CA2012245A1 - Passive cooling system for nuclear reactor containment structures - Google Patents
Passive cooling system for nuclear reactor containment structuresInfo
- Publication number
- CA2012245A1 CA2012245A1 CA002012245A CA2012245A CA2012245A1 CA 2012245 A1 CA2012245 A1 CA 2012245A1 CA 002012245 A CA002012245 A CA 002012245A CA 2012245 A CA2012245 A CA 2012245A CA 2012245 A1 CA2012245 A1 CA 2012245A1
- Authority
- CA
- Canada
- Prior art keywords
- closed
- chamber
- container
- cooling
- heat transferring
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Abandoned
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
ABSTRACT
A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the contain-ment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.
A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the contain-ment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.
Description
' ~0~2Z45 PASSIVE COOLING SYSTEM FOR
NUCLEAR REACTOR CONTAINMENT STRUCTURES
This invention is related to the invention of ;;~
application for patent Serial No. 294,095, filed January 6, 1989, for Natural Circulating Passive Cooling System for Nuclear Reactor Containment Structure. , FIELD OF THE INVENTION
This invention relates to liquid cooled, nucle-ar fission reactor plant complexes. The invention is particularly concerned with a passive or self-acting cooling system for the containment structure housing a fissionable fuel containing nuclear reactor.
BACXGROU~D OF THE INVENTION
~ Typically nuclear fission reactors for power generation are housed within a containment~istructure as a safety measure. Nuclear reactor containments are designed and employed to enclose the nuclear reactor pressure vessel containing the core of heat generating fissionable fuel and ancillary components ~ ; ~^
of the system, such as portions of the coolant/heat 20 transfer conduits or other means which constitute a f~
~,',~ ~
20122~
NUCLEAR REACTOR CONTAINMENT STRUCTURES
This invention is related to the invention of ;;~
application for patent Serial No. 294,095, filed January 6, 1989, for Natural Circulating Passive Cooling System for Nuclear Reactor Containment Structure. , FIELD OF THE INVENTION
This invention relates to liquid cooled, nucle-ar fission reactor plant complexes. The invention is particularly concerned with a passive or self-acting cooling system for the containment structure housing a fissionable fuel containing nuclear reactor.
BACXGROU~D OF THE INVENTION
~ Typically nuclear fission reactors for power generation are housed within a containment~istructure as a safety measure. Nuclear reactor containments are designed and employed to enclose the nuclear reactor pressure vessel containing the core of heat generating fissionable fuel and ancillary components ~ ; ~^
of the system, such as portions of the coolant/heat 20 transfer conduits or other means which constitute a f~
~,',~ ~
20122~
-2- 24-AT-~5001 source and/or ~eans of conveyance of radiation and/or radioactive fission products. As such, the containment structure housing a nuclear reactor must effectively isolate the reactor system and components enclosed within its confines by sealing in all contents including any water, steam, gases or vapor and entrained fission products or other sources of ;-radiation that may have escaped from the reactor pressure vessel and in particular its associated ~ -cooling system.
The provision of a construction fulfilling such requirements with an effective fluid impermeable confinement structure securely isolating its enclosed contents from the external atmosphere does not ;~
generally present either a significant engineering or construction obstacle or achievement. ~;
However, in the event of certain malfunctions in a nuclear reactor system, such as a loss of coolant, large volumes of very hot pressurized water may be released from the system into the interior of . : . ,.
the containment structure. This very hot pressurized `
water flashes into steam which may carry along : ~ . .::- :. -:
radioactive fission products, and substantially ., . ~ .
increase the pressure and temperature within the containment structure. Such accidents can produce very high pressures and temperatures within the confines of the "leak proof" containment ~
~ ~:
Z012~45 ~
. , structure thereby imposing heavy demands upon its integrity and ability to perform its designed role of retaining all potentially hazardous matter derived from the nuclear reactor system. -Potentially deleterious high pressure due to the inherent high thermal energy and flashing steam cannot simply be released by venting from the ,~
containment or otherwise permitted to escape to the outside atmosphere since the steam vapor may entrain 10 and carry radioactive fission products which would f~
also be released into the environment.
A variety of suppression schemes have been -~
proposed and devised to cope with the problem of excessive pressure. They include a variety of ~: -measures or arrangements for condensing evolving or flashing steam and reducing the resultant over-pressure caused by accidents, for example, the designs disclosed in United States Letters Patent No. 3,713,968; No. 4,362,693; No. 4,473,528; and No. 4,526,743.
In the absence of an effective suppression means to mitigate steam generated high pressures, the enveloping containment structure must be designed and constructed at excessively high costs and maintained ~.: . ;..., ,.. ~ ., to resist and retain inordinately high internal fluid pressures. Nevertheless, even a significantly ~ -~
reinforced containment structure cannot be assured to : ~' ~' ' ' ':
1`,; ,..,.: .`:.:
~ 20~Z4~
The provision of a construction fulfilling such requirements with an effective fluid impermeable confinement structure securely isolating its enclosed contents from the external atmosphere does not ;~
generally present either a significant engineering or construction obstacle or achievement. ~;
However, in the event of certain malfunctions in a nuclear reactor system, such as a loss of coolant, large volumes of very hot pressurized water may be released from the system into the interior of . : . ,.
the containment structure. This very hot pressurized `
water flashes into steam which may carry along : ~ . .::- :. -:
radioactive fission products, and substantially ., . ~ .
increase the pressure and temperature within the containment structure. Such accidents can produce very high pressures and temperatures within the confines of the "leak proof" containment ~
~ ~:
Z012~45 ~
. , structure thereby imposing heavy demands upon its integrity and ability to perform its designed role of retaining all potentially hazardous matter derived from the nuclear reactor system. -Potentially deleterious high pressure due to the inherent high thermal energy and flashing steam cannot simply be released by venting from the ,~
containment or otherwise permitted to escape to the outside atmosphere since the steam vapor may entrain 10 and carry radioactive fission products which would f~
also be released into the environment.
A variety of suppression schemes have been -~
proposed and devised to cope with the problem of excessive pressure. They include a variety of ~: -measures or arrangements for condensing evolving or flashing steam and reducing the resultant over-pressure caused by accidents, for example, the designs disclosed in United States Letters Patent No. 3,713,968; No. 4,362,693; No. 4,473,528; and No. 4,526,743.
In the absence of an effective suppression means to mitigate steam generated high pressures, the enveloping containment structure must be designed and constructed at excessively high costs and maintained ~.: . ;..., ,.. ~ ., to resist and retain inordinately high internal fluid pressures. Nevertheless, even a significantly ~ -~
reinforced containment structure cannot be assured to : ~' ~' ' ' ':
1`,; ,..,.: .`:.:
~ 20~Z4~
be resistant to breaching considering the temperature/pressure potential of a typical power generating nuclear reactor plant.
Under malfunctioning conditions, the decay 5 heat produced by the core of fissionable fuel within the pressure vessel is released into the containment via either a pressure suppression vent system or the pressure vessel safety and depressurization valves.
In conventional reactor assemblies this excess thermal energy is commonly removed by active cooling systems comprising motors, pumps, valves and heat ;~
exchangers. Functioning of these acting components depends upon external power and/or proper operator personnel actions.
SUMMARY OF THE INVENTION
. . -. ~ .
This invention comprises a naturally circulat-ing passive cooling system for the containment ;~
structure of a nuclear fission reactor plant. The cooling system provides means for lowering the temperature of the interior environment of a reactor containment to relieve or preclude over-pressure ;
therein by condensing steam and thus reducing ambient temperatures. The passive cooling system entails a naturally circulating heat transfer mechanism that -additionally permits the safe dissipation of thermal energy out into the environment free of contaminating radioactive fission products.
2C~Z2~
OBJECTS OF THE INVENTION
, .:,,, It is a primary object of this invention to --provide a new and improved containment cooling system for nuclear fission reactor plants. ;
It is also an object of this invention to provide a natural circulating cooling system for nuclear fission reactor containment structures.
It is a further object of this invention to provide functional improvements in a nuclear reactor containment comprising a passive or self-acting cooling system based upon convection heat transfer of fluids. ~ `
It is a still further object of this invention -~
to provide passive pressure suppression system based ~ -upon natural heat convection for containment structures of nuclear reactor plants. `~
It is another object of this invention to ^
provide a cooling system for nuclear fission reactor containment structures which is based upon natural ~ `
circulation for heat transfer.
, . ~ .:. . :.
BRIEF DESCRIPTION OF THE DRAWINGS
Figure 1 is a vertical sectional view of a ~ -,containment structure housing a nuclear reactor plant ; ~ ~ -with part in elevation;
Figure 2 is a detailed, enlarged sectional view of a portion of a suppression pool chamber and overhead cooling pool compartment shown in Figure l;
s", ~ ,"~
; :-:, ... - ;,: '':
~ 20~2;~
Under malfunctioning conditions, the decay 5 heat produced by the core of fissionable fuel within the pressure vessel is released into the containment via either a pressure suppression vent system or the pressure vessel safety and depressurization valves.
In conventional reactor assemblies this excess thermal energy is commonly removed by active cooling systems comprising motors, pumps, valves and heat ;~
exchangers. Functioning of these acting components depends upon external power and/or proper operator personnel actions.
SUMMARY OF THE INVENTION
. . -. ~ .
This invention comprises a naturally circulat-ing passive cooling system for the containment ;~
structure of a nuclear fission reactor plant. The cooling system provides means for lowering the temperature of the interior environment of a reactor containment to relieve or preclude over-pressure ;
therein by condensing steam and thus reducing ambient temperatures. The passive cooling system entails a naturally circulating heat transfer mechanism that -additionally permits the safe dissipation of thermal energy out into the environment free of contaminating radioactive fission products.
2C~Z2~
OBJECTS OF THE INVENTION
, .:,,, It is a primary object of this invention to --provide a new and improved containment cooling system for nuclear fission reactor plants. ;
It is also an object of this invention to provide a natural circulating cooling system for nuclear fission reactor containment structures.
It is a further object of this invention to provide functional improvements in a nuclear reactor containment comprising a passive or self-acting cooling system based upon convection heat transfer of fluids. ~ `
It is a still further object of this invention -~
to provide passive pressure suppression system based ~ -upon natural heat convection for containment structures of nuclear reactor plants. `~
It is another object of this invention to ^
provide a cooling system for nuclear fission reactor containment structures which is based upon natural ~ `
circulation for heat transfer.
, . ~ .:. . :.
BRIEF DESCRIPTION OF THE DRAWINGS
Figure 1 is a vertical sectional view of a ~ -,containment structure housing a nuclear reactor plant ; ~ ~ -with part in elevation;
Figure 2 is a detailed, enlarged sectional view of a portion of a suppression pool chamber and overhead cooling pool compartment shown in Figure l;
s", ~ ,"~
; :-:, ... - ;,: '':
~ 20~2;~
Figure 3 is a detailed, enlarged sectional vlew of a portion of a suppression pool chamber and exterior of the containment housing with a flue-like arrangement to induce air or gas flow to remove heat: and Figure 4 is a detailed, enlarged sectional view of a portion of a suppression pool chamber and exterior of the containment housing adjacent to heat sink such :.-,. ~
as water. ~ -DETAILED DESCRIPTION OF THE INVENTION
Referring to the drawings, in particular Figure 1, a nuclear reactor plant complex 10 comprises the nuclear reactor consisting of a pressure vessel 12 containing a heat producing core of fissionable fuel 14. The fuel gives up its generated heat from fission ;-~
to a surrounding coolant, typically comprising water for either the direct generation of steam as in a ;~ ` `
so-called boiling water reactor, or to function as heat ~ ;
transfer medium for the indirect generation of steam as ~;
in a so-called pressurized water reactor. Coolant circulating pipes 16 and 18 provide for the circulation of coolant water into the reactor pressure vessel 12 for transfer of the heat output of the fuel, and j , :-, , conveyance of the heated water and/or steam from the pressure vessel to its use such as electrical power generation whereupon it recycles through the circuit.
The nuclear reactor comprising its pressure ,, :
vessel 12 with fuel core 14 and certain related ~-201~45 components is enclosed within a containment structure 20. The containment structure 20 includes a fluid impermeable liner 22 on the structure, which includes a base or floor, a vertical side wall(s) and roof which is designed to prevent the escape from the confines of any radioactive material to the outer atmosphere.
In a typical water cooled nuclear reactor plant, the containment structure 20, in addition to the reactor pressure vessel 12 includes a number of cell-like chambers or compartments designed for the performance of specific functions or objectives. For instance, the reactor pressure vessel 12 can be surrounded by one or more adjacent chambers providing 15 a drywell(s) 24 to receive and retain any overflow or ~-: . , - ~.
spillage of water, steam or other vapor resulting ~ -from leakage or other sources in connection with the reactor operation.
One or more chambers partially filled with , 20 water provide a suppression pool(s) 26 for cooling ~`
and condensing steam beneath the surface of water , pool therein. Suppression pool chamber(s) 26 is in fluid communication with one or more drywell chambers -;
24 through conduits 28 which open at one terminal end -~
25 into an upper portion of drywell chamber 24 and at -its other terminal end into the suppression pool chamber 26 at a lower region below the surface of the ;
,~', ', '' '' '"' 20~2245 water pool contained therein. Thus, any steam escaping or flashing from water leaking from the high temperature and pressure confines of the pressure vessel and its connecting circuits will be received in the drywell chamber(s) 24. The inherent pressure of the steam escaping or flashing from emerging hot -~
water will ultimately be forced from the drywell chamber(s) 24 through conduit(s) 28 into the suppression pool chamber(s) 26 at a location beneath the surface of the water pool therein. The submerged contact of the steam with the pool water condenses it and thereby reduces the steam increased pressures within the containment structure 20 initially produced by the leaking steam or flashing from escaping high temperature and pressure water.
In accordance with one version of the invention, one or more compartments containing water comprising a cooling pool(s) 30 is preferably provided overhead and adjacent to the suppression pool chamber~s) 26.
The passive cooling systems of this invention -comprise the application of one or more closed heat :
transferring containers 32, and their utilization in several embodiments. The closed heat transferring containers 32, as employed in this invention, consist of a closed tank-like vessel or receptacle, which may be elongated as a closed section of pipe. Enclosed ::'., ~
. ~ - ' .
20~245 -9- 24-AT-~S001 within this container 32 is a fluid having a boiling : ~
point in an apt temperature range, for example about :
50 to 150C, and a relatively high heat of vapori-zation (or evaporation) such as water. In addition to the foregoing physical properties, the fluid should be chemically innocuous with respect to other components and materials of the overall system, namely the fluid should not chemically attack or be reactive with any component of possible contact.
Referring to Figure 2, one embodiment of the invention comprises at least one closed heat transferring container(s) 32 located in a suppression pool chamber 26, either submerged in the pool, such :
as container 32Al, or above the surface of the pool, such as container 32All. Closed heat transfer containers 32Al or 32All are in fluid communication with a corresponding closed condensing .. : : ~
container 34Al or 34All, located submerged in the `.;
cooling compartment 30, through a duct(s) 36. Thus, ::~::
20 excess thermal energy from the reactor which is .
discharged into the suppression pool chamber, can be ;;
transferred out therefrom via natural convection, :~
-: .. . .. ..
from the suppression pool chamber(s) 26 by means of : . :: ,:
either closed heat transferring container(s) 32 to a -: :
cooling compartment 30 by means of the closed condensing container(s) 34, through duct(s) 36, .
without carrying therewith any contaminating ,,' ' ~' ;~." . ', - 1 o2~22~5 24-AT-05001 ~ ~
radiation or radioactive material. The system, moreover, is continuous and passive with the gravity return of cooled and condensed liquid from a closed condensing container 34 through duct 36 to a closed heat transferring container 32 whereupon the recycled liquid is available for further heat conveyance.
In accordance with the natural convection fluid heat transferring mechanisms of the invention, the excessive thermal energy emanating from the 10 reactor dispenses and contacts the closed heat -transferring container(s) 32, whereby the thermal - -~
energy is transferred to the liquid contents of ~ .. . .
container(s) 32 heating it until it reaches its boiling point and thus vaporizes. The vaporized liquid carrying therewith thermal energy expands through the closed system traveling through duct(s) 36 to the closed condensing container~s) 34 which is submerged in the pool of a cooling compartment 30. ~ -Upon reaching the cooling environment of the sub- ;
merged closed condensing container(s) 34A, the hot vapor is cooled and condensed back to a liquid giving up its previously transferred thermal energy from the closed condensing container(s) 34 to the surrounding pool of a cooling com~artment 30. The cooled 25 condensed liquid will flow back by gravity to -container(s) 32. ~
;~12245 Since the liquid pool of the cooling ~ -compartment 30 is physically isolated from the reactor system and the cooling arrangement described, ~ -appropriate thermal energy introduced into this component can be discharged by any apt means out into the atmosphere without any possibility of releasing radioactive material or radiation.
A further embodiment of this invention, with ;,~
two variations is illustrated in Figure 3 and 4. ,: .
lO According to this version of the invention, the ~ ~:
closed heat transferring container(s) 32B is placed in the suppression pool chamber 26, either submerged in the pool of liquid retained therein, or above the ..
surface thereof as shown in 32Bl. The correspond~
15 ing closed condensing container(s) 34B is located ~ : :
outside the reactor containment housing structure 20 ;; . ; :
and at least one duct 36 provides a fluid communica~
tion between the internal closed heat transferring container(s) 32B and its counterpart external closed co~densing container(s) 34B. The mechanism of heat ~ : -, ,~: .:: ,:
transfer cooling is the same as in the other embodi-ments, namely excessive thermal energy entering the suppression pool chamber 26 vaporizes the liquid held in the closed heat transferring container 32B. The :.
vaporized liquid passes through duct(s) 36 into the closed condensing container(s) 34B outside the reactor structure and is condensed in the cooler ,: ,: - .;
. ' ' ' :~ .:
;~12245 environment by giving up its heat of vaporization.
Then the cooled and condensed liquid gravity flows from the closed condensing container(s) 34B through duct(s) 36 back to the closed heat transferring container 32B for repeating the heat +ransporting and dispensing cycle.
The variation of Figure 3 comprises the ;-~
positioning of the closed condensing container(s) 34B ;~-in a flue-like arrangement which induces an accelerated air or other gas flow therethrough. For example, as shown in the drawing of Figure 3, a flue wall 44 is arranged spaced outward from the reactor containment housing 20 outer wall to provide a flue channel 46 for induced air flow. Flue entry openings -~
48 can be placed along the length of the flue as well as at the bottom to increase the cooling air flow over and about the external closed condensing container(s) 34B. To enhance to cooling efficiency by increasing cooling surface area, the external -~
closed condensing container(s) 34B can be provided as small interconnecting multiples of two, three or more as shown.
The variation of Figure 4 comprises the -positioning of the closed condensing container(s) ;~
34811 out beyond the reactor containment housing 20 ''; :.':'. ''' --~ ~0:12245 and submerged in a relatively large body of cooling - --liquid such as water, for example a pond, lake or lagoon.
The operation of the several passive cooling - 5 embodiments are each based on convection heat trans- ~;~
fer and gravity flow to maintain continuous cooling ~
circulation. The cooling circuit consists of fluid ~ ~ -flow from the closed heat transferring containers through the fluid communicating ducts to the closed 10 condensing containers and return. Water or other apt -liquid retained in the closed heat transferring ~ -containers boils or vaporize when encountering increased surrounding temperatures, thereby absorbing thermal energy. The vapor, or steam, flows through ;
the ducts into the higher closed condensing container which is surrounded in a cooling environment or heat sink, such as a cooling fluid body. The vapor or steam is cooled and condensed, giving up the absorbed -thermal energy. The condensed liquid, devoid of the transported thermal energy, flows by gravity from the closed condensing container through the duct back into the closed heat transferring container.
This cooling mechanism of the various embodiments of the invention is passive in that it is ;
self-initiating and acting without manual or automated controls of values, pumps or other motive power. Cooling is provided through natural '' ~"''. '',~
2(~12245 circulation of the heat removing liquid which i9 self-sustaining and recirculated by gravity. Thus, cooling of the reactor containment is provided for -prolonged periods without external power or personnel action.
Moreover, the heat transferring liquid is isolated from the contaminated materials within the containment by being completely enclosed within the cooling system. The closed cooling system therefore can extend out through the reactor containment structure to the exterior ambient atmosphere whereby thermal energy is conveyed out beyond the structure while prohibiting escape of any radiation or radioactive material. ~ ~
'' ., :: ' . . ~, . ,:
. `~ . . :i: :, ,.
','''~' `' "'."-`-"' !: . . ' .
' ' ' ~' . ,, ', ''"'''.`' "' ' ''`'~';
'''"'. ;``'; ' ~,.' ' ''.'', "
as water. ~ -DETAILED DESCRIPTION OF THE INVENTION
Referring to the drawings, in particular Figure 1, a nuclear reactor plant complex 10 comprises the nuclear reactor consisting of a pressure vessel 12 containing a heat producing core of fissionable fuel 14. The fuel gives up its generated heat from fission ;-~
to a surrounding coolant, typically comprising water for either the direct generation of steam as in a ;~ ` `
so-called boiling water reactor, or to function as heat ~ ;
transfer medium for the indirect generation of steam as ~;
in a so-called pressurized water reactor. Coolant circulating pipes 16 and 18 provide for the circulation of coolant water into the reactor pressure vessel 12 for transfer of the heat output of the fuel, and j , :-, , conveyance of the heated water and/or steam from the pressure vessel to its use such as electrical power generation whereupon it recycles through the circuit.
The nuclear reactor comprising its pressure ,, :
vessel 12 with fuel core 14 and certain related ~-201~45 components is enclosed within a containment structure 20. The containment structure 20 includes a fluid impermeable liner 22 on the structure, which includes a base or floor, a vertical side wall(s) and roof which is designed to prevent the escape from the confines of any radioactive material to the outer atmosphere.
In a typical water cooled nuclear reactor plant, the containment structure 20, in addition to the reactor pressure vessel 12 includes a number of cell-like chambers or compartments designed for the performance of specific functions or objectives. For instance, the reactor pressure vessel 12 can be surrounded by one or more adjacent chambers providing 15 a drywell(s) 24 to receive and retain any overflow or ~-: . , - ~.
spillage of water, steam or other vapor resulting ~ -from leakage or other sources in connection with the reactor operation.
One or more chambers partially filled with , 20 water provide a suppression pool(s) 26 for cooling ~`
and condensing steam beneath the surface of water , pool therein. Suppression pool chamber(s) 26 is in fluid communication with one or more drywell chambers -;
24 through conduits 28 which open at one terminal end -~
25 into an upper portion of drywell chamber 24 and at -its other terminal end into the suppression pool chamber 26 at a lower region below the surface of the ;
,~', ', '' '' '"' 20~2245 water pool contained therein. Thus, any steam escaping or flashing from water leaking from the high temperature and pressure confines of the pressure vessel and its connecting circuits will be received in the drywell chamber(s) 24. The inherent pressure of the steam escaping or flashing from emerging hot -~
water will ultimately be forced from the drywell chamber(s) 24 through conduit(s) 28 into the suppression pool chamber(s) 26 at a location beneath the surface of the water pool therein. The submerged contact of the steam with the pool water condenses it and thereby reduces the steam increased pressures within the containment structure 20 initially produced by the leaking steam or flashing from escaping high temperature and pressure water.
In accordance with one version of the invention, one or more compartments containing water comprising a cooling pool(s) 30 is preferably provided overhead and adjacent to the suppression pool chamber~s) 26.
The passive cooling systems of this invention -comprise the application of one or more closed heat :
transferring containers 32, and their utilization in several embodiments. The closed heat transferring containers 32, as employed in this invention, consist of a closed tank-like vessel or receptacle, which may be elongated as a closed section of pipe. Enclosed ::'., ~
. ~ - ' .
20~245 -9- 24-AT-~S001 within this container 32 is a fluid having a boiling : ~
point in an apt temperature range, for example about :
50 to 150C, and a relatively high heat of vapori-zation (or evaporation) such as water. In addition to the foregoing physical properties, the fluid should be chemically innocuous with respect to other components and materials of the overall system, namely the fluid should not chemically attack or be reactive with any component of possible contact.
Referring to Figure 2, one embodiment of the invention comprises at least one closed heat transferring container(s) 32 located in a suppression pool chamber 26, either submerged in the pool, such :
as container 32Al, or above the surface of the pool, such as container 32All. Closed heat transfer containers 32Al or 32All are in fluid communication with a corresponding closed condensing .. : : ~
container 34Al or 34All, located submerged in the `.;
cooling compartment 30, through a duct(s) 36. Thus, ::~::
20 excess thermal energy from the reactor which is .
discharged into the suppression pool chamber, can be ;;
transferred out therefrom via natural convection, :~
-: .. . .. ..
from the suppression pool chamber(s) 26 by means of : . :: ,:
either closed heat transferring container(s) 32 to a -: :
cooling compartment 30 by means of the closed condensing container(s) 34, through duct(s) 36, .
without carrying therewith any contaminating ,,' ' ~' ;~." . ', - 1 o2~22~5 24-AT-05001 ~ ~
radiation or radioactive material. The system, moreover, is continuous and passive with the gravity return of cooled and condensed liquid from a closed condensing container 34 through duct 36 to a closed heat transferring container 32 whereupon the recycled liquid is available for further heat conveyance.
In accordance with the natural convection fluid heat transferring mechanisms of the invention, the excessive thermal energy emanating from the 10 reactor dispenses and contacts the closed heat -transferring container(s) 32, whereby the thermal - -~
energy is transferred to the liquid contents of ~ .. . .
container(s) 32 heating it until it reaches its boiling point and thus vaporizes. The vaporized liquid carrying therewith thermal energy expands through the closed system traveling through duct(s) 36 to the closed condensing container~s) 34 which is submerged in the pool of a cooling compartment 30. ~ -Upon reaching the cooling environment of the sub- ;
merged closed condensing container(s) 34A, the hot vapor is cooled and condensed back to a liquid giving up its previously transferred thermal energy from the closed condensing container(s) 34 to the surrounding pool of a cooling com~artment 30. The cooled 25 condensed liquid will flow back by gravity to -container(s) 32. ~
;~12245 Since the liquid pool of the cooling ~ -compartment 30 is physically isolated from the reactor system and the cooling arrangement described, ~ -appropriate thermal energy introduced into this component can be discharged by any apt means out into the atmosphere without any possibility of releasing radioactive material or radiation.
A further embodiment of this invention, with ;,~
two variations is illustrated in Figure 3 and 4. ,: .
lO According to this version of the invention, the ~ ~:
closed heat transferring container(s) 32B is placed in the suppression pool chamber 26, either submerged in the pool of liquid retained therein, or above the ..
surface thereof as shown in 32Bl. The correspond~
15 ing closed condensing container(s) 34B is located ~ : :
outside the reactor containment housing structure 20 ;; . ; :
and at least one duct 36 provides a fluid communica~
tion between the internal closed heat transferring container(s) 32B and its counterpart external closed co~densing container(s) 34B. The mechanism of heat ~ : -, ,~: .:: ,:
transfer cooling is the same as in the other embodi-ments, namely excessive thermal energy entering the suppression pool chamber 26 vaporizes the liquid held in the closed heat transferring container 32B. The :.
vaporized liquid passes through duct(s) 36 into the closed condensing container(s) 34B outside the reactor structure and is condensed in the cooler ,: ,: - .;
. ' ' ' :~ .:
;~12245 environment by giving up its heat of vaporization.
Then the cooled and condensed liquid gravity flows from the closed condensing container(s) 34B through duct(s) 36 back to the closed heat transferring container 32B for repeating the heat +ransporting and dispensing cycle.
The variation of Figure 3 comprises the ;-~
positioning of the closed condensing container(s) 34B ;~-in a flue-like arrangement which induces an accelerated air or other gas flow therethrough. For example, as shown in the drawing of Figure 3, a flue wall 44 is arranged spaced outward from the reactor containment housing 20 outer wall to provide a flue channel 46 for induced air flow. Flue entry openings -~
48 can be placed along the length of the flue as well as at the bottom to increase the cooling air flow over and about the external closed condensing container(s) 34B. To enhance to cooling efficiency by increasing cooling surface area, the external -~
closed condensing container(s) 34B can be provided as small interconnecting multiples of two, three or more as shown.
The variation of Figure 4 comprises the -positioning of the closed condensing container(s) ;~
34811 out beyond the reactor containment housing 20 ''; :.':'. ''' --~ ~0:12245 and submerged in a relatively large body of cooling - --liquid such as water, for example a pond, lake or lagoon.
The operation of the several passive cooling - 5 embodiments are each based on convection heat trans- ~;~
fer and gravity flow to maintain continuous cooling ~
circulation. The cooling circuit consists of fluid ~ ~ -flow from the closed heat transferring containers through the fluid communicating ducts to the closed 10 condensing containers and return. Water or other apt -liquid retained in the closed heat transferring ~ -containers boils or vaporize when encountering increased surrounding temperatures, thereby absorbing thermal energy. The vapor, or steam, flows through ;
the ducts into the higher closed condensing container which is surrounded in a cooling environment or heat sink, such as a cooling fluid body. The vapor or steam is cooled and condensed, giving up the absorbed -thermal energy. The condensed liquid, devoid of the transported thermal energy, flows by gravity from the closed condensing container through the duct back into the closed heat transferring container.
This cooling mechanism of the various embodiments of the invention is passive in that it is ;
self-initiating and acting without manual or automated controls of values, pumps or other motive power. Cooling is provided through natural '' ~"''. '',~
2(~12245 circulation of the heat removing liquid which i9 self-sustaining and recirculated by gravity. Thus, cooling of the reactor containment is provided for -prolonged periods without external power or personnel action.
Moreover, the heat transferring liquid is isolated from the contaminated materials within the containment by being completely enclosed within the cooling system. The closed cooling system therefore can extend out through the reactor containment structure to the exterior ambient atmosphere whereby thermal energy is conveyed out beyond the structure while prohibiting escape of any radiation or radioactive material. ~ ~
'' ., :: ' . . ~, . ,:
. `~ . . :i: :, ,.
','''~' `' "'."-`-"' !: . . ' .
' ' ' ~' . ,, ', ''"'''.`' "' ' ''`'~';
'''"'. ;``'; ' ~,.' ' ''.'', "
Claims (9)
1. A passive cooling, natural circulation system for the containment structure of a nuclear reactor plant which provides overpressure protection within the containment housing, comprising a nuclear reactor assembly including a containment housing surrounding a pressure vessel having a heat producing core of fissionable fuel enclosed therein, a drywell chamber adjacent to said pressure vessel, a suppression pool chamber for retaining a cooling liquid for condensing steam and cooling hot water, at least one closed heat transferring container holding a volatile liquid positioned within the suppression pool chamber, and at least one closed condensing container located outside of the suppression pool compartment which is connected in closed circuit fluid communication through at least one duct to the heat transferring container whereby the thermal energy from the suppression pool chamber is conveyed from the closed heat transferring container to the closed condensing container.
2. A passive cooling, natural circulation system for the containment structure of a nuclear reactor plant which provides overpressure protection within the containment housing, comprising a nuclear reactor assembly including a containment housing surrounding a pressure vessel having a heat producing core of fissionable fuel enclosed therein, a drywell chamber adjacent to said pressure vessel, a suppression pool chamber for retaining a cooling liquid to condense steam and cool hot water, a cooling liquid compartment, at least one closed heat transferring container holding a volatile liquid positioned within the suppression pool chamber to intercept excessive thermal energy entering said chamber, and at least one closed condensing container positioned within the cooling liquid compartment, said closed heat transferring container being connected in closed circuit fluid communication through at least one duct to the closed condensing container whereby thermal energy within the drywell chamber from the pressure vessel is conveyed from the closed heat transferring container to the closed condensing container within the cooling liquid compartment.
3. The passive cooling, natural circulating system of claim 2, wherein the closed heat transferring container is positioned in the upper area of the suppression pool chamber above the liquid pool therein.
4. The passive cooling, natural circulating system of claim 2, wherein the closed heat transferring container is positioned in the lower area of the suppression pool chamber submerged beneath the surface of liquid pool therein.
5. A passive cooling, natural circulation system for the containment structure of a nuclear reactor plant which provides overpressure protection within the containment housing, comprising a nuclear reactor assembly including a containment housing surrounding a pressure vessel having a heat producing core of fissionable fuel enclosed therein, a drywell chamber adjacent to said pressure vessel, a suppression pool chamber for retaining a cooling liquid, at least one closed heat transferring container holding a volatile liquid positioned within the suppression pool chamber to intercept excessive thermal energy entering said chamber, and at least one closed condensing container positioned outside of the containment housing, said closed heat transferring container being connected in closed circuit fluid communication through at least one duct to the closed condensing container outside the containment housing whereby thermal energy within the drywell chamber from the pressure vessel is conveyed from the closed heat transferring container within the suppression pool chamber to the closed condensing chamber outside the containment housing.
6. The passive cooling, natural circulation system of claim 5, wherein the closed condensing chamber located outside the containment housing is exposed to the ambient atmosphere.
7. The passive cooling, natural circulation system of claim 5, wherein the closed condensing chamber located outside the containment housing is submerged beneath the surface of a pool of water.
8. A passive cooling, natural circulation system for the containment structure of a nuclear reactor plant which provides overpressure protection within the containment housing, comprising a nuclear reactor assembly including a containment housing surrounding a pressure vessel having a heat producing core of fissionable fuel enclosed therein, a drywell chamber adjacent to said pressure vessel, a suppression pool chamber for retaining a cooling liquid, a multiplicity of closed heat transferring container holding a volatile liquid positioned within the suppression pool chamber to intercept excessive thermal energy entering said chamber, and a multiplicity of closed condensing container positioned outside of the containment housing, each of said closed heat transferring container being connected in closed fluid communication through at least one duct to each of the closed condensing container outside the containment housing, said closed condensing containers being located in a gas flue carrying a flow of cooling gas whereby thermal energy within the drywell chamber from the pressure vessel is conveyed from the closed heat transferring container within the suppression pool chamber to the closed condensing chamber outside the containment housing and within the cooling gas flue.
9. The invention as defined in any of the preceding claims including any further features of novelty disclosed.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US34527289A | 1989-05-01 | 1989-05-01 | |
| US345,272 | 1989-05-01 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA2012245A1 true CA2012245A1 (en) | 1990-11-01 |
Family
ID=23354315
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA002012245A Abandoned CA2012245A1 (en) | 1989-05-01 | 1990-03-15 | Passive cooling system for nuclear reactor containment structures |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JPH0341394A (en) |
| KR (1) | KR900019060A (en) |
| CA (1) | CA2012245A1 (en) |
| NO (1) | NO901942L (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6333697A (en) * | 1986-07-29 | 1988-02-13 | 株式会社東芝 | Container-heat removing device |
| US4948554A (en) * | 1989-01-06 | 1990-08-14 | General Electric Company | Natural circulating passive cooling system for nuclear reactor containment structure |
-
1990
- 1990-03-15 CA CA002012245A patent/CA2012245A1/en not_active Abandoned
- 1990-04-30 KR KR1019900006081A patent/KR900019060A/en not_active Withdrawn
- 1990-04-30 NO NO90901942A patent/NO901942L/en unknown
- 1990-05-01 JP JP2111910A patent/JPH0341394A/en active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0341394A (en) | 1991-02-21 |
| NO901942L (en) | 1990-11-02 |
| KR900019060A (en) | 1990-12-22 |
| NO901942D0 (en) | 1990-04-30 |
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