Patent Number: 051788217
Section: claims

1. A boiling water nuclear fission reactor having a standby supply of coolant water for submerging the heat producing fissionable fuel core of the reactor during any periods of inadvertent loss of coolant accidents, consisting essentially of the combination of: a nuclear reactor pressure vessel having an inlet for supplying circulating coolant feedwater, and an outlet for steam discharge therefrom;  a core of fissionable fuel for producing heat to generate steam from coolant water located centrally in a lower region of the reactor pressure vessel and spaced inward therefrom, said fuel core normally being submerged in circulating coolant water; an open ended cylindrical shroud encircling the fuel core and extending a distance both above and below the fuel core to provide a core upper plenum area above the fuel core and a core lower plenum area below the fuel core, said cylindrical shroud being spaced inward away from the reactor pressure vessel to provide an annular area for a coolant flow path between the inside of the pressure vessel and the outside of the open ended cylindrical core shroud whereby coolant feedwater supplied by the vessel inlet along with recirculating liquid water coolant can flow downward from the upper region of the reactor pressure vessel about the exterior of the fuel core surrounding shroud and then around the shroud bottom and back upward through the heat producing fuel core for submerging same and absorbing heat energy to cool the fuel core and generate steam for discharge from the vessel outlet to perform work; and at least one elongated chamber having an open lower end and closed upper end provided with a bleed vent for venting gaseous contents out from the chamber, positioned generally vertically within the annular area between the reactor pressure vessel and shroud surrounding the fuel core, whereby the chamber can fill from the circulating coolant water and contain liquid coolant water during normal reactor operation and upon the inadvertent occurrence of a reduced level of liquid water coolant for submerging the fuel core due to a loss of coolant accident resulting in a depressurization of the reactor, steam is flashed within the liquid contents in the chamber which forces the contained coolant water from the chamber into the reactor vessel about the fuel core to augment cooling of the same.  at least one elongated tubular chamber having an open lower end and closed upper end provided with a bleed vent for venting gaseous contents out from the tubular chamber, positioned generally vertically within the annular area between the reactor pressure vessel and shroud surrounding the fuel core and extending from above to below the position of the fuel core, whereby the chamber can fill and contain liquid water coolant during normal reactor operation and upon the inadvertent occurrence of a reduced level of liquid coolant water for submerging the fuel core due to a lose of coolant accident resulting in a depressurization of the reactor, steam thereby is flashed within the liquid contents in the tubular chamber which forces the contained coolant water from the open lower end of the tubular chamber out into the reactor vessel about the fuel core to augment cooling of the same.  a nuclear reactor pressure vessel having an inlet for supplying circulating coolant feedwater into the reactor pressure vessel and to a fuel core therein and an outlet for steam discharge therefrom;  a core fissionable fuel for producing heat to generate steam from coolant water located centrally in a low region of the reactor pressure vessel and spaced inward therefrom, said fuel core normally being submerge din circulating coolant water; an open ended cylindrical shroud encircling the fuel core and extending a distance both above and below the fuel core to provide a core upper plenum area above the fuel core and a core lower plenum area below the fuel core, said cylindrical shroud being spaced inward away from the reactor pressure vessel to provide an annular area for a coolant flow path between the inside of the pressure vessel and the outside of the open ended cylindrical core shroud whereby coolant feedwater supplied by the vessel inlet along with recirculating liquid water coolant can flow downward from the upper region of the reactor pressure vessel about the exterior of the fuel core surrounding shroud and then around the shroud bottom and back upward through the heat producing fuel core for submerging same and absorbing heat energy to cool the fuel core and generate steam for discharge from the vessel outlet to perform work; and a generally vertical elongated chamber of annular cross sectional configuration having an open lower end and closed upper end provided with a bleed vent for venting gaseous contents out from the annular chamber, positioned generally vertically within the annular area between the reactor pressure vessel and the shroud encircling around the shroud surrounding the fuel core and extending therein from above to below the position of the fuel core, whereby the chamber can fill and contain liquid coolant water during normal reactor operation and upon the inadvertent occurrence of a reduced level of liquid coolant water for submerging the fuel core due to a loss of coolant accident causing a depressurization of the reactor, steam is flashed within the liquid contents in the annular chamber forcing the contained coolant water from the chamber into the reactor vessel about the fuel core to augment cooling of the 2. The boiling water nuclear reactor of claim 1, wherein a multiplicity of generally vertical elongated chambers are positioned in a spaced apart array around the annular area between the reactor pressure vessel and the shroud surrounding the fuel core. 3. The boiling water nuclear fission reactor of claim 1, where the generally vertical elongated chamber is tubular in configuration. 4. The boiling water nuclear fission reactor of claim 1, wherein the generally vertical elongated chamber is annular in configuration encircling around the shroud surrounding the fuel core within the annular area between the reactor pressure vessel and the shroud. 5. A boiling water nuclear fission reactor having a standby supply of coolant water for submerging the heat producing core of fissionable fuel of the reactor during any periods of inadvertent loss of coolant accidents, consisting essentially of the combination of: a nuclear reactor pressure vessel having an inlet for supplying circulating coolant feedwater into the reactor pressure vessel and to a fuel core therein and an outlet for steam discharge therefrom; a core of fissionable fuel for producing heat to generate steam from coolant water located centrally in a lower region of the reactor pressure vessel and spaced inward therefrom, said fuel core normally being submerged in circulating coolant water; an open ended cylindrical shroud encircling the fuel core and extending a distance both above and below the fuel core to provide a core upper plenum area above the fuel core and a corer lower plenum area below the fuel core, said cylindrical shroud being spaced inward away from the reactor pressure vessel to provide an annular area for a coolant flow path between the inside of the pressure vessel and the outside of the open ended cylindrical core shroud whereby coolant feedwater supplied by the vessel inlet along with recirculating liquid water coolant can flow downward from the upper region of the reactor pressure vessel about the exterior of the fuel core surrounding shroud and then around the shroud bottom and back upward through the heat producing fuel core for submerging same and absorbing heat energy to cool the fuel core and generate steam for discharge from the vessel outlet to perform work; and 6. The boiling water nuclear fission reactor of claim 5, wherein a multiplicity of generally vertical elongated tubular chambers are positioned in a spaced apart array around within the annular area between the reactor pressure vessel and the shroud surrounding the fuel core. 7. The boiling water nuclear fission reactor of claim 5, wherein the bleed vent comprises a capillary tube for the venting of any gases from the interior of the elongated tubular chamber. 8. The boiling water nuclear fission reactor of claim 5, wherein the bleed vent in the closed upper end of the elongated tubular chamber is in fluid communicated through a duct with the core upper plenum area whereby any gases from the interior of the elongated tubular chamber are vented therefrom out into the core upper plenum area. 9. The boiling water nuclear fission reactor of claim 5 wherein the bleed vent in the closed upper end of the elongated tubular chamber is in fluid communication through a duct with a source of fluid pressure external to the reactor pressure vessel for forcing contained coolant water from the open lower end of the tubular chamber out into the reactor vessel about the fuel core to augment cooling the same. 10. A boiling water nuclear fission reactor having a standby supply of coolant water for submerging the heat producing core of fissionable fuel of the reactor during any periods of inadvertent loss of coolant accidents, consisting essentially of the combination of: 11. The boiling water nuclear fission reactor of claim 10, wherein the generally vertical chamber of annular cross sectional configuration is adjoined with the reactor pressure vessel which provides a wall portion of the chamber. 12. The boiling water nuclear fission reactor of claim 10, wherein the bleed vent comprises a capillary tube for the venting of any gases from the interior of the annular chamber. 13. The boiling water nuclear fission reactor of claim 10, wherein the bleed vent in the closed upper end of the annular chamber is in fluid communication through a duct with the core upper plenum area whereby any gases from the interior of the annular chamber are vented therefrom out into the core upper plenum area. 14. The boiling water nuclear fission reactor of claim 10, wherein the bleed vent in the closed upper end of the annular chamber is in fluid communication through a duct with a source of fluid pressure external to the reactor pressure vessel for forcing contained coolant water from the open lower end of the annular chamber out into the reactor vessel about the fuel core to augment cooling of the same.