Natural Circulation

15.25. Natural circulation, or more accurately, natural recirculation of the coolant, is the most interesting thermal-hydraulic feature of the SBWR.

image334

Simplified Boiling Water Reactor Assembly

1 Reactor Pressure Vessel

2 RPVTop Head

3 Integral Dryer-Separator Assembly

4 Main Steam Line Nozzle

5 Depressurization Valve Nozzle

6 Chimney

7 Feedwater Inlet Nozzle

8 Reactor Water Cleanup/Shutdown Cooling Suction Nozzle

9 Isolation Condenser Return Nozzle

10 Gravity-Driven Cooling System Inlet Nozzle

11 RPV Support Skirt

12 Core Top Guide Plate

13 Fuel Assemblies

14 Core Plate

15 Control Rod Guide Tubes

16 Fine Motion Control Rod Drives

 

Fig. 15.3. SBWR assembly (General Electric Co.).

 

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TABLE 15.2. SBWR Design Specification Summary

General

Thermal-Hydraulic

Power

Thermal 1800 MW Electrical 600 MW Power density 42.0 MW/m3

System pressure 7.17 MPa(a) (1040 psia) Steam temp. 288°C (550°F) Feedwater temp. 216°C (420°F) Recirculation flow 60 Mg/s

Core

Control

Length 2.44 m Diameter, equivalent 4.73 m

Control rod number 177 Neutron absorber B4C Control rod form Cruciform drive Electro-hydraulic fine — motion

Fuel

Assemblies in core 732

Lattice type 8×8

Rod, OD 12.3 mm (0.484 in.)

It is dependent on the difference in density between the cooler returning and feed fluid mix in the downcomer leg and the steam-water mixture in the core and chimney. As pointed out in §9.131, the flow rate depends on the relative influence of the density difference “driving force” and the frictional flow resistance. Hence, a short core of relatively low flow resist­ance is needed to assure an adequate recirculation rate. To assure reactor stability, the core flow must be maintained above certain levels which depend on the reactor power.

15.26. Reactor stability during normal operation and anticipated tran­sients is an important design consideration for all BWRs. For example, reactivity feedback instability of the reactor core could result in power oscillations. Hydrodynamic channel instability could inpede heat transfer to the moderator and also drive the reactor into power oscillations. Finally, the total system stability depends on the basic process dynamics. Stability criteria are stated in terms of a decay ratio, which is defined as the ratio of the magnitude of the second oscillatory overshoot to that of the first overshoot resulting from a step perturbation. The lower the ratio, the more stable the system. SBWR stability decay ratios have been modeled and found to be at least a factor of 2 lower than those for currently operating BWRs [3].