Nuclear power station having a gas-injection device for a coolant
A nuclear power station includes a feedwater/steam circuit having a condensate-purification device and a feedwater pump connected upstream of a reactor pressure vessel. A branch line has a gas-injection device for introducing hydrogen into a coolant to ensure especially low maintenance and repair costs of the gas-injection device and an especially homogeneous distribution of hydrogen produced in the gas-injection device. The branch line branches off from the feedwater/steam circuit directly downstream of the condensate-purification device and discharges into the feedwater/steam circuit directly upstream of the feedwater pump.
1. A nuclear power station, comprising:
a reactor pressure vessel;
a feedwater/steam circuit connected to said reactor pressure vessel;
a condensate-purification device and a feedwater pump connected in said feedwater/steam circuit upstream of said reactor pressure vessel;
a branch line having an inlet branching off from said feedwater/steam circuit directly downstream of said condensate-purification device and an outlet, separate from said inlet, discharging into said feedwater/steam circuit directly upstream of said feedwater pump; and
a gas-injection device connected in said branch line for introducing hydrogen into a coolant.
2. The nuclear power station according to claim 1 , wherein said gas-injection device has an electrolytic unit for decomposition of a partial quantity of water conducted in said gas-injection device into hydrogen and oxygen.
3. The nuclear power station according to claim 2 , wherein said electrolytic unit has a number of diaphragm electrolytic cells.
4. The nuclear power station according to claim 1 , wherein said gas-injection device has a hydrogen side, an oxygen side and a pressure-control unit maintaining a lower pressure on said hydrogen side than on said oxygen side.
5. The nuclear power station according to claim 2 , including an exhaust-gas system for receiving oxygen produced in said electrolytic unit.
6. The nuclear power station according to claim 1 , wherein said reactor pressure vessel is a boiling water reactor pressure vessel.
7. A nuclear power station, comprising:
a reactor pressure vessel;
a feedwater/steam circuit connected to said reactor pressure vessel;
a condensate-purification device having a downstream output and a feedwater pump having an upstream input connected in said feedwater/steam circuit upstream of said reactor pressure vessel; and
a gas-injection device connected via an inlet to said downstream output of said condensate-purification device and via an outlet to said upstream input of said feedwater pump.
8. The nuclear power station according to claim 7 , wherein said gas-injection device has an electrolytic unit for decomposition of a partial quantity of water conducted in said gas-injection device into hydrogen and oxygen.
9. The nuclear power station according to claim 8 , wherein said electrolytic unit has a number of diaphragm electrolytic cells.
10. The nuclear power station according to claim 7 , wherein said gas-injection device has a hydrogen side, an oxygen side and a pressure-control unit maintaining a lower pressure on said hydrogen side than on said oxygen side.
11. The nuclear power station according to claim 8 , including an exhaust-gas system for receiving oxygen produced in said electrolytic unit.
12. The nuclear power station according to claim 7 , wherein said reactor pressure vessel is a boiling water reactor pressure vessel.
13. The nuclear power station according to claim 7 , wherein said gas-injection device is connected to said condensate-purification device and said feedwater pump via a branch line.