Patent Number: 051065711
Section: description

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENT Referring to FIG. 1, there is shown, generally at 10, relevant portions of a nuclear reactor system in accordance with the invention. A pressure vessel 12 is disposed within a containment building 14 (only part of which is shown. Containment building 14 is conventionally formed of reinforced concrete or structural steel having a strength sufficient to withstand expected values of pressure encountered therein. As is conventional, pressure vessel 12 contains a quantity of water which is converted to steam, either directly or through an intermediate steam generator, by heat of nuclear fission produced by a plurality of fuel rods (not shown). Modulator vanes (also not shown) are moved in and out of the fuel rods in pressure vessel 12 as necessary to control the production of heat and thus the amount of steam that is generated. Steam exits pressure vessel 12 (or an intermediate steam generator) on one or more main steam lines 16 to a steam turbine-generator (not shown). A drywell 18 surrounds pressure vessel 12 for containment of liquid and/or steam in case of a rupture of nuclear components such as, for example, pressure vessel 12 or main steam line 16. A safety relief valve 20 is connected from main steam line 16 to a sealed annular suppression pool 22 containing a quantity of water 24. A substantial air space 26 remains free above the surface of water 24 to provide a compressible medium in suppression pool 22, whereby steam can be admitted to suppression pool 22 and additional water condensed from such steam can be accommodated. An outlet tube 28, connected to safety relief valve 20, passes into water 24, whereby the pressure in air space 26 remains lower than the pressure in outlet tube 28 by the amount of hydraulic head produced by the submerged portion of outlet tube 28. A vacuum breaker valve 30 is a check valve permitting outward flow from suppression pool 22 to drywell 18 under certain conditions to be detailed hereinafter. A depressurization valve 32, connected to main steam line 16, opens to drywell 18. A gravity driven cooling system pool 34 includes a supply of water 36 sufficient to flood pressure vessel 12 to a depth substantially above the upper ends of all fuel rods in pressure vessel 12. A coolant control valve 38 controls flow of the water from gravity driven cooling system pool 34 to pressure vessel 12. Coolant control valve 38 is closed during normal operation. An equalizing line 54 connects a pool of water, in this case suppression pool 22, to pressure vessel 12. A valve 56 is in equalizing line 54. A check valve 58 is normally closed to prevent water from pressure vessel 12 or water 36 from flowing into suppression pool 22. Valve 56 may be operated at the same time as coolant control valve 38. Equalizing line 54 provides coolant from suppression pool 22 to pressure vessel 12 and keeps the reactor core covered if gravity driven cooling system pool 34 is emptied. The level of water 24 in suppression pool 22 is sufficient to keep the reactor core in pressure vessel 12 covered to the depth required for cooling for an infinite period because any water released from pressure vessel 12 into drywell 18 automatically drains back into water 24 after the lower portions of drywell 18 are flooded. An isolation condenser 40 is connected near the top of pressure vessel 12 through an isolation line 42 and an isolation valve 44. An isolation return line 46, with an isolation valve 47, is connected from a return, or condensate, side of isolation condenser 40 to a position near the bottom of pressure vessel 12. Isolation condenser 40 is submerged in an isolation pool 48 containing a large quantity of water 50. Isolation pool 48 is open to the atmosphere, as indicated by a stack 52. During normal operation, safety relief valve 20, depressurization valve 32, coolant control valve 38 and isolation valve 44 or isolation valve 47 are closed. Steam generated in pressure vessel 12 passes through main steam line 16 to steam turbines (not shown). Conventional equipment condenses the used steam and returns it to pressure vessel 12 for reuse. The water and steam in pressure vessel 12 may be radioactive and thus must not be released to the atmosphere during any foreseeable emergency. In the event of a loss of coolant in pressure vessel 12, or a break in main steam line 16, safety relief valve 20 is opened to permit the flow of existing steam through outlet tube 28 and into water 24 in suppression pool 22. Water 24 is initially at a temperature of about 100 degrees F. As the steam enters water 24 it condenses, thereby lowering the steam pressure in main steam line 16 and pressure vessel 12 and raising the temperature of water 24. While this continues, normal reactor controls are actuated to reduce the amount of heat generated in pressure vessel 12. By the time the temperature of water 24 is raised to about 120 degrees F, the pressure in pressure vessel 12 has been reduced sufficiently that the pressure head produced by the elevated position of gravity driven cooling system pool 34 is greater than the pressure in pressure vessel 12. Depressurization valve 32 is opened as a further means to vent main steam line 16 into drywell 18, and coolant control valve 38 is opened to permit water 36 from gravity driven cooling system pool 34 to pass into pressure vessel 12, whereby all fuel rods are submerged in water. Isolation valves 44 and 47 are opened to permit steam to flow from pressure vessel 12 into isolation condenser 40, wherein it is condensed to water, and returned on isolation return line 46 to pressure vessel 12. The heat is transferred from isolation condenser 40 to water 50, which is permitted to boil. Sufficient water 50 is contained in isolation pool 48 to absorb steam generated by decay heat from fuel rods in pressure vessel 12 for about 78 hours without replenishment. Water 50 is isolated from contamination by water and steam inside isolation condenser 40. Thus, water 50 can be replenished as necessary from any normal supply without the complicating problem of water contamination. A chamber 60 in isolation return line 46 collects condensate which is returned to pressure vessel 12 through isolation return line 46 and isolation valve 47. Chamber 60 also collects any non condensable gasses being discharged from isolation condenser 40 and permits them to be vented through a vent line 62 and a vent valve 64 to suppression pool 22. Venting the non condensable gasses permits continued removal of the reactor decay heat by isolation condenser 40 for all phases of an accident, particularly after cooling of drywell 18 and suppression pool 22 begin. It is also possible to route vent line 62 to other regions of containment building 14, using a fan (not shown) if necessary. Vent valve 64 is normally closed and is only opened when isolation condenser 40 is removing decay heat from containment building 14 after a break in main steam line 16, or similar loss of cooling for pressure vessel 12. The opening of depressurization valve 32 raises the pressure in drywell 18 to a value about equal to that in pressure vessel 12. As the cooling produced by isolation valves 44 and 46 progresses, the pressure within pressure vessel 12 drops below that in drywell 18. Steam then flows into depressurization valve 32 from drywell 18, and thence to isolation condenser 40 where it condenses. As the pressure in drywell 18 decreases even further, it eventually, attains a value below that in air space 26. When this difference exceeds the head produced by submergence of outlet tube 28 in water 24, vacuum breaker valve 30 opens to vent air space 26 to drywell 18. It is foreseen that, in certain installations, the full task of removing heat from containment building 14 may be accomplished using isolation condenser 40. In such an installation, suppression pool 22, and its associated elements, may be omitted. The foregoing description has used a simplified apparatus in one configuration for convenience of description. For example, a commercial nuclear reactor system may employ two or more main steam lines 16 with appropriate valves and controls. Also, only a single isolation condenser 40 is shown submerged in water 50. It appears preferable to employ more than one isolation condenser 40 submerged in the same, or in different pools of water 50. In the preferred embodiment, four isolation condensers 40 are disposed in a single large isolation pool 48. Any three isolation condensers 40 are capable of absorbing all of the decay heat from nuclear reactor system 10. Thus, if an equipment problem occurs in one isolation condenser 40, the remaining three isolation condensers 40 are capable of completing the job. A further embodiment, which is considered to fall within the scope of the invention, includes a nuclear reactor that uses nuclear heat to heat water and produce steam in a second loop via a steam generator. This nuclear reactor may use an isolation condenser that initially transfer heat from the reactor liquid to the outside pool without steaming. Following initial depressurization or blowdown following an event, the reactor produces steam that is directed to the isolation condenser using appropriate flow paths which would be well understood by one skilled in the art. Such an embodiment of the invention may exist without the specific containment configuration shown and described in the foregoing. The term isolation condenser is used herein to describe a heat exchanger that receives a heated fluid such as liquid, steam or a combination thereof, from the nuclear reactor and transfers heat through a set of tubes to a pool of water outside the containment boundary to the atmosphere. Passive heat removal can be extended indefinitely by increasing the capacity of isolation pool 48, or by condensing steam produced in isolation pool 48 and returning the condensate to water 50. The invention described herein is applicable to all types of light water cooled nuclear facilities. Having described preferred embodiments of the invention with reference to the accompanying drawings, it is to be understood that the invention is not limited to those precise embodiments, and that various changes and modifications may be effected therein by one skilled in the art without departing from the scope or spirit of the invention as defined in the appended claims.