Patent Number: 054266815
Section: claims

1. A boiling water reactor comprising: a primary containment vessel;  a reactor pressure vessel surrounded by said primary containment vessel;  a nuclear fuel core arranged inside said reactor pressure vessel;  a pool of water located inside said primary containment vessel and outside said reactor pressure vessel;  a condenser pool of water located outside and above said primary containment vessel;  a residual heat removal condenser submerged in said condenser pool and having an input and an output;  a first flowpath from said reactor pressure vessel to said input of said residual heat removal condenser;  a release valve placed in said first flowpath for selectively opening said first flowpath to the flow of steam from said reactor pressure vessel to said residual heat removal condenser, said release valve being designed to constrict the flow of high-pressure steam from said reactor pressure vessel to said residual heat removal condenser; and  a second flowpath for carrying condensed steam from said residual heat removal condenser to said pool located inside said primary containment vessel, said second flowpath having an output submerged in said pool located inside said primary containment,  wherein the operating pressure of said residual heat removal condenser is maintained in the range of 100-200 psi.  a primary containment vessel;  a reactor pressure vessel surrounded by said primary containment vessel;  a nuclear fuel core arranged inside said reactor pressure vessel;  a suppression pool of water located inside said primary containment vessel and outside said reactor pressure vessel;  a gravity-driven cooling system pool of water located inside said primary containment vessel and outside said reactor pressure vessel at an elevation above said nuclear fuel core;  a condenser pool of water located outside and above said primary containment vessel;  a residual heat removal condenser submerged in said condenser pool and having an input which is not in flow communication with the interior of said primary containment vessel;  a first flowpath from said reactor pressure vessel to said input of said residual heat removal condenser;  a release valve placed in said first flowpath for selectively opening said first flowpath to the flow of steam from said reactor pressure vessel to said residual heat removal condenser, said release valve being designed to constrict the flow of high-pressure steam from said reactor pressure vessel to said residual heat removal condenser; and  a second flowpath for carrying condensed steam from said residual heat removal condenser to said gravity-driven cooling system pool,  wherein the operating pressure of said residual heat removal condenser is maintained in the range of 100-200 psi.  a fourth flowpath for carrying water from said suppression pool to said reactor pressure vessel;  a fifth flowpath for carrying fluid from an ultimate heat sink external to said primary containment vessel and back to the ultimate heat sink;  means for conducting heat from said water flowing along said fourth flowpath to said fluid flowing along said fifth flowpath; and  a pump for pumping water from said suppression pool along said fourth flowpath.  a primary containment vessel;  a reactor pressure vessel surrounded by said primary containment vessel;  a nuclear fuel core arranged inside said reactor pressure vessel;  a pool of water located inside said primary containment vessel and outside said reactor pressure vessel;  a condenser pool of water located outside and above said primary containment vessel;  a residual heat removal condenser submerged in said condenser pool and having an input and an output;  a first flowpath from said reactor pressure vessel to said input of said residual heat removal condenser;  a release valve placed in said first flowpath for selectively opening said first flowpath to the flow of steam from said reactor pressure vessel to said residual heat removal condenser;  means for constricting the flow of high-pressure steam from said reactor pressure vessel to said residual heat removal condenser; and  a second flowpath for carrying condensed steam from said residual heat removal condenser to said pool located inside said primary containment vessel, said second flowpath having an output submerged in said pool located inside said primary containment,  wherein the operating pressure of said residual heat removal condenser is maintained in the range of 100-200 psi. 2. The boiling water reactor as defined in claim 1, wherein said first flowpath comprises a portion of a main steam line from said reactor pressure vessel. 3. The boiling water reactor as defined in claim 1, wherein said pool located inside said primary containment vessel is a gravity-driven cooling system pool of water located at an elevation above said nuclear fuel core. 4. A boiling water reactor comprising: 5. The boiling water reactor as defined in claim 4, wherein said first flowpath comprises a portion of a main steam line from said reactor pressure vessel. 6. The boiling water reactor as defined in claim 4, further comprising a third flowpath for carrying noncondensed gases from said residual heat removal condenser to said suppression pool. 7. The boiling water reactor as defined in claim 6, further comprising a pump for pumping water from said suppression pool to said reactor pressure vessel. 8. The boiling water reactor as defined in claim 6, further comprising: 9. A boiling water reactor comprising: 10. The boiling water reactor as defined in claim 9, wherein said constricting means is incorporated in said release valve. 11. The boiling water reactor as defined in claim 9, wherein said first flowpath comprises a portion of a main steam line from said reactor pressure vessel. 12. The boiling water reactor as defined in claim 9, wherein said pool located inside said primary containment vessel is a gravity-driven cooling system pool of water located at an elevation above said nuclear fuel core.