Self-contained emergency spent nuclear fuel pool cooling system
View Patent ↗An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required.
1. A spent nuclear fuel pool at least partially filled with a liquid comprising water, the spent fuel pool including:
a cooling conduit directly immersed within the liquid within the spent fuel pool in direct heat exchange relationship with the liquid and having an interior of the cooling conduit isolated from the liquid within the spent nuclear fuel pool;
a coolant fluid reservoir remote from the spent fuel pool connected to the cooling conduit by a coupling line through which a coolant can be circulated from the coolant fluid reservoir through the cooling conduit and out to a receiving pond;
a circulating mechanism for circulating the coolant through the coupling line, the circulating mechanism being configured to be normally in an off state in which the coolant is not circulated through the coupling line;
a sensor for monitoring a condition of the liquid within the spent fuel pool and providing a sensor output indicative of the condition;
a control system connected to the sensor output and the circulating mechanism and operable to turn on the circulating mechanism when the sensor output indicates the liquid in the spent fuel pool has reached a preselected condition indicative of an abnormal state of the condition; and
including a plurality of the cooling conduits respectively connected to the coolant fluid reservoir through a corresponding coupling line in parallel.
2. The spent nuclear fuel pool of claim 1 wherein the circulating mechanism is a pump powered by either a primary or an auxiliary power source.
3. The spent nuclear fuel pool of claim 2 wherein the auxiliary power source is a motor-generator.
4. The spent nuclear fuel pool of claim 2 wherein the pump is a diesel or gasoline driven pump.
5. The spent nuclear fuel pool of claim 4 wherein the diesel or gasoline driven pump is a fire truck.
6. The spent nuclear fuel pool of claim 2 wherein the auxiliary power source is dedicated to running just the pump.
7. The spent nuclear fuel pool of claim 6 wherein the auxiliary power source is a battery.
8. The spent nuclear fuel pool of claim 1 wherein the circulating mechanism is an active mechanism that is only activated when the liquid within the spent fuel pool rises above a preselected temperature.
9. The spent nuclear fuel pool of claim 1 wherein the cooling conduit is a cooling coil.
10. The spent nuclear fuel pool of claim 1 wherein the cooling conduit comprises a plurality of cooling conduits connecting in parallel to the coupling line.
11. The spent nuclear fuel pool of claim 10 wherein the cooling conduit is a plurality of cooling coils.
12. The spent nuclear fuel pool of claim 1 wherein the coolant is seawater.
13. The spent nuclear fuel pool of claim 1 wherein the receiving pond includes a cooling tower.
14. The spent nuclear fuel pool of claim 1 wherein the cooling conduit is constructed from a copper-nickel alloy selected from the group 90/10, 70/30 or Monel.
15. The spent nuclear fuel pool of claim 1 wherein the circulating mechanism is an active mechanism configured so that it is only activated when the liquid within the spent fuel pool reaches a preselected level.
16. The spent nuclear fuel pool of claim 1 wherein the coolant reservoir includes a plurality of coolant sources and at least some of the coupling lines are connected to separate ones of the coolant sources.
17. The spent nuclear fuel pool of claim 1 wherein at least some of the cooling conduits have circulating mechanisms that are independent of others of the cooling conduits.