US2005050892A1PendingUtilityA1

Gravity condensate and coolant pressurizing system

Priority: Sep 8, 2003Filed: Sep 8, 2003Published: Mar 10, 2005
Est. expirySep 8, 2023(expired)· nominal 20-yr term from priority
Inventors:Len Gould
F01K 13/00
11
PatentIndex Score
0
Cited by
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References
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Claims

Abstract

This invention is an improved method of installing the main subsystems of any Rankine Cycle thermal electric power generating station to reduce the capital cost of constructing the plant, to increase the overall safety of a nuclear reactor installation, and to improve the efficiency and safety of such a power plant. This invention achieves a reduction of the amount of complex and redundant machinery required for operation, and an increase of the withstand pressure of the containment of a nuclear reactor; by installing the primary thermal power source and vapour generators at a significant elevation below the condenser.

Claims

exact text as granted — not AI-modified
1 ) A Rankine cycle electrical generating plant having a significant vertical separation of the turbine condenser above the vapor generator to enable gravity to provide all or a significant part of the working fluid pressure required to supply condensed liquid working fluid to the vapor generator system.  
   
   
       2 ) A Rankine cycle electrical generating plant as in  claim 1  where the said vertical separation is provided in whole or in part by surface terrain, either natural or artificial.  
   
   
       3 ) A Rankine cycle electrical generating plant as in  claim 1  where the said vertical separation is provided in whole or in part by an underground excavation or a natural cavern.  
   
   
       4 ) A Rankine cycle electrical generating plant as in  claim 1  where the said vertical separation is provided in whole or in part by a structure rising above local surface elevation.  
   
   
       5 ) A passive primary or secondary emergency cooling system for a nuclear reactor as in  claim 2  which exploits the said vertical separation of  claim 2  to allow gravity to pressurize a heat exchanger system within or in thermally conductive contact with a reactor containment vessel 
 from a large reservoir of emergency coolant;    said reservoir located at a significant elevation above the reactor/steam generator installation and having the coolant return as either liquid or vapour by a sealed pipe system to an emergency condenser and capture system installed near the coolant reservoir level.    
   
   
       6 ) A passive primary or secondary emergency cooling system for a nuclear reactor as in  claim 3  which exploits the said vertical separation of  claim 3  to allow gravity to pressurize a heat exchanger system within or in thermally conductive contact with a reactor containment vessel 
 from a large reservoir of emergency coolant;    said reservoir located at a significant elevation above the reactor/steam generator installation and having the coolant return as either liquid or vapour by a sealed pipe system to an emergency condenser and capture system installed near the coolant reservoir level.    
   
   
       7 ) A containment of a nuclear reactor having the containment functionality enhanced by being installed in a sealable excavation deep underground below the condenser system, with said containment excavation being designed to exploit the mass of the large vertical column of rock and earth above it to increase its capacity for containing pressure and therefore contaminants in the event of an emergency and to resist breaching for any reason of the containment.  
   
   
       8 ) A passive emergency cooling system for a nuclear reactor as in  claim 2  or  claim 3  which employs the said vertical separation of  claim 2  or  claim 3  to allow gravity to pressurize an isolated passive emergency high pressure cooling heat exchanger system installed near the level of the reactor and thermally connected to the reactor primary circuit, from a sufficient reservoir of emergency cooling water located at a significant elevation above the reactor installation and having the coolant return as vapour by a sealed pipe system to an emergency condenser and capture system installed at the coolant reservoir level.  
   
   
       9 ) A passive emergency cooling system for a CANDU heavy water nuclear reactor as in  claim 2  or  claim 3  which employs the said vertical separation of  claim 2  or  claim 3  to allow gravity to pressurize an isolated passive emergency high pressure cooling heat exchanger system installed near the level of the reactor and thermally connected to the reactor moderator fluid, from a sufficient reservoir of emergency cooling water located at a significant elevation above the reactor installation and having the coolant return as vapour by a sealed pipe system to an emergency condenser and capture system installed at the coolant reservoir level.

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