The feedwater is the water returning from the balance of plant, i.e., from the turbine condensation and condenser following the low pressure turbine. The water is at a lower temperature than core inlet. In a BWR, moisture (at core exit temperature) is separated in 'moisture separators' or 'steam dryers', and that is sent to the annulus where it is mixed with the cooler 'feedwater' from the balance of plant. The mixture is then pumped back to the core inlet.Luxdot said:Summary:: Inlet water temp vs feeder water temp
How can the inlet water temp be higher than the one of the feeder water that is in the reactor tank of a BWR?
A BWR (Boiling Water Reactor) is a type of nuclear reactor where water is used as both the coolant and the moderator for the nuclear reaction. It is a common type of reactor used for electricity generation.
Water temperature is an important factor in the operation of a BWR. The hotter the water, the more steam is produced, which is used to turn turbines and generate electricity. However, if the water temperature gets too high, it can cause problems with the reactor's cooling system and potentially lead to a shutdown.
The ideal water temperature for a BWR is typically between 550-600 degrees Fahrenheit (288-315 degrees Celsius). This allows for efficient electricity generation without putting too much strain on the reactor's cooling system.
The water temperature in a BWR is controlled through a system of pumps, valves, and heat exchangers. The pumps circulate the water through the reactor core, where it is heated by the nuclear reaction. The heat exchangers then transfer the heat to a secondary water system, which produces steam to power the turbines. The valves regulate the flow of water to maintain the desired temperature.
If the water temperature in a BWR exceeds the recommended range, the reactor's safety systems will automatically shut it down. This is to prevent any damage to the reactor or potential safety hazards. The shutdown process is known as a "scram" and is a normal safety feature in nuclear reactors.