Westinghouse 4-loop PWR
E935605
The Westinghouse 4-loop PWR is a large commercial pressurized water reactor design featuring four primary coolant loops, widely used in nuclear power plants for reliable baseload electricity generation.
Statements (48)
| Predicate | Object |
|---|---|
| instanceOf |
commercial nuclear power reactor design
ⓘ
pressurized water reactor design ⓘ |
| application | baseload electricity generation ⓘ |
| containmentType | large dry containment (in many implementations) ⓘ |
| controlMechanism |
chemical shim using boric acid in coolant
ⓘ
control rods ⓘ |
| coolantType | light water ⓘ |
| coolingSystem | closed primary coolant loop ⓘ |
| coreLocation | reactor pressure vessel ⓘ |
| deploymentContext | commercial nuclear power plants ⓘ |
| designer | Westinghouse Electric Company NERFINISHED ⓘ |
| designGoal |
high availability
ⓘ
high reliability ⓘ long fuel cycles ⓘ |
| fuelForm | zirconium-alloy clad fuel rods ⓘ |
| fuelType | low-enriched uranium dioxide ⓘ |
| generationCategory | Generation II nuclear power plant design ⓘ |
| geographicalUse | worldwide ⓘ |
| gridRole | reliable baseload power supply ⓘ |
| heatTransferMechanism | primary-to-secondary heat exchange in steam generators ⓘ |
| moderatorType | light water ⓘ |
| neutronSpectrum | thermal ⓘ |
| numberOfPrimaryLoops | 4 GENERATED ⓘ |
| pressureBoundary | reactor coolant system pressure boundary ⓘ |
| primaryCircuitConfiguration | four-loop ⓘ |
| primaryCoolantPressure | high pressure to prevent boiling ⓘ |
| primaryCoolantSystemComponent |
pressurizer
GENERATED
ⓘ
reactor coolant pump GENERATED ⓘ steam generator GENERATED ⓘ |
| reactivityControlMethod |
control rod insertion and withdrawal
ⓘ
soluble boron ⓘ |
| regulatoryCategory | light water reactor ⓘ |
| relatedDesign |
Westinghouse 2-loop PWR
NERFINISHED
ⓘ
Westinghouse 3-loop PWR NERFINISHED ⓘ |
| safetyFeature |
containment building
ⓘ
control rod shutdown system ⓘ emergency core cooling system ⓘ multiple redundant safety systems ⓘ |
| secondarySideWorkingFluid | water-steam ⓘ |
| steamCycleType | indirect steam cycle ⓘ |
| steamGeneratorType | U-tube steam generator ⓘ |
| thermalEfficiencyClass | typical of large PWRs ⓘ |
| thermalPowerClass | large commercial power reactor ⓘ |
| typicalElectricalOutputRange | approximately 900 to 1300 MWe ⓘ |
| typicalFuelCycleLength | about 18 months ⓘ |
| typicalFuelEnrichment | about 3 to 5 percent U-235 ⓘ |
| typicalOperatingTemperature | primary coolant hot leg temperature around 300 degrees Celsius GENERATED ⓘ |
| usesNeutronReflector | yes, in many implementations ⓘ |
Referenced by (1)
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