is given by the expression  !   !   ! NLh Ns Nhl X X f Leff s f Leff hl 2 X f Leff B R5 1 φLO 1 φ2LO ð5:26Þ 2 2 2 DA DA DA i5Ns i5NL i51 i

i

h

i

If the acceleration pressure drop is negligible, then Eq. (5.25) becomes the same Has that of Eq. (5.16). For open loops of the type shown in Fig. 5.2B, dP 6¼ 0; and the integral momentum equation can be written as ð ðH w 2 Lt Rw2 dv 1 1 P 2 P 2 g ρdz 5 0 ð5:27Þ o i A2 s50 2ρ0 z50  Noting that Pi 5 Po 1 ρin gH and ρ 5 ρ0 1 2 β h ði 2 ir Þ with ir 5 iin and ρ0 5 ρin leads to the same steady-state flow rate equation obtained above (i.e., Eq. 5.25).

5.2.2

Dimensionless flow equation

The steady-state momentum (Eq. 5.6b) and energy (Eq. 5.8) are nondimensionalized by the following substitutions 

v 5

v w i 2 ir z s Ai Di Li ; ω5 ; I5 ; Z 5 ; S 5 ; ai 5 ; di 5 ; li 5 vr wss H H Δih Ar Dr Lt ð5:28aÞ

Steady-state and transient analysis Chapter | 5

195

where

  N N   Leff i 1X Vt 1X Ar 5 Ai Li 5 ; Dr 5 Di Li and leff i 5 Lt i51 Lt i51 Lt Lt

ð5:28bÞ

where wss and Δih , respectively, are the steady-state mass flow rate and the enthalpy rise across the heater and vr and ir are the reference values of specific volume and enthalpy, respectively. With these substitutions, the dimensionless equations become I I I w2ss vr pμb w22b  ss NG dv dZ 2 gρ IdZ 5 0 1 2 gρ β Hi β HΔi r h 0 h 0 h 2Dbr A22b a2i A2r r ρ0 8 Vt > > > > > Vh Vt dI < 5 0 HAi dS > > Vt > > > : 2 Vc

ð5:29Þ

9 > heater > > > > = pipes > > > cooler > > ;

ð5:30Þ

Note that the friction factor has been substituted with f 5 p/Reb in the momentum equation. Also, at steady state, ω 5 1 (by definition). Further simplifications of the momentum equation can be done depending on the type of the loop considered.

5.2.2.1 Closed loop H  H For the closed loop dv 5 0 and dZ 5 0. Hence the dimensionless momentum equation becomes I pμb w22b ss NG IdZ 5 0 ð5:31Þ 2 gρ β HΔi h 0 h 2Dbr A22b r ρ0 Noting that Δih 5 Qh =wss ; Eq. (5.31) can be rearranged as  1 2 Grm II 32b Ress 5 p NG H where II 5 IdZ and NG is given by (   !   ! NL h Ns leff s leff B Lt X 2 X NG 5 1 φLO 11b 22b 11b Dr i51 d a d a22b i5Ns i i 0n   o 1 ) !   Ntp Nhl leff tp X leff hl 2 X cA @ 1 φ2LO 1 φ LO 11b a22b 11b a22b d d i5NL i5Nhl h

i

i

ð5:32Þ

ð5:33aÞ

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Single-phase, Two-phase and Supercritical Natural Circulation Systems

If local loss coefficients are negligible, then it becomes (   NLh  Ns  Lt X ls lB 2 X NG 5 1 φ LO Dr i51 d11b a22b i d 11b a22b i i5Ns   !)  Ntp Nhl  X ltp c lhl 2 X 2 1 φLO 1 φLO 11b 22b 11b d a d a22b i i5NL i5Nhl

ð5:33bÞ

i

h

If the loop is also a uniform diameter loop, then it becomes NG 5

o Lt n 2 2   ls 1 φLO lB 1 φ2LO lhl 1 φLO ltp c D

ð5:33cÞ

If local losses are accounted for the uniform diameter loop, then NG becomes NG 5

n  o i    Lt h  2  2 leff sp 1 φLO leff B 1 φ2LO leff hl 1 φLO leff tp c D

ð5:33dÞ

For the purpose of evaluation of II, the dimensionless energy equation can be rewritten as 8 H > > heater ð0 , S # Sh Þ > > Lh > < dI ð5:34Þ 5 0 pipes ðSh , S # Shl and Sc , S # St Þ dS > > H > > cooler Shl , S # Sc > : 2 Lc Integrating Eq. (5.34) with appropriate boundary conditions we obtain the following equations for the distribution of enthalpy in the various segments of the loop I 5 Icl 1

H S Lh

for the heated section between 0 , S # Sh

ð5:35Þ

The dimensionless length of the single-phase heated section, Ssp, can be obtained as If 5 Icl 1

H Ssp Lh

or

  Lh Ssp 5 If 2 Icl H

ð5:36Þ

The boiling length, SB, is then calculated as SB 5 ShSsp. The heater exit enthalpy is also the enthalpy in the two-phase adiabatic portion (hot leg in Fig. 5.1) and is obtained by setting S 5 Sh in Eq. (5.35), which on simplifying yields Ihl 5 Icl 1 1

for

Sh , S # Shl

ð5:37Þ

Steady-state and transient analysis Chapter | 5

197

In a similar way, the enthalpy distribution in the cooler can be obtained as I 5 Ihl 1

H ðShl 2 SÞ Lc

ð5:38Þ

The dimensionless two-phase length in the cooler can be obtained by setting LHS 5 If in the above equation and rearranging as   Lc Stp 5 Shl 2 If 2 Ihl H

ð5:39Þ

The dimensionless single-phase length in the cooler is obtained as Ssp 5 Sc 2 Stp . The enthalpy at the cooler exit is obtained by setting S 5 Sc in Eq. (5.38) which on simplifying yields Icl 5 Ihl 2 1 With the above enthalpy distribution it follows becomes  1 2 Grm 32b Ress 5 p NG

H

ð5:40Þ IdZ 5 1 and Eq. (5.32)

ð5:41Þ

Also, the above equation can be rearranged to get the following explicit equation for the mass flow rate. 1 " #32b 2 g ρ2f β h II H Qh Dbr A22b r Wss 5 ð5:42Þ p μbf NG This equation is valid for all orientations of the source and sink for a closed loop. However, H shall be replaced with the center line elevation difference and II for the particular orientation needs to be evaluated as shown above for the case with the source and sink horizontal. Eq. (5.41) can be rewritten as   Grm r Ress 5 C ð5:43Þ NG where C5

 r 2 1 and r 5 p 32b

ð5:44Þ

As already mentioned, the above equation is valid for a loop with horizontal heater and horizontal cooler. For other source and sink orientations, the actual integral shall be evaluated. In general, no serious error is expected by using the center line elevation difference if the heater is supplied with a uniform heat flux. For laminar flow with p 5 64 and b 5 1, the values of the constants C 5 0.1768 and r 5 0.5, so that Eq. (5.41) becomes

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Single-phase, Two-phase and Supercritical Natural Circulation Systems



Grm Ress 5 0:1768 NG

0:5 ð5:45Þ

For a transition regime, C 5 1.2161 and r 5 1/2.584 so that   Grm 0:387 Ress 5 1:2161 NG

ð5:46Þ

Similarly, for turbulent flow with p 5 0.316 and b 5 0.25, the corresponding values are C 5 1.96 and b 5 1/2.75.   Grm 0:364 Ress 5 1:96 ð5:47Þ NG

5.2.2.2 Open loop H  H For the open loop shown in Fig. 5.2A, dv 6¼ 0 and dZ 5 0. Hence the momentum equation becomes I I w2ss vr pμb w22b  ss NG 1 2 gρ β HΔi dv IdZ 5 0 ð5:48Þ h 0 h 2Dbr A22b a2i A2r r ρ0 Noting that Δih 5 Qh =wss ; the above equation can be rearranged to obtain     p 3 ve 2 vin Ress NG 5 Grm II ð5:49Þ 1 Re32b 2 2 ss ai H where II 5 IdZ and the geometric number NG is given by 8   !   !   !9 NLh Ns Nhl = X leff s leff B leff hl Lt
where



leff

 s

5

n

i

h

i

ð5:50Þ

leff

 sp

  o 1 leff DC =Lt : Just as in closed loops, one can

easily obtain the relationships for an open loop with negligible local loss coefficients and for uniform diameter. Note that evaluation of NG requires the knowledge of the two-phase friction multiplier also. Thus the flow rate can be obtained numerically by solving the above polynomial equation. In the case of laminar flow b 5 1, then the above equation becomes a cubical equation. Neglecting the first term (i.e., the acceleration term), it reduces to Eq. (5.32). For the open loop shown in Fig. 5.2B also, the above equation (i.e., Eq. 5.49) holds good. For evaluating II for the open loop shown in Fig. 5.2, the energy equation can be written as

199

Steady-state and transient analysis Chapter | 5

8 H dI < 5 Lh dS : 0

heater ð0 , S # Sh Þ

ð5:51Þ

pipes ðSh , S # SSD and SSD , S # St Þ

The enthalpy distribution in the heater can be obtained by integrating the above equation I 5 Iin 1

H S Lh

ð5:52Þ

The dimensionless single-phase heated length Ssp can be estimated as   Lh Ssp 5 If 2 Iin H

ð5:53Þ

Again the dimensionless boiling length is obtained as SB 5 Sh 2 Ssp . The heater exit enthalpy is obtained as Ihl 5 Iin 1

H Lh Sh : Since Sh 5 ; Ihl 5 Iin 1 1 Lh H

The above equation is valid for Sh , S # SSD. Using this, the and the dimensionless momentum equation (5.49) becomes     p 3 ve 2 vin Ress NG 5 Grm 1 Re32b 2 ss a2i

ð5:54Þ H

IdZ 5 1 ð5:55Þ

Note that the dimensionless enthalpy Iin needs to be obtained. For this, the steam drum, wherein complete separation of the steamwater mixture is assumed to take place (without any carryover or carryunder) can be approximated to two volumes on either side of the baffle (see Fig. 5.2A). On the left side of the baffle is a two-phase volume where the separated steam goes out of the steam drum. The separated water at the saturated condition goes to the single-phase volume on the right side of the baffle. On the right side of the baffle, some amount of inlet subcooling is obtained due to the mixing of saturated water with the subcooled feed water flow rate wF entering at iF . By a heat balance, the enthalpy at the downcomer inlet can be calculated as   for SSD , S # St ð5:56Þ Iin 5 If 2 xe If 2 IF where xe is the exit quality. Since ir 5 iF ; the above equation can be rewritten as Iin 5 If ð1 2 xe Þ

ð5:57Þ

The dimensionless Reynolds number and modified Grashof number appearing in the equations for the open and closed loops can be defined as

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Single-phase, Two-phase and Supercritical Natural Circulation Systems

Ress 5

D3r ρ2f β h gQh H Dr wss ; Grm 5 Ar μf Ar μ3f

ð5:58Þ

2

5.2.2.3 Evaluation of φLO and φ2LO We had used the two-phase friction multiplier for the heated and adiabatic sections without actually providing an expression for their estimation. Since 2 quality variation is linear for the uniformly heated test section, φLO can be evaluated at half the value of the exit quality. From the basic definition of φ2LO and McAdams et al.’s (1942) model for two-phase viscosity, we can 2 obtain the following equations for φ2LO and φLO . 2 3b 2 3b ρ ρ 1 1 2 f f 4

5 and φLO 5

5 ð5:59Þ φ2LO 5 4 ρe 11xe μf 21 ρm 11 xe μf 21 μg

2

μg

where ρe 5

ρg ρf xe ðρf 2 ρg Þ 1 ρg

and ρm 5



ρg ρf

0:5xe ρf 2 ρg 1 ρg

ð5:60Þ

It may be recognized that there are several other two-phase friction multiplier models in the literature and one could choose any one of these. In that 2 case, appropriate relations for the φ2LO and φ LO need to be derived.

5.2.2.4 Evaluation of β h While deriving the dimensionless equation for the flow rate, it was assumed that β h is a constant. It was shown in Chapter 4 that approximating β h to a constant value for small ranges of quality introduces similar errors as that of approximating β T to a constant value for small temperature ranges in singlephase flows. In fact, it is a constant only above a critical quality, which depends on the system pressure. The average value of β h is calculated from the following equation. βh 5

    1 @v 1 Δv 1 ve 2 vin ρ 2 ρe Δρ  in  5 5 5 5 v @i p vm Δih 0:5ðvin 1 ve Þ ie 2 iin ρm Δih 0:5 ρe 1 ρin Δih

ð5:61Þ

5.2.2.5 Special cases Single-phase NCSs: For single-phase NC xe 5 0 and by definition φ2LO 5 1. Using these in Eq. (5.33b), we get

Steady-state and transient analysis Chapter | 5

NG 5

 Nt  Lt X leff Dr i51 d11b a22b i

201

ð5:62Þ

which is the same as that given for single-phase loops in Chapter 4. Similarly, noting that i 5 CpT if Cp is a constant, we get     1 @v 1 @v 5 : βh 5 v @i p vCp @T p ð5:63Þ   1 @v βT : Noting that β T 5 we obtain β h 5 v @T p Cp Note that if we use the above relationship between β h and β T, then the steady-state flow rate equations (both dimensional and dimensionless) become the same as that for single-phase flow as shown in Table 5.1.

5.2.2.6 Two-phase loops relevant to pressurized water reactors In this case, since the heat source and heat sink are present, the equations given above for closed loops can be used. 5.2.3

Validation of the dimensionless flow equation

As already mentioned, explicit flow rate equations for two-phase NCLs are not readily available in the literature. Hence, it was decided to compare the predictions of flow rate equations developed here with various computer codes used for thermal hydraulic system analysis. The system codes TINFLO-S (Nayak et al., 1998) and RELAP5/MOD3.2 (The RELAP5 Development Team, 1995) were selected for this. TINFLO-S code is developed specifically for thermal hydraulic analysis of NCSs and is based on the homogeneous equilibrium model. It may be noted that there are two issues with the dimensionless flow equation (i.e., Eq. 5.43) presented here. The first is that it is directly applicable to closed loops and in case of open loops it is applicable only if the acceleration term is negligible. The second issue is that it is valid only for the homogeneous two-phase flow model. Hence, it was decided to test the impact of these two issues on the predicted dimensionless flow rate. To facilitate this, the loop geometry shown in Fig. 5.3A and B were selected. The advantage of this loop geometry was that experimental two-phase NC data at different pressures were available. Fig. 5.4 shows a comparison of the predicted dimensionless flow rates with that predicted by TINFLO-S and RELAP5/MOD3.2 codes using the homogeneous model. The predictions were made for the turbulent flow case (i.e., b 5 0.25). The figure shows that the predicted flow rates with the homogeneous model in RELAP5 code underpredicts the flow rate by about 15%, which is attributed to the neglect of the acceleration term. Thus the use

TABLE 5.1 Comparison of single-phase and two-phase natural circulation equations. Parameter Mass flow rate, w

Hydraulic resistance, R

Ress NG

Single-phase NCS

Two-phase NCS

2 1 2ρr β T gQh H 3 RCp   Nt P fL K 1 2 2 A i i51 DA

2 1 2ρr β h gQh H 3 R

  Gr m r C NG   N t leff Lt P Dr 11b a22b i51 d i

  Gr m r C NG o 19 8 0n      NLh 


Dr3 ρ2f β T gQh H Ar μ3 Cp

Dr3 ρ2f β h gQh H Ar μ3

Ns P i51



fLs Ks 1 DA2 A2

 i

1 φ2LO

P

NLh NS



K tp fLB 1 DA2 A2

 i

1 φ2LO

Nh l

P

NLh



Ktp fLhl 1 DA2 A2

h

Gr m

 i

1 φ2LO

!   Ntp f Ltp c K tp P 1 DA2 A2 Nh l

i

i

Steady-state and transient analysis Chapter | 5

Coolant

Coolant

Condenser

Condenser

SD

2036

Steam drum 885

2210

1515

Preheater

2445 575

203

850

Heater

1180

Heater 1180

655

2020

3400

(A)

(B)

Ress

FIGURE 5.3 Schematic of the different loops considered: (A) 7, 9.1, 15.74, and 19.86 mm diameter loops; (B) 49.3 mm diameter loop.

10

6

10

5

10

4

1/2.75

Ress = 1.96 (Grm /NG )

10

TINFLO-S prediction RELAP5/MOD3.2 homogeneous model

3

10

8

10

9

10

10

10

11

10

12

10

13

10

14

Grm /NG FIGURE 5.4 Comparison of flow rate predictions.

of Eq. (5.43) for open loops could result in an error of B15%. Therefore one should use Eq. (5.55) for open loops for better accuracy. TINFLO-S code predictions are in reasonable agreement with the dimensionless flow equation.

5.2.4

Comparison of the homogeneous and the two-fluid models

A comparison of the predictions of the two-fluid and the homogeneous models using the RELAP5/MoD3.2 code was made by Gartia et al. (2006).

204

Single-phase, Two-phase and Supercritical Natural Circulation Systems

10

6

Ress

1/2" FPTIL-RELAP5 (two fluid) 3/4" FPTIL-RELAP5 (two fluid) 1" FPTIL-RELAP5 (two fluid) 1/2" FPTIL-RELAP5 (homogeneous) 3/4" FPTIL-RELAP5 (homogeneous) 1" FPTIL-RELAP5 (homogeneous)

10

5

4

10 12 10

10

13

10

14

Grm /NG FIGURE 5.5 Two-fluid and homogeneous model predictions.

The predictions were made for the two-phase NCL schematically represented by Fig. 5.3A with an inside diameter of 9.1, 15.74, and 19.86 and the results are shown in Fig. 5.5. The predictions show that the error introduced by the use of the homogeneous model is only marginal when compared to the twofluid model for the steady-state two-phase NC. This is attributed to the fact that there is practically no thermal nonequilibrium at the low flow rates typical of two-phase NC and the velocity difference between the vapor and liquid is not significant enough to cause a large difference in prediction. However, for the 9.1 mm loop, the difference is perceptible due to the larger difference in velocities existing in smaller diameter loops. It may be noted further that the homogeneous model is found to reasonably predict other two-phase NC phenomena like stability (Furutera, 1986; Lee and Lee, 1991; Wang et al., 1994a,b; Nayak et al., 1998; Van Bragt and Van Der Hagen, 1998). Thus there are indications that the use of the homogeneous model for the two-phase NC phenomena may not result in serious error. However, this may not hold true for extreme transients like LOCA with cold water injection where the nonequilibrium effects are dominant. Fig. 5.6 shows a comparison of the predicted dimensionless flow rate with data from uniform diameter and nonuniform diameter loops. While plot  ting the data β h 5 ρin 2 ρe =ðρm Δiss Þ was used. In addition, the McAdams et al. (1942) model was used to evaluate the two-phase friction factor. The steady-state data used included four uniform diameter loops from Dubey et al. (2004) and Naveen et al. (2000) and two nonuniform diameter loops

Ress

Steady-state and transient analysis Chapter | 5

10

6

10

5

10

4

FIGURE 5.6 Comparison with test data.

0%

0%

+4

10

205

–4

3

Ress = 1.96(Grm /NG )

0.364

UDL data NDL data

10

2

10

7

10

9

10

11

10

13

10

15

Grm / NG (Mendler et al., 1961) and the integral test loop (Rao et al., 2002). The data fall in the following parameter range: Loop diameter: 9.199.2 mm; quality: 0.4%24%, Circulation length: 8.796.6 m; inlet subcooling: 0.129 K, SD level: 90% 6 5%; pressure: 0.113.8 MPa, and power: 0.3300 kW. The measured dimensionless flow rate as a function of Grm/NG is plotted in Fig. 5.6 for various loops. Two lines representing 1 40% and 240% deviations from the dimensionless flow equation are also shown in the figure. As can be seen, the agreement between the data and the dimensionless flow equation is within 6 40% which is reasonable.

5.3 Parametric effects on two-phase natural circulation systems One of the drawbacks of a dimensionless equation is that it often masks the parametric trends. In fact the steady-state performance of two-phase loops is significantly influenced by the operating conditions (i.e., pressure, power and inlet subcooling), geometric conditions (loop diameter and elevation difference) and the model used to calculate the two-phase friction multiplier. The influences of orificing and acceleration term are also important for twophase NCSs. The above-mentioned influences can be studied with the help of the simple steady-state flow rate Eq. (5.25) given above with the resistance evaluated by Eq. (5.26) for open loops and that given in Table 5.1 for closed loops. The thermal expansion coefficient was evaluated using Eq. (5.61) 2 with φ2LO and φ LO evaluated by Eq. (5.59). The calculation of steady-state flow rate is iterative. The calculations start with an assumed flow rate. With the assumed flow rate, calculate the single-phase heated length (Ls), boiling

206

Single-phase, Two-phase and Supercritical Natural Circulation Systems

length (LB), exit quality, and enthalpy distribution using the steady-state solution of the energy equation. Subsequently calculate the enthalpy integral appearing in the momentum equation. Knowing the exit quality, the density 2 and φ2LO and φ LO are estimated. Subsequently, the total hydraulic resistance is estimated and then the flow rate using Eq. (5.25). If the estimated flow rate is different from the assumed flow rate, the calculations are repeated until a specified convergence criterion is satisfied.

5.3.1

Two-phase natural circulation flow regimes

An interesting aspect of two-phase NC behavior is illustrated by Fig. 5.7. It shows that the two-phase NC flow rate can increase (Fig. 5.7A), decrease (Fig. 5.7B), or remain practically invariant with power (Fig. 5.7C). Based on the nature of the variation of the steady-state flow with power, three different NC flow regimes can be observed for two-phase loops. These flow regimes are designated as gravity-dominant (or buoyancy-dominant), frictiondominant, and the compensating regimes. It may be noted that the gravitydominant and friction-dominant flow regimes in two-phase NCLs were reported first by Fukuda and Kobori (1979). In a NCL, the gravitational pressure drop (being the driving pressure differential) is always the largest component of pressure drop and all other pressure drops (friction, acceleration, and local) must balance the gravity (or buoyancy) pressure differential at steady state. However, the NC flow regimes are differentiated based on the change of the pressure drop components with quality (or power).

5.3.1.1 Gravity-dominant regime The gravity-dominant regime is usually observed at low qualities. In this regime, for a small change in quality there is a large change in the void fraction (see Fig. 5.8) and hence the density and buoyancy force. The increased buoyancy driving force is to be balanced by a corresponding increase in the retarding frictional force that is possible only at a higher flow rate. As a result, the gravity-dominant regime is characterized by an increase in the flow rate with power (compare the gravity-dominant regime in Fig. 5.9 with Fig. 5.7A). 5.3.1.2 Friction-dominant regime The friction-dominant regime is observed at low to moderate pressures when quality is high. At higher qualities and moderate pressures, the increase in void fraction with quality is marginal (see the curve for pressures in the range 115 bar in Fig. 5.8) leading to an almost constant or marginal increase in buoyancy force. However, the continued conversion of highdensity water to low-density steam at high qualities (due to the increase in power) requires that the mixture volumetric flow rate and hence the mixture

Steady-state and transient analysis Chapter | 5

FIGURE 5.7 Effect of power on the two-phase NC flow rate. (A) Flow increases with power; (B) flow decreases with power; (C) flow nearly constant with power.

(A)

Mass flow rate (kg/s)

2.1

49.3 mm i.d. loop Pressure: 9.6 bar Subcooling: 1 K

1.8

1.5 Equation (5.25) Experimental data RELAP5/MOD3.2 TINFLO-S

1.2

10

20

30

40

Power (kW) (B)

Mass flow rate (kg/s)

0.03

0.02

Experimental data TINFLO-S Equation (5.25)

0.01 9.1 mm diameter tube 12.6–14.6 bar (abs) 0.00

1500

2000

2500

3000

3500

4000

Power (W)

(C)

Mass flow rate (kg/s)

0.04

0.03

9.1 mm i.d. loop Δ Tsub : 8–16K

0.02

Pressure: 57 + 1 bar 0.01

0.00 2000

Experiment RELAP5/Mod 3.2 TINFLO-S Equation (5.25) 3000

207

4000

Power (W)

5000

208

Single-phase, Two-phase and Supercritical Natural Circulation Systems

1 b ar

ba

r

1.0

70

b ar

ba 0

0.6

17

Void fraction

r

15

0.8

22

0

r ba

1 22

.2

ba

r

0.4

0.2

0.0 0.0

0.2

0.4

0.6

0.8

1.0

Quality FIGURE 5.8 Effect of quality on void fraction.

FIGURE 5.9 Effect of pressure on flow regime.

Flow normalized to 100% FP

6 GDR

Friction dominant region

5 15 bar

Predicted by Eq. (5.26) Loop diameter = 9.1 mm

4 3 2

Compensating regime 70 bar

1

170 bar

0

0

20

40

GDR

60

80

100

Power (%) velocity must increase, resulting in an increase in the frictional force and hence a decrease in the flow rate. Thus the friction-dominant regime is characterized by a decrease in flow rate with an increase in power (compare the curve for the FDR for 15 bar given in Figs. 5.7B and 5.9).

5.3.1.3 Compensating regime Between the gravity-dominant and friction-dominant regimes, there exists a compensating regime, where the flow rate remains practically unaffected by

2.0 GDR

1.6

Flow normalized to 100% power

Flow normalized to 100% power

Steady-state and transient analysis Chapter | 5

Friction dominant region 15 bar

Compensating regime

1.2 a 50 b

r

0.8 17

GDR Predicted by Eq. (5.26) Loop diameter: 19.86 mm GDR: Gravity dominant regime

0.4

0.0

r 0 ba

0

20

40

60

80

100

Power (%) (A)

209

2.0 1.6

GDR ar 2b

1.2

Compensating regime

r 8 ba

0.8

bar 170

0.4 0.0

Friction dominant regime

0

20

GDR

Predicted by Eq. (5.26) Loop diameter = 49.3 mm GDR: Gravity dominant regime

40

60

80

100

Power (%) (B)

FIGURE 5.10 Effect of pressure on flow regime for different loop diameters.

an increase in power. In this regime, the increase in buoyancy force is compensated by a corresponding increase in the frictional force, leaving the flow rate practically unaffected (compare Fig. 5.7C and the curve for 7 MPa in Fig. 5.9) in spite of an increase in quality.

5.3.1.4 Effect of pressure and loop diameter on the flow regimes The NC flow regimes depend strongly on the system pressure (see Figs. 5.9 and 5.10). In fact, at high pressures only the gravity-dominant regime (as in single-phase NC) may be observed if the power is low. The frictiondominant regime shifts to low pressures with an increase in loop diameter (see Fig. 5.10B). Knowledge of the flow regimes is important to understand the stability behavior of two-phase loops. 5.3.2

Effect of operating conditions

The operating conditions for two-phase NCLs depend on the type of loop considered. For example, in the case of open loops of the type shown in Fig. 5.2B, the operating conditions include power, pressure, inlet subcooling, and level. In the case of open loops of the type shown in Fig. 5.2A and closed loops (Fig. 5.1), the inlet subcooling is a dependent parameter. Therefore the operating parameters for such open loops include the feed water flow rate and its enthalpy (or temperature), whereas for the closed loops the heat sink conditions (pressure if it is a steam generator, coolant flow rate, and its inlet temperature) also become additional operating conditions.

5.3.2.1 Effect of power The effect of power on the two-phase NC flow rate is shown in Fig. 5.11A and B. The results given in Fig. 5.11A were generated for the open loop

210

Single-phase, Two-phase and Supercritical Natural Circulation Systems 0.15

30 bar 70 bar 100 bar

Flow rate Exit quality

0.6

Mass flow rate (kg/s)

Flow rate (kg/s), Exit quality (fraction)

0.8

0.4

0.2

0.0 0.0

6.0x10

4

1.2x10

5

1.8x10

Power (W)

(A)

5

2.4x10

5

3.0x10

5

0.10

0.05 o

ID = 14 mm, 15 C subcooling 0.00

0

10

20

30

40

50

60

70

Power (kW) (B)

FIGURE 5.11 Effect of power on flow rate and exit quality. (A) Flow rate and exit quality variation; (B) effect of pressure on flow rate.

shown in Fig. 5.3A, whereas the results given in Fig. 5.11B were generated for a uniform diameter closed loop of the type shown in Fig. 5.1. As expected, the flow rate increases with power in the buoyancy-dominant regime and it decreases with power in the friction-dominant regime. The exit quality is found to increase monotonously with power.

5.3.2.2 Effect of pressure It may be noted from Fig. 5.11B that the pressure has contrasting effects in the buoyancy-dominant and friction-dominant regimes. In the buoyancydominant regime increasing the pressure tends to decrease the flow rate while in the friction-dominant regime increasing the pressure tends to increase the flow rate. In the buoyancy-dominant region, increasing pressure tends to decrease the void fraction and hence the buoyancy force, leading to a decrease in the flow rate. In the friction-dominant regime, increasing the pressure decreases the void fraction increasing the two-phase density thereby decreasing the friction pressure drop leading to an increase in the flow rate. The results given in Fig. 5.12A were generated for the open loop shown in Fig. 5.3A with 19.9 mm loop diameter. The results given are similar to what is given in Fig. 5.11B for the closed loop. The effect of pressure on two-phase NC flow was studied experimentally and theoretically in the 49.3 mm inside diameter loop (see Fig. 5.3B) for a constant power and the results are shown in Fig. 5.12A. The trend of the data is in agreement with the predictions of Eq. (5.25). Initially increasing the pressure increases the two-phase NC flow rate. But at high pressures there is a significant decrease in the void fraction and hence the buoyancy force, leading to a decreasing flow rate with increasing pressure.

Steady-state and transient analysis Chapter | 5 2.0

Mass flow rate (kg/s)

0.45

Flow rate (kg/s)

0.36

0.27 50 bar 100 bar 150 bar

0.18

0.09

0.00 0.0

211

1.2 0.8

4

1.2x10

5

1.8x10

5

2.4x10

5

3.0x10

Eq. (5.31) Experimental data

0.4 0.0

6.0x10

Power: 30 kW

1.6

5

Power (W)

(A)

0

20

40

60

80

Pressure (bar)

(B)

FIGURE 5.12 Effect of pressure on two-phase natural circulation flow rate. (A) Flow rate versus power at different pressures; (B) effect of pressure at constant power.

5.3.2.3 Effect of feed water enthalpy Inlet subcooling in closed-loop two-phase NCSs is not an independent operating parameter. The independent parameter which can be controlled by the operator is the feed water enthalpy which will influence the inlet subcooling. The effect of feed water enthalpy on exit quality and flow rate for two-phase NCSs is shown in Fig. 5.13. These results were generated for the 19.86 mm inside diameter loop with the length scales shown in Fig. 5.3A. Increasing the feed water enthalpy increases the exit quality consistently. However, the effect of feed water enthalpy is found to be different at low and high powers. Increasing the feed water enthalpy in the buoyancy-dominant region (Fig. 5.13C) increases the flow rate, while in the friction-dominant region the flow rate decreases with an increase in feed water enthalpy (see Fig. 5.13D).

5.3.3

Effect of friction multiplier model

Apart from the homogeneous model, a large number of two-phase friction multiplier models exist. These models have a significant effect on the predicted flow rate. Fig. 5.14 gives the predicted two-phase NC flow rate as a function of power for the loop shown in Fig. 5.3A with inside diameter of 9.1 mm. The homogeneous model and the two-phase friction multiplier-based models of Martinelli-Nelson (1948), Lockhart-Martinelli (1949), Baroczy (1966), and Sekoguchi et al. (1970) were selected for this comparison. It is seen from Fig. 5.14 that for low quality (less than 0.9%) and low power, all two-phase friction factor models give practically the same flow rate. Beyond 0.9% quality, widely different trends in flow rate are predicted by the different friction factor models. In general, the homogeneous model predicts the trends correctly although there could be some deviations in the predicted magnitude.

212

Single-phase, Two-phase and Supercritical Natural Circulation Systems 0.32 10 kW 30 kW 50 kW

Exit quality (fraction)

Exit quality (fraction)

0.08

0.06

0.04

100 kW 125 kW 150 kW

0.24

0.16

0.08

0.02

3.50x10

5

7.00x10

5

1.05x10

6

1.40x10

6

3.50x10

5

7.00x10

5

1.05x10

6

1.40x10

6

Feed water enthalpy (J/kg)

Feed water enthalpy (J/kg)

(A)

(B) 0.400

0.40

Flow rate (kg/s)

Flow rate (kg/s)

0.375 0.35

50 kW 30 kW 10 kW

0.30

0.350

100 kW 125 kW 150 kW

0.325

0.25 3.50x10

5

7.00x10

5

1.05x10

6

1.40x10

0.300

6

3.50x10

5

7.00x10

5

1.05x10

6

1.40x10

6

Feed water enthalpy (J/kg)

Feed water enthalpy (J/kg)

(C)

(D)

FIGURE 5.13 Effect of feed water enthalpy on two-phase natural circulation flow rate. (A) Variation of exit quality at low power; (B) variation of exit quality at high power; (C) variation of flow rate at low power; (D) variation of flow rate at high power.

0.05

Homogeneous Baroczy Sekoguchi

Martinelli-Nelson Lockhart-Martinelli

0.03 0.02

Quality = 0.9%

Flow rate (kg/s)

0.04

FIGURE 5.14 Effect of twophase friction factor model.

0.01 0.00

0

2

Loop ID = 9.1 mm Pressure = 60 bar

4

6

8

10

Power (kW)

5.3.4

Effect of the acceleration term

Predictions for the two-phase NC flow rate were made with and without the acceleration term to study its influence. These predictions were obtained for

Steady-state and transient analysis Chapter | 5

213

0.5

Flow rate (kg/s)

0.4

0.3

0.2

With acceleration term Without acceleration term

0.1

0.0 0.0

6.0x10

4

1.2x10

5

1.8x10

5

2.4x10

5

3.0x10

5

Power (W) FIGURE 5.15 Effect of acceleration pressure drop on the predicted natural circulation flow rate.

the 19.9 mm loop with the length scales as shown in Fig. 5.3A for a system pressure of 70 bar. The effect of an acceleration pressure drop on the steadystate mass flow rate is shown in Fig. 5.15. The effect of the acceleration pressure drop is found to be significant at high powers in contrast to singlephase loops where its effect is negligible.

5.3.5

Effect of loop geometry

A large number of geometric parameters affect the two-phase NC flow rate. Important among these are the orientation of the source and sink, riser height (elevation), loop diameter, the inlet and exit orificing, etc. The effect of loop diameter and orificing only are presented here.

5.3.5.1 Effect of loop diameter The effect of loop diameter is predicted for the loop shown in Fig. 5.3A and the results are shown in Fig. 5.16. As seen from Fig. 5.16A, the effect of loop diameter looks more or less similar to that of single-phase loops at low powers. As seen from Fig. 5.16B, the gravity-dominant and frictiondominant regimes appear for high powers. 5.3.5.2 Effect of orificing Orificing has a significant location-specific influence on the predicted flow rate. The effect of orificing has been studied for the 19.9 mm loop with the length scales as shown in Fig. 5.3A. As expected, the inlet orificing (i.e., loss coefficient Ki in the single-phase region at the heater inlet) has

214

Single-phase, Two-phase and Supercritical Natural Circulation Systems FIGURE 5.16 Effect of loop diameter at medium pressure for a two-phase natural circulation loop. (A) Effect of loop diameter at low powers; (B) effect of loop diameter at high powers.

1.2

Mass flow rate (kg/s)

Pressure = 70 bar h feed = 572.1327 kJ/kg Elevation = 2.445 m

0.9

0.6

15.7 mm loop 19.9 mm loop 49.3 mm loop

0.3

0.0

0

1250

2500

3750

5000

Power (W) (A)

Mass flow rate (kg/s)

0.700

0.525

14 mm ID 20.7 mm ID 28 mm ID

0.350

0.175

0.000

o

Predictions at 70 bar and 15 C subcooling

0

75

150

225

300

Power (kW) (B)

much less influence on the flow rate compared to exit orificing (i.e., loss coefficient Ke in the two-phase region at the heater exit) as shown in Fig. 5.17. These calculations were carried out with a constant orifice loss coefficient of 30. Also, the predicted difference in flow rates widens with increase in power (Fig. 5.17).

5.3.6

Closure

It may be noted that all major parameters which influence the two-phase NC flow are studied here. However, the influences of some of the important

Steady-state and transient analysis Chapter | 5

215

0.40

Flow rate (kg/s)

0.32

0.24

Ki = 0 & Ke = 0 Ki = 30 & K e = 0 Ki = 0 & Ke = 30

0.16

0.08

0.00 0.0

6.0x10

4

1.2x10

5

1.8x10

5

2.4x10

5

3.0x10

5

Power (W)

FIGURE 5.17 Effect of inlet and exit orificing.

parameters such as the effect of elevation difference and the orientation of the source and sink are excluded as their effect is similar to that of single-phase NC.

5.3.7

Effect of parallel channels

Like a single-phase parallel channel system, two-phase parallel channel systems also exhibit multiple steady-state solutions with differing flow directions. Experiments in a parallel channel system with 10 channels showed that flow reversal can be induced by switching off the power in any channel. Linzer and Walter (2003) showed that the flow reversal in a two-phase parallel channel NCS can occur without reducing the power to zero. Based on their study, a criterion for flow reversal has been given by them for a threechannel system with two unequally heated parallel channels. The methodology for the analysis of parallel channel systems is similar to that discussed in Chapter 4 except that two-phase conditions are encountered. Hence, the effect of parallel channels is not discussed again here.

5.4 Transient performance of two-phase natural circulation systems For the transient case, the time-dependent equations are to be solved numerically as in single-phase loops. However, in two-phase NCSs the fluid density in two-phase regions is a function of phase fraction and the saturation values for the vapor and liquid phases. In single-phase regions, it is a function of pressure and fluid temperature. Similarly, the fluid enthalpy in two-phase

216

Single-phase, Two-phase and Supercritical Natural Circulation Systems

regions is also a function of phase fraction and saturation values for the vapor and liquid phases, while in single-phase regions it is a function of pressure and fluid temperature. Moreover, the estimation of two-phase pressure loss also involves the specification of a two-phase friction multiplier model. Earlier in this chapter, it was pointed out that the homogeneous equilibrium model which assumes equal velocity and equal temperature for both phases predicts the NCS behavior reasonably well. As already stated, although several advanced models like four-equation, five-equation, and six-equation models are available for predicting the behavior of two-phase systems, a detailed discussion of these advanced models is beyond the scope of this book and our discussion is restricted to the homogeneous equilibrium model. Naveen et al. (2017a) developed a system code NUTAN-Th for thermal hydraulic analysis of multichannel NCSs based on the homogeneous equilibrium model. The code has previously been used for analysis of single-phase NCLs (Naveen et al., 2014). For the homogeneous model, the transient mass and momentum balance equations used are the same as those described by Eqs. (5.1) and (5.2). The energy balance equation is somewhat modified as   @ 1 @ðwiÞ @P qξ 1 @ Ak @T @s ðρiÞ 1 2 5 1 ð5:64Þ @t A @s @t A A @s In the energy balance equation, the last term represents the heat transfer due to axial conduction in the fluid. Fluid axial conduction may not play a large role in two-phase flow, however, accounting this term does not introduce any numerical problems. Also, it has some minor effects during start-up from stagnant single-phase initial conditions especially for liquid metals. Since all the NCLs need to be started from single-phase conditions, this term has been included in the energy balance equation. In many closed NCLs, the heater consists of an electrically heated pipe wherein the heat is generated in the pipe wall itself. At the inner wall, heat is exchanged between the pipe and the fluid flowing through the heater. This heat transfer is governed by Newton’s law of cooling given by q 5 hi ðTw 2 T Þ Substituting for q from Eq. (5.65) into Eq. (5.64) yields   @ 1 @ðwiÞ @P hi ξ ðTw 2 T Þ 1 @ Ak @T @s ðρiÞ 1 2 5 1 @t A @s @t A A @s

ð5:65Þ

ð5:66Þ

In addition the equation of state is also needed, which can be written as ρ 5 ρðP; iÞ

ð5:67Þ

Eqs. (5.1), (5.2), and (5.66) form a nonlinear hyperbolic system of partial differential equations.

Steady-state and transient analysis Chapter | 5

FIGURE 5.18 Mesh cell labeling convention (Liles and Reed, 1978).

j+2 lk+2

k+2 k+1 k k-1 zk

zk-1

217

j+1 j

lk+1 lk j-1 j-2

k-2 Reference (i.e., z = 0)

5.4.1

Discretization of governing equations

For the numerical solution of the governing equations, a staggered mesh approach is used. The flow field is divided into nonoverlapping rigid control volumes called cells. The field variables, i, P, and ρ are defined at the cell centers, while the fluid mass flow rate, w, is defined at cell interfaces. The mesh cell configuration and labeling conventions for cell edges and cell centers are depicted in Fig. 5.18. The mass and energy equations are discretized over the mesh cells indicated by solid lines in Fig. 5.18 and the momentum balance equation is integrated over the dashed mesh cells. This forms a staggered spatial difference scheme. Discretization is done making use of a semi-implicit numerical technique. Eq. (5.1) is discretized as

n11 n11 w 2 w j j21 Δt ρn11 5 ρnk 2 ð5:68Þ k Ak lk The momentum conservation equation is discretized as

n n11 n 2Pn11 1 Pn11 ðj 5 1 to m 2 1Þ k Δt 1 kj 1 Cj wj k11 Δt 5 Oj ð5:69Þ where

1 2 0 !n !n 3 2 2 2 φ2LO 1 2 ϕ ϕ φ j flφ flφ j LO n LO LO A1 5ðjwjÞn Δt Cj 5 4Kj@ 1 1 j 4Dh A2 ρf 4Dh A2 ρf 2ρf A2k 2ρf A2k11 k

k11

ð5:70Þ

218

Single-phase, Two-phase and Supercritical Natural Circulation Systems

lk lk11 1 and ð5:71Þ 2Ak 2Ak11 2 3  2 n

 2 n  2 n w w w 1 1 n n 4 5 Oj 5 Ij wj 2 Δt 1 2 2 2 Δt ρA2 k11 ρA2 k 2ρ j A2k11 Ak      2 ρnk11 zk11 2 zj 1 ρnk zj 2 zk gΔt kj 5

ð5:72Þ   n For local losses the term jwj=2ρA2 j is evaluated at the smaller of the cross-section areas on the two sides of the junction. Hence,   1; if Ak =Ak11 , 1 ð5:73Þ ϕj 5 0; if Ak =Ak11 $ 1 The energy conservation equation is discretized as





n11 inj wn11 2 inj21 wn11 hni;k ξ k Tw;k 2 Tkn Δt   j j21 Δt n11 ρ n11 5 ρnk ink 2 1 Pn11 2 Pnk 1 k ik k Ak lk Ak 2 0 1 13 0 1

6 B n C C7 B n nC n C7 B B 2Δt 6 6Aj BTk11 2 Tk C 2 Aj21 BTk 2 Tk21 C7 C C7 B B lk Ak lk 6 4 @ lk11 1 lk A @ 1 lk21 A5 kk11 kk kk kk21 ð5:74Þ

Eqs. (5.68), (5.69), and (5.74) have four unknowns, namely, cell enthalpy, cell pressure, cell density, and junction mass flow rate. A solution of the governing equations in the time domain requires simultaneous solution of Eqs. (5.68), (5.69), and (5.74) and the equation of state (i.e., Eq. 5.67). In the present analysis, this is achieved by eliminating enthalpy from Eq. (5.74) using the equation of state. From the equation of state, the rate of change of density is written as     @ρ @ρ @i @ρ @P 5 1 ð5:75Þ @t @i P @t @P i @t Using Eq. (5.75), Eq. (5.1) is written as     @ρ @i @ρ @P 1 @w 1 1 50 @i P @t @P i @t A @s

ð5:76Þ

Integrating Eq. (5.76) over the control volume “k,” ð t1Δt ð sj   ð t1Δt ð sj ð t1Δt ð sj   @ρ @i @ρ @P 1 @w dsdt1 dsdt1 dsdt 5 0 P @i @t @P @t A @s sj21 sj21 sj21 t t t i ð5:77Þ

Steady-state and transient analysis Chapter | 5

219

 

 @ρ n  n11 n  @ρ n  n11 1 n11 l i 2 i 1 2 Pnk lk 1 wj 2 wn11 P;k k k k i;k Pk j21 Δt 5 0 ð5:78Þ   @i @P Ak Rearranging gives in11 2 ink k 52 Δt

1 n @ρ  @i 

wn11 j

2 wn11 j21

Ak lk

P;k

2

n @ρ  @P i;k n @ρ  @i P;k



Pn11 2 Pnk k Δt

 ð5:79Þ

The energy balance equation, that is, Eq. (5.66) is written in the form as follows: i

  @ρ @i 1 @ðwiÞ @P hi ξðTw 2 T Þ 1 @ @T 1ρ 1 2 5 1 Ak @t @t A @s @t A A @s @s

ð5:80Þ

Substituting for @ρ=@t from Eq. (5.1) into Eq. (5.80),   i @w @i 1 @ðwiÞ @P hi ξ ðTw 2 T Þ 1 @ @T 1ρ 1 2 5 1 Ak 2 A @s @t A @s @t A A @s @s

ð5:81Þ

Integrating Eq. (5.81) over control volume “k,” gives Ð t1Δt Ð sj

@i dsdt 1 @t

ð t1Δt ð sj

1 @ðwiÞ dsdt t sj21 A @s ð t1Δt ð sj Ð t1Δt Ð sj i @w @P 2 t dsdt 5 sj21 A @s dsdt 2 sj21 @t t   ð t1Δt ð sj Ð t1Δt Ð sj hi ξ ðTw 2 T Þ 1 @ @T dsdt 1 Ak dsdt sj21 t A @s t sj21 A @s t

sj21 ρ





  n11 n n11 n n n11 n11 n w i 2 w i i w 2 w n in11 j j j21 j21 k j j21 2 ik 1 ρk k 2 A k lk Ak lk Δt

 n11  n n11 n n h ξ T 2 T k i;k w;k k P 2 Pk 5 2 k 1 Ak Δt 2 0 1 0 13 B n B T n 2 T n C7 n C 1 6 6 B Tk11 2 Tk C B k21 C7 6Aj B C 2 Aj21 B k C7 lk A lk21 A5 @ lk Ak lk 4 @ lk11 1 1 2kk11 2kk 2kk 2kk21

ð5:82Þ

ð5:83Þ

220

Single-phase, Two-phase and Supercritical Natural Circulation Systems





   n11  n n wn11 inj 2 ink 2 wn11 inj21 2 ink n in11 j j21 2 i P 2 P k k k k ρk 2 1 Ak lk Δt Δt 2 0 1 0 13

n n11 n B n B T n 2 T n C7 n C hi;k ξk Tw;k 2 Tk 1 6 6 B Tk11 2 Tk C B k21 C7 1 5 6 Aj B C 2 Aj21 B k C7 lk A lk21 A5 @ lk Ak lk 4 @ lk11 Ak 1 1 2kk11 2kk 2kk 2kk21 ð5:84Þ Substituting for in11 from Eq. (5.79) into Eq. (5.84) gives, k "

n  @ρ  n n ij 2 ik 2 ρnk wn11 j  @i P;k "  # n n    n

 @ρ  n n11 Ak lk @ρ n @ρ  n n   Pn11  5 ij21 2 ik 2 ρ k wj21 1 1ρ k    @i P;k @P Δt @i P;k k i;k n  !

A l @ρ n n @ρ n @ρ  n k k n11 n    1 h ξ lk Tw;k 2 Tk 2 1ρ k Pn @i P;k i;k k @i P;k @P i;k k Δt 2 0 1 0 13 n B n B T n 2 T n C7 nC @ρ  6 6 BT 2 Tk C B k21 C7 1 2  6Aj B k11 C 2 Aj21 B k C7 lk A lk21 A5 @ lk @i P;k 4 @ lk11 1 1 kk11 kk kk kk21 ð5:85Þ

For convenience, Eq. (5.85) is written in the following form n n11 n11 Γnj;k wn11 5 Γnj21;k wn11 1 Γnw;k Tw;k 1 Θnk j j21 1 Ωk Pk

where

n  @ρ  n n 5 ij 2 ik 2 ρnk  @i P;k n

 @ρ  n ij21 2 ink 2 ρnk Γnj21;k 5  @i P;k Γnj;k

ð5:86Þ

ð5:87Þ ð5:88Þ

Steady-state and transient analysis Chapter | 5

Ωnk

Ak l k 5 Δt

 ! n n @ρ n @ρ   1ρ k  @i P;k @P i;k

@ρ n n h ξ lk @i P;k i;k i;k n n n !     @ρ A l @ρ @ρ n k k  hn ξ lk T n 2  1 ρ  Pnk and Θnk 5 2 k @P  @i P;k i;k i;k k @i P;k Δt i;k 2 0 1 0 13  B n B T n 2 T n C7 nC @ρ n 6 6 BT 2 Tk C B k21 C7 1 2  6Aj B k11 C 2 Aj21 B k C7 lk A lk21 A5 @ lk @i P;k 4 @ lk11 1 1 kk11 kk kk kk21 Γnw;k 5

221

ð5:89Þ ð5:90Þ

ð5:91Þ

The advantage of presenting the energy conservation equation in the form given by Eq. (5.86) is that this equation has enthalpy terms of old time step which are known. This allows for the solution of Eqs. (5.68), (5.69), and (5.86) using the tridiagonal matrix algorithm (TDMA). The solution of discretized energy balance equations, that is, Eqs. (5.74) and (5.86), needs fluid enthalpies at cell junctions. However, in the staggered mesh approach adopted here, the fluid enthalpy is not defined at the cell interfaces or junctions and, hence, needs to be evaluated in terms of known quantities. This can be achieved using the upwind scheme. As per this scheme, junction enthalpy is given by     1 1 ηj n 1 2 ηj n n ij 5 ð5:92Þ ik 1 ik11 2 2 where

  ηj 5 wnj =wnj

ð5:93Þ

5.5 Solution procedure The solution of governing equations in time domain involves the following steps: 1. Eqs. (5.70)(5.72) and (5.87)(5.91) are evaluated first. These equations give the coefficients in Eqs. (5.69) and (5.86), respectively. The system of equations given by Eqs. (5.69) and (5.86) (in the case of flow through a channel, pressures at channel inlet and exit are given) constitute “2m 1 1” equations in “2m 1 1” unknowns. The unknowns are “m 1 1” junction flow rates and “m” cell pressures. The solution for this system of equations is obtained using TDMA.

222

Single-phase, Two-phase and Supercritical Natural Circulation Systems

2. Having obtained the junction mass flow rate for all the junctions at the new time step, Eq. (5.68) is solved for density in each cell at the new time step. Finally, the enthalpy in each cell at the new time step is obtained from the solution of Eq. (5.74) for each cell.

5.6 Typical transient solutions To illustrate the use of the above-described solution methodology, a few typical transients relevant to two-phase NC are solved here.

5.6.1

Start-up from rest

Unlike forced circulation systems where flow can be established before the heater is switched on, a NCS needs to be started from the state of stagnant initial conditions. A two-phase NCL passes through the state of single-phase NC before it reaches the state of a two-phase NCL. Naveen et al. (2010) studied the start-up of NCSs and studied the effect of loop diameter and operating conditions on their start-up. Fig. 5.19 shows the start-up predictions made using NUTAN-Th code for the loop shown in Fig. 5.3B from stagnant single-phase initial conditions at a pressure of 5 bar. At time t 5 0, the heater power is suddenly raised to 20 kW. To start with the single-phase NC sets in the loop till the fluid temperature reaches the saturation temperature. With the initiation of boiling, the buoyancy force increases significantly, which leads to a sharp rise in the loop mass flow rate. With the increased mass flow rate the heater exit enthalpy becomes less than the saturation value and as a result the system returns back to single-phase NC, resulting in a sharp reduction in flow. The reduced flow rate increases the exit enthalpy beyond the saturation value, resuming steam production and resulting in a sharp increase in the flow rate and the system returns back to single-phase again. After a few oscillations, steady two-phase NC is achieved. The inset in Fig. 5.19A shows the mass flow rate oscillations during the transition from single-phase natural circulation (SPNC) to two-phase natural circulation (TPNC). It may be noted that, although the riser is adiabatic, its steam quality is slightly larger (see Fig. 5.19B) because of the flashing induced by the static pressure decrease as the fluid rises up. It may also be noted that the quality appears first in the riser exit and then in the heater exit, which is again attributed to flashing. These oscillations could induce significant vibrations in the case of loops with very tall risers. Fig. 5.20 shows predictions for the start-up and power raising in the 15.7 mm inside diameter loop shown in Fig. 5.3A from stagnant single-phase initial conditions at 25 bar. At time t 5 0, the heater power is raised to 2.5 kW and is gradually increased in steps to 6 kW. To start with, the singlephase NC sets in the loop till the fluid temperature reaches the saturation value. With the initiation of boiling, the buoyancy force increases

Steady-state and transient analysis Chapter | 5

Pressure: 5 bar Power: 20 kW 2.5

2.0

2.0 Mass flow rate (kg/s)

Flow rate (kg/s)

2.5

1.5

223

TPNC

1.5

1.0

0.5

1.0 0.0 1400

1450

1500

1550

Time (s)

0.5 SPNC

0.0

1000

2000

Time (s) (A) 0.008

Steam quality (fraction)

Heater exit Riser exit

0.006

0.004

0.002

0.000 1400

1450

1500

1550

Time (s) (B) FIGURE 5.19 Start-up transient at 5 bar in the loop shown in Fig. 5.3B due to a sudden increase of power. (A) Flow variation; (B) quality variation.

significantly, which leads to a sharp rise in loop mass flow rate. In the gravity-dominant region, as described earlier, flow increases with an increase in power. Note that the flow rate oscillations are significantly reduced in this case due to the higher pressure.

5.7 Parametric influences In a NCS, system thermal-hydraulic behavior is highly dependent on system geometry and operating conditions. System operating parameters which

Single-phase, Two-phase and Supercritical Natural Circulation Systems

0.20

7000

Flow Mass flow rate (kg/s)

FIGURE 5.20 Predicted start-up behavior for 15.7 mm ID loop at 25 bar pressure.

8000 Pressure = 25 bar

0.15

6000 5000

0.10

4000 3000

Power 0.05

Power (W)

224

2000 1000

0.00 0

1000

2000

3000

4000

5000

0 6000

Time (s)

influence the transient behavior include power, pressure, inlet subcooling, feed water flow rate, and inlet temperature. The effects of some of these parameters are studied in this section.

5.7.1

Effect of initial pressure

The flow rate in a two-phase NCS is dependent on the operating conditions such as system pressure and heater power. This can easily be understood from the variation of steam void fraction with steam quality given in Fig. 5.8. A careful analysis of Fig. 5.8 shows that for the same value of steam quality, the void fraction value varies significantly with system pressure. At low pressure, a steam quality of 1% can result in almost 95% void fraction whereas the same quality near critical pressure leads to an almost equal value of void fraction. It was explained earlier that the driving force in a NCS depends upon the density difference and height difference between the sink and source. Therefore the larger the void fraction in the hot leg, the larger is the driving force. This effect becomes much more pronounced for systems having tall chimneys/risers. Fig. 5.21A and B show the start-up simulation for the 15.7 mm inside diameter loop with the length scales as given in Fig. 5.3A at pressures of 3 and 5 bar, respectively. It may be noted that the amplitude of oscillations during the transition from single-phase to two-phase NC decrease with increase in pressure whereas the steady-state flow at 5 bar is more than that at 3 bar indicating that both transients are in the friction dominant region. This becomes clear if we compare Fig. 5.21 with Fig. 5.12.

5.7.2

Effect of loop diameter

Fig. 5.22A and B shows the simulations for 25 bar pressure for 9.1 and 15.7 mm inside diameter loops, respectively. The length scales of the loops

Steady-state and transient analysis Chapter | 5 (A)

FIGURE 5.21 Model predictions for 15.7 mm ID loop at 250 W and 3 and 5 bar. (A) Start-up at 3 bar; (B) start-up at 5 bar.

0.20 Power = 250 W 0.15

Flow rate (kg/s)

225

0.10

0.05

0.00 15,000 15,500 16,000

16,500 17,000 17,500 Time (s)

18,000

(B) 0.20 Power = 250 W

Flow rate (kg/s)

0.15

0.10

0.05

0.00 12,000

12,500

13,000

13,500

14,000

14,500

15,000

Time (s)

correspond to that shown in Fig. 5.3A. A comparison of Fig. 5.22A and B shows that for the same operating pressure, the loops having lower diameter are more oscillatory. Increasing the loop diameter significantly reduces the amplitude of two-phase flow oscillations. Also as expected, the larger diameter loop shows significantly larger flows. Also, in the case of the 9.1 mm diameter loop, the peak flow rate is obtained at about 1.8 kW and subsequently the friction-dominant region sets in, whereas for the 15.7 mm loop the gravity-dominant region is observed even at 6 kW.

5.7.3

Effect of parallel channels on the transient behavior

Parallel heated channels are present in almost all nuclear as well as the fossil-fueled power plants. Hence, the study of parallel channel effects is important for transients in these plants. Parallel channels can show interesting behavior during the transients, including flow reversals. For simulating

Single-phase, Two-phase and Supercritical Natural Circulation Systems

Mass flow rate (kg/s)

(A)

9.1 mm ID

Pressure = 25 bar

0.07

8000

0.06

7000

0.05

6000

0.04

5000

0.03

4000

0.02

3000

0.01

2000

0.00

1000

–0.01 0

Power (W)

226

FIGURE 5.22 Model predictions for 9.1 mm ID loop at 25 bar pressure. (A) Start-up and power raising in 9.1 mm loop; (B) start-up and power raising in 15.7 mm loop.

0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 5500 6000 Time (s)

(B) 0.20

8000 Pressure = 25 bar 7000

Flow

6000 5000

0.10

4000

Power (W)

Mass flow rate (kg/s)

0.15

3000

Power 0.05

2000 1000

0.00

0

1000

2000

3000

4000

5000

0 6000

Time (s)

parallel channel behavior in the time domain the governing equations remain the same as described earlier. However, most of the commercial computer codes are capable of handling only a few parallel channels during transient analysis, whereas NC-based boiling water reactors and fossil fuel plants have hundreds of parallel channels. For example, a typical configuration of the NC-based vertical pressure tube-type boiling water reactor, such as AHWR, has 452 parallel channels. Naveen et al. (2017a) developed a computer code, NUTAN-Th, to simulate the behavior of multichannel systems. As described earlier, the code is based on the homogeneous equilibrium model. In the code, the governing equations are discretized for each channel as described in Section 5.4 and pressure is assumed to be uniform in the inlet and outlet plena (headers). This implies that we need to solve the discretized equations for all the channels simultaneously. Naveen et al. (2017b) carried out cold start-up simulation of AHWR using computer code, NUTAN-Th. A typical configuration of the main heat transport system of AHWR considered for the analysis is shown in Fig. 5.23A and B.

227

Steady-state and transient analysis Chapter | 5 Steam

(A)

(B) Steam to turbine

Steam drum

Feed water

Steam drum

Feed water in

Downcomer Tail pipe Down comer

Distribution ring header Calandria housing active core

Tail pipes

Calandria

Ring header

Feeders

Feeder

FIGURE 5.23 Schematic of the pressure tube-type reactor. (A) Schematic of the MHTS; (B) schematic of one loop.

It has four loops (only two are shown in Fig. 5.23A), each with a steam drum from where four downcomers take off (only one is shown in Fig. 5.23A and B) and join a ring header which is common to all four loops. From the header, the feeders take off and join to an equal number of coolant channels where the subcooled water absorbs heat and becomes a two-phase mixture. The two-phase mixture rises through the tail pipes to the steam drum where it gets separated and the separated steam goes out. The separated water mixes with the subcooled feed water and enters the downcomers, thus completing the circuit. The density difference between the subcooled water in the downcomer and two-phase mixture in the tail pipe provides the driving force for the NC flow. Each loop has 113 parallel channels (only three are shown in Fig. 5.23B) connected between the ring header and the steam drum and four downcomers connecting the steam drum to the inlet header. Each loop serves one quarter of the core. Several peripheral channels are orificed and the orifice loss coefficients used in the calculation are shown in Table 5.2. As can be seen, most of the central channels are not orificed (loss coefficient equals 0). The channel power distribution at FP is shown in Table 5.3. The table also shows how the channels are named. A transient simulation was carried out considering all 113 channels in a loop. For this simulation, a cold start-up at 2% FP and 70 bar was simulated from stagnant initial conditions assuming the power distribution to be the same as at full power. Hence to obtain the channel powers at 2% FP, the value given for each channel in Table 5.3 is divided by 50. The predicted transients in all the channels are similar. Hence, typical predicted transients in the 10 channels of the K-row (the channels inside the dotted line in Table 5.2) are shown in Fig. 5.24A and B. It may be noted that

228

Single-phase, Two-phase and Supercritical Natural Circulation Systems

TABLE 5.2 Map for the inlet orifice loss coefficient.

13

12 14

11 15

10 16

9 17

8 18

Z

A

300

300

300

300

300

300

Y

B

SOR

300

300

300

300

300

7 19

6 20

5 21

4 22

3 23

2 24

1 25

300

X

C

0.0

0.0

0.0

SOR

0.0

0.0

0.0

0.0

W

D

AR

0.0

0.0

0.0

0.0

0.0

SOR

0.0

0.0

V

E

0.0

0.0

0.0

0.0

RR

0.0

0.0

0.0

0.0

0.0

U

F

0.0

0.0

SOR

0.0

0.0

0.0

0.0

SOR

0.0

0.0

0.0

T

G

SR

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

SOR

0.0

300

S

H

0.0

0.0

0.0

0.0

0.0

AR

0.0

0.0

0.0

0.0

0.0

300

R

J

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

RR

0.0

0.0

300

300

Q

K

SOR

0.0

0.0

SR

0.0

0.0

0.0

0.0

0.0

0.0

SOR

300

300

P O

300

0.0

0.0

0.0

0.0

0.0

0.0

0.0

SOR

0.0

0.0

0.0

300

300

M

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

300

300

N

SOR

0.0

0.0

SOR

0.0

0.0

SR

0.0

0.0

AR

0.0

SOR

300

L

Note: The symmetry lines go through the middle of channels in the N-th row and 13th column. RR, regulating rod; SR, shim rod; SOR, shut-off rod; AR, adjuster rod.

in all channels the NC flow initiates in single-phase condition. However, the flow rates are not equal as the power in each channel is different. The flow initiation in single-phase condition is accompanied by oscillations. The oscillations persist for a longer time in low-power channels. Subsequently, a stable marginally increasing single-phase flow is observed during the heat-up phase. Once the saturation values are achieved, a sharp jump in flow rate with a few oscillations is observed. The transition from single-phase to twophase NC is shown in detail in Fig. 5.24B. Subsequently, a stable steady state with flow rate more than thrice that of the initial single-phase NC is attained with two-phase NC. Fig. 5.25A shows the predicted downcomer flow rate variation during cold start-up at 2% FP. The flow rate variations of all four downcomers are almost identical. Although the downcomer flow rate remains entirely in single phase, a jump in flow rate is observed as the boiling occurs in the core outlet. Fig. 5.25B shows the sharp rise in flow during the phase change in the channels during the transient.

Steady-state and transient analysis Chapter | 5

229

TABLE 5.3 Typical channel power distribution in the AHWR core.

13

Z

A

Y

B

X

C

W

D

V

F

T

G

R

10

9

8

7

6

5

4

3

2

1

15

16

17

18

19

20

21

22

23

24

25

1.842

1.707

1.649

1.628

1.635

1.655

SOR

1.842

1.75

1.908

1.732

1.658

1.859

1.84

1.782

2.047

SOR

2.07

1.897

2.038

2.094

AR

1.779

1.977

2.163

2.045

2.163

SOR

2.147

2.01

1.855

1.979

2.224

2.103

RR

2.086

2.308

2.301

2.01

2.008

2.187

2.249

SOR

2.259

2.015

1.966

2.262

SOR

2.298

2.142

2.086

SR

2.333

2.254

2.109

1.914

1.845

1.984

2.259

2.303

SOR

2.028

1.846

2.338

2.152

2.064

2.076

1.895

AR

1.843

1.962

2.079

2.153

1.886

1.645

1.63

2.391

2.195

2.156

2.256

2.051

1.893

1.911

2.009

RR

2.034

2.055

1.716

1.606

H J

Q

K

P

L

O

11

14

E

U

S

12

SOR

2.422

2.383

SR

2.254

2.073

2.104

2.251

2.093

2.149

SOR

1.888

1.598

2.461

2.267

2.24

2.382

2.153

2.06

2.247

SOR

2.213

1.963

2.028

1.731

1.618

2.487

2.289

2.266

2.42

2.192

2.147

2.326

2.24

1.959

1.766

1.766

1.819

1.673

SOR

2.487

2.461

SOR

2.391

2.338

SR

2.187

1.855

AR

1.84

SOR

1.842

M N

Note: The symmetry lines go through the middle of channels in the N-th row and 13th column. Channel powers in MWth. RR, regulating rod; SR, shim rod; SOR, shut-off rod; AR, adjuster rod.

5.8 Closure A methodology for the steady-state analysis has been presented in this chapter along with derivation of explicit flow rate equations for both closed- and open-loop NCSs. A dimensionless equation for flow rate has also been derived. However, an explicit dimensionless flow rate equation can be obtained only for closed loops. For open loops, the dimensionless flow equation is a polynomial. If the acceleration term can be neglected then the explicit dimensionless equations for the closed and open loops become the same. Both the explicit dimensional and dimensionless flow rate equations are based on the homogeneous equilibrium model. The steady-state performance of the homogeneous model when compared with the two-fluid model showed only marginal deviation, which is attributed to the near thermal equilibrium that exists in low-velocity NC flows. In addition, the difference in vapor and liquid velocities is not large enough to cause significant deviation in the

230 (A)

Single-phase, Two-phase and Supercritical Natural Circulation Systems

6 Mass flow rate (kg/s)

FIGURE 5.24 Cold start-up at 2% power for a pressure tube-type natural circulation-based BWR. (A) Start-up transient for various channels in K-row; (B) transition from SPNC to TPNC.

7

K1 K2 K4 K5 K6 K7 K8 K9 K11 K12

5 4 3 2 1 0 0

5000

10,000

15,000

20,000

25,000

30,000

Time (s)

(B)

7 K1 K2 K4 K5 K6 K7 K8 K9 K11 K12

Mass flow rate (kg/s)

6 5 4 3

TPNC

2 SPNC 1 0 29,500

30,000

30,500

31,000

Time (s)

predictions for the loops considered for analysis. However, this may not remain valid for transients involving severe nonequilibrium effects like LOCA with cold water injection. The adequacy of the dimensionless equation derived has been tested with data from both uniform and nonuniform diameter loops which showed deviations within 6 40%. Using the explicit equations derived for the steady-state behavior, a parametric analysis of both open- and closed-loop NCSs has been carried out. The analysis covered the parametric influences of the operating parameters such as power, pressure, feed water enthalpy, as well as the geometric parameters like loop diameter. Unlike single-phase systems, the acceleration term has significant influence on the steady-state performance of two-phase NC systems. The influence of local loss coefficient is found to be location-specific, unlike single-phase NCSs. The local loss coefficient in the two-phase region has a stronger influence on the steady-state flow rate than the local loss coefficient in the single-phase region. An interesting characteristic of two-phase NCLs is the existence of buoyancy-dominant and

Steady-state and transient analysis Chapter | 5

160

70

140

Mass flow rate (kg/s)

60

Downcomer 1 Downcomer 2 Downcomer 3 Downcomer 4

120

50

100 40 80 30 60

Power (% FP)

(A)

231

FIGURE 5.25 Variation of the flow rate in the downcomer during cold start-up. (A) Downcomer flow variation; (B) sharp rise in flow due to the phase change.

20

40 Flow

10

20 Power 0

0

5000

10,000

15,000

20,000

25,000

30,000

0

Time (s) 5 Downcomer 1 Downcomer 2 Downcomer 3 Downcomer 4

Mass flow rate (kg/s)

80

4

60

3

Power

40

2

Power (% FP)

(B)

100

Flow

20

1

0 29,000

29,500

30,000

30,500

0 31,000

Time (s)

friction-dominant regimes which are not normally observed in single-phase closed loops except at very high elevations. Certain parameters like pressure have contradicting influences on the flow rate depending on the NC flow regime. A formulation for the transient analysis of two-phase NCLs has been presented based on the homogeneous equilibrium model. Using the formulation, transient analysis of simple open loops and a pressure tube-type boiling water reactor have been performed. Influences of some important parameters on the transient performance have also been explored. It may be noted that the transient formulation presented for two-phase NCSs is also applicable to single-phase NCSs.

Nomenclature A a

flow area, m2 dimensionless flow area (A/Ar)

232

Single-phase, Two-phase and Supercritical Natural Circulation Systems

b Cp D d f g Grm H h I II i K k L lk l N NG P p Q q R Ress s S Δs t Δt T v v V w x z Z

exponent in the friction factor equation specific heat, J/(kg K) diameter, m dimensionless hydraulic diameter (D/Dr) friction factor acceleration due to gravity, m/s2 modified Grashof number (D3r ρ2f β h gQh H=Ar μ3r Þ height, m heat transfer coefficient,W/m2K  dimensionless enthalpy I 5 ði 2ir Þ=Δi Hh  dimensionless enthalpy integral II 5 IdZ enthalpy, J/kg loss coefficient thermal conductivity, W/(mK) length, m length of kth control volume, m dimensionless length, (L/Lt) number of pipe segments geometric number defined by Eq. (5.33) pressure, Pa constant in friction factor equation power, W heat flux, W/m2 24 hydraulic resistance,  m  Reynolds number, Dr wss =Ar μr coordinate along the loop, m dimensionless coordinate around the loop (s/H) space step, m time, s time step, s temperature, K specific volume, m3/kg dimensionless specific volume, (v/vr) volume, m3 mass flow rate, kg/s quality elevation, m dimensionless elevation (z/H)

Subscripts 0 a B c cl DC e

reference ambient boiling cooler cold leg downcomer exit

Steady-state and transient analysis Chapter | 5 eff eq F f fg h hl i i, in j k o r s SD sp ss t tp tp,c w

effective equivalent feed saturated liquid gas minus liquid heater hot leg inside, ith segment, ith node inlet junction kth control volume outside reference secondary, steam, single-phase steam drum single-phase steady state total two-phase two-phase cooler wall

Superscripts 2 n

mean value nth time step

Greek symbols α βh βh γ Δ φ2LO θ μ ξ ρ

thermal diffusivity, m2/s thermal expansion coefficient based on enthalpy, (J/kg)21 thermal expansion coefficient based on temperature, K21 H parameter defined as Li =Ai , 1/m refers to difference two-phase friction multiplier angle between the flow direction and the horizontal dynamic viscosity, kg/(ms) perimeter, m density, kg/m3

List of acronyms used AHWR AR BWR CANDU DFM ESBWR EVET

advanced heavy water reactor adjustor rod boiling water reactor Canadian deuterium uranium reactor drift flux model economic simplified boiling water reactor equal velocity equal temperature

233

234

Single-phase, Two-phase and Supercritical Natural Circulation Systems

FDR FP GDR ID LHS LOCA MHTS NC NCL NCS PWR RHS RR SBLOCA SD SOR SPNC SR TDMA TFM TPNC UDL UVUT

friction-dominant regime full power gravity-dominant regime inside diameter left-hand side loss of coolant accident main heat transport system natural circulation natural circulation loop natural circulation system pressurized water reactor right-hand side regulating rod small break LOCA steam drum shut-off rod single-phase natural circulation shim rod tridiagonal matrix algorithm two-fluid model two-phase natural circulation uniform diameter loop unequal velocity unequal temperature

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