Patent Number: 058964312
Section: claims

1. A condensing system for a vacuum breaker of a nuclear reactor, said system configured to couple to the vacuum breaker, said system comprising: a steam inlet pipe, said steam inlet pipe comprising a loop seal between a first end and a second end; and  a condenser, said condenser positioned proximate said steam inlet pipe and configured to substantially condense steam flowing through said steam inlet pipe.  a wetwell;  a drywell;  a vacuum breaker coupling said wetwell to said drywell; and  a condensing system coupled to said vacuum breaker, said condensing system comprising:  coupling the steam inlet pipe to the vacuum breaker;  positioning the condenser proximate the steam inlet pipe; and  coupling the condenser to the pool of water. 2. A condensing system in accordance with claim 1 wherein the nuclear reactor includes a wetwell, and wherein said condenser is positioned in the wetwell. 3. A condensing system in accordance with claim 1 wherein the nuclear reactor includes a drywell, and wherein said condenser is positioned in the drywell. 4. A condensing system in accordance with claim 1 wherein the reactor includes a pool of water, and wherein said condenser is coupled to the pool of water. 5. A nuclear reactor comprising: 6. A nuclear reactor in accordance with claim 5 wherein said condenser is positioned in said wetwell. 7. A nuclear reactor in accordance with claim 5 wherein said condenser is positioned in said drywell. 8. A nuclear reactor in accordance with claim 5 further comprising a pool of water, wherein said condenser is coupled to said pool of water. 9. A nuclear reactor in accordance with claim 8 wherein said pool of water comprises a Gravity Driven Cooling System pool. 10. A nuclear reactor in accordance with claim 8 wherein said pool of water comprises a passive cooling containment system pool. 11. A nuclear reactor in accordance with claim 5 wherein said steam inlet pipe comprises a first end, a second end, and a loop seal between said first end and said second end, said second end coupled to said vacuum breaker, said first end positioned in said drywell. 12. A nuclear reactor in accordance with claim 5 further comprising a wall separating said wetwell from said drywell, said wall having a spill-over-hole therein, said spill-over-hole spaced from a floor of said drywell, said steam inlet pipe first end positioned above said spill-over-hole. 13. A method for preventing steam from flowing from a drywell to a wetwell in a nuclear reactor utilizing a condensing system, the nuclear reactor including a vacuum breaker and a pool of water, the vacuum breaker coupling the drywell to the wetwell, the condensing system including a steam inlet pipe and a condenser, said method comprising the steps of: 14. A method in accordance with claim 13 wherein the steam inlet pipe includes a first end, a second end, and a loop seal between the first end and the second end, and wherein coupling the steam inlet pipe to the vacuum breaker comprises the step of coupling the second end of the steam inlet pipe to the vacuum breaker so that the first end is positioned adjacent the drywell. 15. A method in accordance with claim 13 further comprising the step of positioning the condenser in the drywell. 16. A method in accordance with claim 13 further comprising the step of positioning the condenser in the wetwell.