Thermal hydraulic parameters of coolant channels

The pertinent parameters required for the analysis of coolant channels are tabulated in Table 3. Figure 17 shows the power dissipate and the temperature increase in each channel at 265 kW reactor total power. This power was the results of the thermal power calibration (Mesquita et al. 2007). The profile of the mass flow rate and velocity in the core is shown in the graphs of Figure 18. Figure 19 compares experimental and theoretical profile of mass flux G in the core coolant channels. The theoretical values were calculated using PANTERA code (Veloso, 2005). As it can see by the Reynolds number the flow regime is turbulent in channels near the core centre.

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Channel

Channel

Tout — Tin

Flow

Area

Mass

Velocity

Reynolds

Power

Rate

Flux

Number

q

Д T

m

G

u

Re

[kW]

[°C]

[kg/s]

[cm2]

[kg/m2s]

[m/s]

0

2.65

15.5

0.041

1.574

260.48

0.26

3228

1

9.81

15.5

0.151

8.214

183.83

0.18

5285

2

5.70

17.1

0.080

5.779

138.44

0.14

5181

3

4.85

16.3

0.071

5.735

123.79

0.12

4184

4

3.00

12.1

0.059

5.694

103.62

0.10

2525

5

0.93

7.7

0.029

3.969

73.06

0.07

549

Specific heat (cr ) = 4.1809 [kJ/kgK], water density (p) 995 kg/m3 and dynamic viscosity(u) = 0.620 10-3 kg/ms at 45 oC.

Table 3. Properties of the coolant channel at the power of 265 kW1

 

As can be seen in Figure 18 and Figure 19 the velocity and mass flux in each channel are proportional to power dissipated in the channel.

 

Channel Power and Temperature Increase

 

Д Temperature

 

Power

 

— о

 

Channe Number

 

Fig. 17. Power and temperature increase in coolant channels at 265 kW

 

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Fig. 18. Mass flow rate and velocity in coolant channels at 265 kW

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Fig. 19. Mass flux in coolant channels at 265 kW 4.3 Pool temperature

Figure 20 shows the water temperatures evolution at the reactor pool, and the inlet and outlet coolant temperature in the core’s hottest channel until the beginning of steady state. The results showed that the thermocouples positioned 143 mm over the top grid plate (Inf 7) measure a temperature level higher than all the other thermocouples positioned over the reactor core. The temperature measurements above the core showed that thorough mixing of water occurs within the first centimeters above core top resulting in a uniform water temperature. It means that the chimney effect is not much high, less than 400 mm above the reactor core, in agreement with similar experiments reported by Rao et al. (1988). The chimney effect is considered as an unheated extension of the core. The chimney height is the
distance between the channel exit and the fluid isotherm plan above the core and it depends of the reactor power.

Подпись: Primary Inlet

image056 Подпись: Ground Подпись: Sup l Подпись: Ground

image059Primary Outlet

Подпись: Air Ground Channel

Outlet

Подпись: Time [ s ] Подпись: 22000 Подпись: 27000

.Channel

Fig. 20. Temperatures patterns in the reactor pool at 265 kW thermal power

1.4 Temperatures with the forced cooling system tuned off

Подпись: Fig. 21. Temperature evolution as a function of power with the forced cooling system off

Figure 21 shows the behavior of fuel element, channel outlet, reactor pool, and specimen rack temperatures at various operation powers, with the forced cooling system turned off.