Patent Number: 047175320
Section: claims

1. In a pressure control system of a pressurized water nuclear reactor plant, containing a pressurizer, water sprayers, heaters, power operated relief valves, safety valves, and a pressurizer relief tank, containing a liquid coolant, having a sparger therein for release of water and steam from the pressurizer, the improvement wherein said sparger comprises: a primary conduit having a terminus, terminating within the liquid coolant in the pressurizer relief tank, said conduit having orifices therein for discharge of fluid therefrom;  a secondary conduit, attached to said terminus of said primary conduit, having orifices therein for discharge of fluid therefrom; and  valve means through which said primary and secondary conduits communicate, said valve means responsive to a predetermined pressure differential across said valve means between said primary and secondary conduits.  a primary conduit of a first diameter, having orifices therein for discharge of fluid therefrom, having a first total are of flow through said orifices;  a secondary conduit of a second diameter less than said first diameter, having orifices therein for discharge of fluid therefrom, having a second total area of flow through said orifices greater than said first total area of flow, with at least a portion of said orifices being below the level of the orifices of said primary conduit; and  a spring biased valve through which said primary and secondary conduits communicate, said valve responsive to a predetermined pressure differential across said valve between said primary and secondary conduits.  a primary conduit having orifices therein for discharge of fluid therefrom;  a secondary conduit, attached to the terminus of said first conduit, having orifices therein for discharge of fluid therefrom; and  valve means through which said primary and secondary conduits communicate, said valve means responsive to a predetermined pressure differential across said valve means between said primary and secondary conduits. 2. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 1 wherein the orifices in said primary conduit are at a first depth within said liquid coolant, and wherein at least a portion of the orifices in said secondary conduit are at a greater depth. 3. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 2 wherein the total area of flow through the orifices in said secondary conduit is greater than the total area of flow through the orifices in said primary conduit. 4. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 3 wherein the orifices in said secondary conduit are of a diameter greater than the diameter of the orifices in said primary conduit. 5. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 1 wherein said secondary conduit is a bifurcated conduit having two leg portions which extend back towards said primary conduit. 6. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 5 wherein said secondary conduit has a diameter less than the diameter of said primary conduit. 7. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 1 wherein said valve means is a spring biased valve responsive to said predetermined pressure differential. 8. A pressure control system for a pressurized water reactor nuclear plant as defined in claim 7 wherein said spring biased valve is responsive to a pressure differential of about 50 pounds per square inch gauge pressure. 9. In a pressure control system of a pressurized water nuclear reactor plant, containing a pressurized, water sprayers, heaters, power operated relief valves, safety valves, and a pressurizer relief tank, containing a liquid coolant, having a sparger therein for release of water and steam from the pressurizer, the improvement wherein said sparger comprises: 10. A pressure control system for a pressurized water nuclear reactor plant as defined in claim 9 wherein said secondary conduit is a bifurcated conduit having two leg portions which extend back towards said primary conduit. 11. A pressure control system for a pressurized water nuclear reactor plant as defined in claim 10 wherein the orifices in said secondary conduit are of a diameter greater than the diameter of the orifices in said primary conduit. 12. A two stage sparger comprising: 13. A two stage sparger as defined in claim 12 wherein at least a portion of the orifices in said secondary conduit are below the horizontal level of the orifices in said primary conduit. 14. A two stage sparger as defined in claim 13 wherein the total area of flow through the orifices in said secondary conduit is greater than the total area of flow through the orifices in said primary conduit. 15. A two stage sparger as defined in claim 14 wherein the orifices in said secondary conduit are of a diameter greater than the diameter of the orifices in said primary conduit. 16. A two stage sparger as defined in claim 12 wherein said secondary conduit is a bifurcated conduit having two leg portions which extend back towards said primary conduit. 17. A two stage sparger as defined in claim 16 wherein said secondary conduit has a diameter less than the diameter of said primary conduit. 18. A two stage sparger as defined in claim 12 wherein said valve means is a spring biased valve responsive to said predetermined differential.