Patent Number: 053032748
Section: claims

1. In a nuclear reactor system which includes a containment structure having an upper drywell space and a lower wetwell space, the said spaces being separated one from the other by an intervening floor member,  a nuclear reactor pressure vessel disposed in the drywell space, there being a reactor core within said pressure vessel,  a suppression pool of water confined in the wetwell space, there being a gas space above a normal level of the water in the suppression pool, and  means for venting a heated and pressurized fluid present in said structure drywell space incident a pressure vessel loss-of-coolant accident to a submerged location in said suppression pool thereby to remove heat from and reduce pressure in the drywell space by condensing a water fraction of said heated fluid in said suppression pool water, a non-condensable fraction of said heated fluid venting to the wetwell gas space,  satellite heat removal means operable for effecting additional drywell heat removal during such accident and all drywell venting in the event the floor member structure is breached by a core meltdown during the loss-of-coolant accident with consequent merger of the gas space and drywell so that the containment lacks a space to which the heated fluid non-condensable fraction can vent, said satellite heat removal means comprising  a satellite structure external of said containment and set adjacent said containment structure, said satellite having upper and lower chambers,  at least one heat exchanger in said upper chamber,  a pool of cooling water in said upper chamber surrounding said heat exchanger,  vent means communicating the cooling water pool with an ambient environment,  an inlet conduit communicating an inlet end of the heat exchanger with the containment drywell whereby heated fluid present in the containment drywell can flow into the heat exchanger and be cooled to condense a water fraction therefrom,  an outlet conduit communicating an outlet end of the heat exchanger with the containment drywell,  a condensate/non-condensable gas collector in said outlet conduit, condensate collected in the collector passing therefrom to the containment drywell, a non-condensable gas fraction collected in the collector passing into a vent pipe, and  a pool of water in said lower chamber, there being a gas space in said lower chamber above a level of the water pool therein, the vent pipe having an outlet end submerged below said water pool level. 2. The nuclear system of claim 1 in which the volume of the lower chamber water pool in the satellite structure is at least about the same as the volume of water present in the containment structure suppression pool. 3. The nuclear system of claim 1 in which the gas space in the lower chamber of the satellite structure is at least as large as that above the suppression pool in the containment structure wetwell. 4. The nuclear system of claim 3 in which the satellite structure lower chamber gas space is about 2 to about 3 times larger than that in the containment wetwell space. 5. The nuclear system of claim 1 in which the vent pipe extends down from the satellite upper chamber and through the gas space above the satellite lower chamber water pool, and a vacuum breaker carried in said vent pipe at a location in lower chamber gas space and operable to admit gas from the said gas space into the vent pipe whenever a reduced pressure condition in the drywell is such that would induce a siphon draw of water from said lower chamber pool of water to the containment drywell via the heat exchanger. 6. The nuclear system of claim 1 in which the inlet and outlet conduits which communicate the heat exchanger with the containment drywell each have a conduit end present in the containment drywell which said conduit ends are situated at an elevation below that at which opposite ends of the respective conduits are situated. 7. The nuclear system of claim 1 comprising a normally open valve disposed in at least the inlet conduit. 8. The nuclear system of claim 1 in which the inlet and outlet conduits have ends communicating with the containment drywell at locations above any flood level therein to which the liquid in the suppression pool and that in the reactor pressure vessel could rise during loss-of-coolant accident.