Patent Number: 048308153
Section: claims

1. In a decay heat removal system for a nuclear boiling water reactor, a cooling apparatus comprising: an isolation condenser shell; and  a heat exchange loop transpiercing said shell and sized for shutdown cooling duty,  said cooling apparatus connected to said nuclear boiling water reactor and to additional heat exchange loops to provide both isolation cooling and shutdown cooling for said nuclear boiling water reactor.  a nuclear boiling water reactor having a controlled reactor core for heating feedwater to generate steam;  a turbine-generator for receiving steam and generating electric power;  a condenser feedwater system for receiving spent steam, producing condensate, and injecting feedwater back into said reactor;  an isolation cooling system for condensing steam from said reactor independent of said turbine-generator and for dissipating the energy of said steam during controlled shutdown of said reactor; and  a shutdown cooling system for maintaining the water in said boiling water reactor at a temperature permitting refueling of said reactor;  a combined isolation and shutdown cooling system comprising in combination:  an isolation condenser shell, said shell containing nonradioactive coolant;  a heat exchange loop transpiercing said shell, said loop including means for admitting steam shunted from said reactor independent of said turbine-generator to exchange heat by condensing said reactor steam while boiling said nonradioactive coolant in said condenser shell;  a steam vent in said condenser shell for venting boiling nonradioactive coolant to atmosphere; and  means for connecting said shutdown cooling system to said heat exchange loop during shutdown of said reactor.  providing a condenser cooling shell;  filling said condenser cooling shell with nonradioactive coolant;  providing a heat exchange loop transpiercing said shell for effecting heat exchange with said nonradioactive coolant;  connecting said loop in a shunt independent of said turbine-generator during emergency shutdown of said reactor to dissipate heat from said steam and said reactor coolant; and  venting said nonradioactive coolant to atmosphere when said nonradioactive coolant is heated to boiling.  a nuclear boiling water reactor having a reactor core for heating feedwater to generate a two-phase steam/water mixture and a steam separator for classifying said steam from said water;  a turbine-generator for receiving said steam to generate electric power;  a power grid for receiving electric power from said turbine-generator; and  means for isolating said reactor from said turbine-generator during shutdown of said reactor core;  an improved cooling system for dissipating heat generated by said shutdown reactor core comprising;  a cooling apparatus, said apparatus including a housing containing water coolant and a plurality of heat exchange surfaces immersed in said water coolant;  means for circulating steam from said reactor through said surfaces to remove heat from said steam when said reactor core is shutdown;  means for circulating condensed steam from said surfaces back into said reactor when said reactor core is shutdown;  means for circulating said reactor coolant from said reactor through said surfaces to remove heat from said reactor coolant when said reactor core is shutdown;  means for circulating cooled reactor coolant from said surfaces back into said reactor when said reactor core is shutdown;  means for venting said nonradioactive water coolant from said housing into the atmosphere when said nonradioactive water coolant is boiled to steam; and  means for circulating said nonradioactive water coolant from said apparatus through a secondary heat exchange loop to dissipate sufficient heat from said reactor coolant so that said reactor can be refueled. 2. In a boiling water nuclear power generating system including: 3. A process for cooling a nuclear boiling water reactor, said reactor having a reactor core for heating reactor coolant to generate steam, a turbine-generator for receiving said steam and generating electric power, and a feedwater system for receiving spent steam and providing feedwater back into said reactor, said process comprising: 4. In a nuclear power generating system of the type including: 5. The power generating system of claim 4 and wherein said nonradioactive water coolant is circulated through said secondary heat exchange loop to dissipate additional heat from said steam.