WO2021029985A1 - Système de protection de réacteur nucléaire flottant - Google Patents

Système de protection de réacteur nucléaire flottant Download PDF

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Publication number
WO2021029985A1
WO2021029985A1 PCT/US2020/040957 US2020040957W WO2021029985A1 WO 2021029985 A1 WO2021029985 A1 WO 2021029985A1 US 2020040957 W US2020040957 W US 2020040957W WO 2021029985 A1 WO2021029985 A1 WO 2021029985A1
Authority
WO
WIPO (PCT)
Prior art keywords
water pipe
tank
water
barge
nuclear reactor
Prior art date
Application number
PCT/US2020/040957
Other languages
English (en)
Inventor
Palvannanathan Ganesan
Original Assignee
Palvannanathan Ganesan
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Priority claimed from US16/539,581 external-priority patent/US11107595B2/en
Application filed by Palvannanathan Ganesan filed Critical Palvannanathan Ganesan
Publication of WO2021029985A1 publication Critical patent/WO2021029985A1/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/001—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against explosions, e.g. blast shields
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F41—WEAPONS
    • F41H—ARMOUR; ARMOURED TURRETS; ARMOURED OR ARMED VEHICLES; MEANS OF ATTACK OR DEFENCE, e.g. CAMOUFLAGE, IN GENERAL
    • F41H5/00—Armour; Armour plates
    • F41H5/24—Armour; Armour plates for stationary use, e.g. fortifications ; Shelters; Guard Booths
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G21C11/04—Biological shielding ; Neutron or gamma shielding on waterborne craft
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/024—Supporting constructions for pressure vessels or containment vessels
    • 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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04H—BUILDINGS OR LIKE STRUCTURES FOR PARTICULAR PURPOSES; SWIMMING OR SPLASH BATHS OR POOLS; MASTS; FENCING; TENTS OR CANOPIES, IN GENERAL
    • E04H5/00—Buildings or groups of buildings for industrial or agricultural purposes
    • E04H5/02—Buildings or groups of buildings for industrial purposes, e.g. for power-plants or factories
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04H—BUILDINGS OR LIKE STRUCTURES FOR PARTICULAR PURPOSES; SWIMMING OR SPLASH BATHS OR POOLS; MASTS; FENCING; TENTS OR CANOPIES, IN GENERAL
    • E04H9/00—Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate
    • E04H9/02—Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate withstanding earthquake or sinking of ground
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04H—BUILDINGS OR LIKE STRUCTURES FOR PARTICULAR PURPOSES; SWIMMING OR SPLASH BATHS OR POOLS; MASTS; FENCING; TENTS OR CANOPIES, IN GENERAL
    • E04H9/00—Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate
    • E04H9/04—Buildings, groups of buildings or shelters adapted to withstand or provide protection against abnormal external influences, e.g. war-like action, earthquake or extreme climate against air-raid or other war-like actions
    • E04H9/06—Structures arranged in or forming part of buildings
    • 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

Definitions

  • 15/807,182 entitled FLOATING NUCLEAR REACTOR PROTECTION SYSTEM relates to a floating nuclear power reactor. More particularly, the invention of the '182 application relates to a floating nuclear power reactor including a barge which is floatably positioned in the interior of a large water-filled tank or body of water and wherein the nuclear power reactor is positioned on the barge. Even more particularly, the invention of the '182 application relates to a protection system for a floating nuclear power reactor to protect the nuclear reactor from an aircraft strike or a missile strike. Additionally, the protection system of the invention of the '182 application includes structure to reduce the impact forces of an aircraft strike or a missile strike. The instant invention relates to structure to maintain the temperature and water level of the water-filled tank in which the barge of the floating nuclear power reactor is floating.
  • a suspension system for suspending and stabilizing a barge which is floating in a large water tank. That system is incorporated herein which further enhances the protection of the nuclear reactor in the event of an aircraft strike or a missile strike.
  • the invention of Applicant's earlier '182 application provides a protection system for the nuclear power reactor of the co-pending application and to provide protection to other exposed nuclear power reactors of different designs.
  • the prior application and patents of Applicant do not have any means to maintain the temperature and water level of the water-filled tank.
  • the floating nuclear reactor of the '182 patent application includes a tank, which may be rectangular, having a bottom wall, an upstanding first end wall, an upstanding second end wall, an upstanding first side wall and an upstanding second side wall.
  • a tank which may be rectangular, having a bottom wall, an upstanding first end wall, an upstanding second end wall, an upstanding first side wall and an upstanding second side wall.
  • Each of the first end wall, the second end wall, the first side wall and the second side wall of the tank have an outer side, an inner side, a lower end and an upper end.
  • the tank is partially or fully buried in the ground with the tank having water therein.
  • a barge is floatably positioned in the tank with the barge having a bottom wall, a first end wail, a first side wall, a second side wall and an open second end.
  • a nuclear reactor is positioned on the barge.
  • At least one suspension assembly, and preferably a plurality of suspension assemblies connect the first end wall of the barge to the first end wall of the tank.
  • At least one suspension assembly, and preferably a plurality of suspension assemblies connect the first side wall of the tank to the first side wall of the barge.
  • At least one suspension assembly, and preferably a plurality of suspension assemblies connect the second side wall of the tank to the second side wall of the barge.
  • At least one suspension assembly connect the second end wall of the barge to the second end wail of the tank.
  • the suspension assemblies permit the barge to move upwardly and downwardly with respect to the tank while maintaining the barge in a level condition.
  • the suspension assemblies permit the barge to move downwardly if struck by a missile or aircraft to lessen the impact thereof.
  • the nuclear reactor of the '182 patent application is positioned in the tank so as to close the open second end of the barge.
  • the nuclear reactor includes a first containment member which has a cylindrical body portion, a hemi-spherical upper end and a hemi-spherical lower end.
  • the first containment member is comprised of stainless steel or other suitable material.
  • the first containment member is positioned at the open end of the barge with the sides of the containment member being in engagement with the ends of the sidewalls of the barge so as to close the open end of the barge.
  • the positioning of the first containment member causes the outer side of the first containment member to be in contact with the water in the tank.
  • the first containment member defines a sealed interior compartment.
  • the first containment member has a hatch or door mounted thereon at the lower end thereof which selectively closes an opening in the first containment member.
  • the first containment member also has a pipe extending from the lower end thereof which is in fluid communication with the interior compartment thereof.
  • a normally closed one-way valve is imposed in the pipe.
  • a reactor vessel is positioned In the interior compartment of the first containment member.
  • the nuclear reactor of the co-pending application has a unique cooling system for the nuclear reactor which does not form a part of this invention.
  • a heat exchanger is positioned adjacent the first containment member and includes a body section, an upper section and a lower section.
  • the heat exchanger includes an outer wall member or second containment member which is comprised of metal.
  • a vessel is positioned within the second containment member of the heat exchanger. The vessel has an interior compartment which is filled with fluid.
  • the heat exchanger is connected to a turbine or other device.
  • the suspension assemblies also permit the barge to move downwardly in the tank in the event of an aircraft strike, a missile strike or an earthquake to reduce the impact forces on the barge and nuclear reactor.
  • a hollow steel conical-shaped member is mounted on the upper end of the first containment member of the nuclear reactor.
  • a hollow steel conical-shaped member is also mounted on the upper end of the heat exchanger. If an aircraft or a missile should strike either of the conical-shaped members, the conical-shaped members would cause the disintegration of the aircraft or missile and would deflect the same.
  • a roof is positioned over the upper end of the barge which hides the location of the nuclear reactor and heat exchanger from view so that an aircraft attempting to strike either the nuclear reactor or the heat exchanger will not know the precise position of those structures on the barge.
  • the interior of the conical-shaped members on the upper ends of the nuclear reactor and the heat exchanger will be filled with a material which acts as an impact absorbing member.
  • the instant invention provides means for maintaining the temperature and water level of the water-filled tank in which the barge floats.
  • a further object of the invention is to provide structure for maintaining the temperature and water level of the water-filled tank in which the barge of the nuclear reactor floats.
  • a further object of the invention is to provide cooling water to the condenser and to drain hot water from the condenser.
  • Fig. 1 is a perspective view of a floating nuclear power reactor of the '182 application wherein the nuclear reactor confinement member and the containment member of the heat exchanger have a conical-shaped member on the upper ends thereof;
  • Fig. 2 is a perspective view similar to Fig. 1 except that a roof structure is positioned over the nuclear reactor, the heat exchanger and the barge of the '182 application;
  • Fig. 3 is a sectional view illustrating the conical-shaped members of the '182 application mounted on the upper ends of the nuclear reactor and the heat exchanger thereof with a roof extending thereover;
  • Fig. 4 is a sectional view similar to Fig. 3 except that the conical-shaped members are filled with an impact absorber material;
  • Fig. 5 is a sectional view similar to Fig. 3 except that the conical-shaped members on the nuclear reactor have a filtration material therein and a vent tube assembly therein;
  • Fig. 6 is a sectional view which illustrates the suspension assemblies of the '182 application which suspend the barge in the water-filled tank;
  • Fig. 7 is a sectional view which illustrates the structure of the '182 application and the structure of this invention which maintains the temperature and water level of the tank in which the nuclear reactor floats.
  • Applicant has previously received U. S. Patent Nos. 9,378,855; 9,396,823; and 9,502,143 relating to floating nuclear power reactors. Applicant incorporates the disclosure of the above identified patents in their entirety by reference thereto to complete this disclosure if necessary. Applicant also incorporates the disclosure of Application Serial No. 15/807,182 filed November 8, 2017 in its entirety by reference thereto to complete this disclosure if necessary.
  • the floating nuclear reactor of the invention of the '182 application is referred to generally by the reference numeral 10.
  • the nuclear reactor 10 floats in a concrete tank 12 having a bottom wall 14, a first end wall 16, a second end wall 18, a first side wall 20, a second side wall 22 and an open upper end 24.
  • Tank 12 is buried in the ground 26 as seen in Fig. 1 so that the open upper end 24 of tank 12 is at or above ground level 28.
  • the tank 12 is partially filled with water 30 from a source of water. Preferably the water 30 is gravity fed to the tank 12.
  • the tank 12 may be completely buried in the ground.
  • the numeral 32 refers to a barge-like vessel which floats in the tank 12.
  • Barge 32 includes a bottom wall 34, a first side wall 36, a second side wall 38, a semi-circular end wall 40 and an open end 41 at the ends 42 and 43 of side walls 36 and 38 respectively.
  • Barge 32 is comprised of a metal material such as stainless steel, steel, iron, aluminum or other suitable material.
  • Barge 32 is supported in tank 12 by a plurality of upper suspension assemblies 44, 46, 48, 50,
  • Barge 32 is also supported in tank 12 by a plurality of lower suspension assemblies, identical to suspension assemblies 44, 46, 48,
  • the numeral 59 refers to a nuclear reactor which is positioned in barge 32 so as to close the open end 41 of barge 32 as will be explained in detail hereinafter.
  • Reactor 59 includes an upstanding containment member 60 which has a cylindrical body portion 62, a hemi-spherical upper end 64 and a hemispherical lower end 66.
  • Containment member 60 is comprised of stainless steel or other suitable material. Containment member 60 is positioned at the open end 41 of barge 32 with the sides of containment member 60 being in engagement with the ends 42 and 43 of side walls 36 and 38 respectively of barge 32 and being secured thereto by welding or the like to close the open end 41 of barge 32.
  • the positioning of the containment member 60 as just described causes the outer side of containment member 60 to be in contact with the water 30 in tank 12.
  • Containment member 60 defines a sealed interior compartment 68.
  • Containment member 60 has a hatch 70 mounted therein as seen in Fig. 3.
  • Containment member 60 also has a pipe 72 extending from the lower end thereof which is in fluid communication with the interior compartment 68.
  • a normally closed one-way valve 74 is imposed in pipe 72.
  • a reactor vessel 75 is positioned in compartment 68 and has an interior compartment 76. Vessel 75 is supported in compartment 68 by braces 77 which extend between the exterior of reactor vessel 75 and the interior side of containment member 60 as seen in Fig. 3.
  • the numeral 80 refers to an upstanding heat exchanger which is positioned adjacent containment member 60 as seen in the drawings.
  • Heat exchanger 80 includes a body section 82, an upper section 84 and a lower section 86.
  • Heat exchanger 80 is comprised of a metal material such as stainless steel or other suitable material.
  • a vessel 88 is positioned within heat exchanger 80 and is supported therein by braces 90 extending therebetween.
  • Vessel 88 defines an interior compartment 92.
  • a tube 93 interconnects the reactor vessel 75 and the vessel 88 of heat exchanger 80 as seen in the drawings.
  • the heat exchanger 80 is connected to a turbine 96, or other device, by tube 94, which is connected to a generator 98 or other structure.
  • a hollow metal cone 100 is mounted on the hemi-spherical upper end 64 of containment member 60.
  • Cone 100 is comprised of stainless steel, steel or other suitable material.
  • Cone 100 has an interior compartment 102 which is preferably filled with a filter material 104 which not only may serve as a filtration bed but serves as an impact absorber should the cone 100 be struck by an aircraft or a missile.
  • the cone 100 if struck by an aircraft or missile, will disintegrate or tear apart the aircraft or missile and deflect the aircraft or missile away from the cone 100.
  • An outlet pipe 106 may be provided in the upper end of containment member 60 to permit steam or the like to pass upwardly therethrough onto the filtration material 104.
  • the cone 100 may also have a discharge tube assembly 108 extending upwardly from pipe 106 and which has discharge tubes 110 extending downwardly and outwardly from the upper end of tube 108 as seen in Fig. 5.
  • a metal cone 112 extends upwardly from the upper end of heat exchanger
  • Cone 112 if struck by an aircraft or missile, will disintegrate the aircraft or missile in the same manner as the cone 100.
  • a roof 116 extends over the cones 100, 112 and the barge 32 to hide the reactor 59 and the heat exchanger 80 from view. Thus, if an aircraft is attempting to strike the reactor 59, the pilot of the aircraft will not be able to determine the exact location of the reactor 59.
  • a pair of vertically disposed guide tracks or channels 120 and 122 are secured to the inner side of end wall 18.
  • a pair of vertically disposed guide tracks or channels 124 and 126 are secured to the inner side of side wall 20.
  • a pair of vertically disposed guide tracks or channels 128 and 130 are secured to the inner side of end wall 16.
  • a pair of vertically disposed guide tracks or channels 132 and 134 are secured to the inner side of side wall 22.
  • the guide tracks 120, 122, 124, 126, 128, 130, 132 and 134 form a part of the suspension assemblies 46, 48, 50, 52, 54, 56, 58 and
  • Suspension assembly 48 includes an upper chain member 136, a lower chain member 138 and an intermediate chain member 140. The outer ends of chain members 136, 138 and 140 are secured to the upper wheel in guide track
  • chain members 136, 138 and 140 are secured to the barge 32.
  • upper chain member 136 extends upwardly and inwardly from guide track 122 to barge 32.
  • lower chain member 138 extends downwardly and inwardly from guide track 122 to barge 32.
  • intermediate chain member 140 extends horizontally inwardly from guide track 122 to barge 32.
  • the suspension assembly below suspension assembly 46 would be similarly attached to the lower wheel in guide track 122 and the barge 32.
  • the other suspension assemblies would be attached to the guide tracks 124, 126, 128,
  • the suspension assemblies 44, 50, 56 and 58 are identical.
  • the suspension assemblies 46, 48, 54 and 56 are identical.
  • the only difference between the suspension assemblies 44, 50, 56, 58 and the suspension assemblies 46, 48, 54 and 56 is that the suspension assemblies 46, 48, 54 and 56 are somewhat longer than the suspension assemblies 44, 50, 56 and 58.
  • the guide tracks or channels could be secured to the barge rather than being secured to the walls of the tank. In that embodiment, the ends of the chains of the suspension assemblies would be secured to the tank.
  • each of the suspension assemblies have a horizontally disposed intermediate chain member 140
  • the intermediate chain member 140 may be omitted in some situations.
  • the cones will disintegrate and deflect the aircraft or the missile to prevent damage to the nuclear reactor. Additionally, the impact absorbing material in the cones 100 and 112 will lessen the damage to the nuclear reactor. Further, if the barge 32 or the cones 100 and 112 are struck by an aircraft or missile, the suspension systems will permit the barge 32 to move downwardly in the tank 12 to lessen or absorb the impact forces of the strike.
  • the numeral 142 refers to a water inlet pipe or tube to bring water into the water tank 12 from a large source of water preferably by gravity.
  • Inlet tube 142 includes a valve 144 to control the rate of flow of the water therethrough.
  • An optional pump 146 in inlet tube 142 would help to accelerate the flow of water through inlet tube 142 if necessary. This helps to maintain the temperature and water level of the tank 16 at an optimal range.
  • Valve 144 and pump 146 may be remotely controlled.
  • the numeral 148 refers to a flexible water inlet water pipe or tube for bringing water into the interior compartment 68 of containment member 60 from a large source of water preferably by gravity.
  • a valve 150 is provided in inlet tube 148 to control the rate of flow of water therethrough.
  • An optional pump 152 in inlet tube 148 helps to accelerate the flow of water through inlet tube 148 if necessary.
  • Valve 150 and pump 152 may be remotely controlled.
  • Inlet tube 148 has a flexible, slack and folded tubular section 154 at its inner end.
  • the numeral 156 refers to a flexible water inlet pipe or tube for bringing water into the interior compartment 68 of containment member 60 from a large source of water preferably by gravity.
  • a valve 158 is provided in inlet tube 156 to control the rate of flow of water therethrough.
  • An optional pump 160 in inlet tube 156 helps to accelerate the flow of water through inlet tube 156 if necessary. Valve 158 and pump 160 may be remotely controlled.
  • Inlet tube 156 has a flexible, slack and folded tubular section 162 at its inner end.
  • the inlet tubes 148 and 156 deliver cold water directly into the interior compartment 68 of containment member 60 during emergency cooling to cool the cooling loops and the reactor wall thereof.
  • the numeral 164 refers to a gate which is situated in the upper part of containment member 60 just below water level. Gate 164 is opened during emergency cooling of the reactor. The outflow of water through gate 164 permits additional cold water to enter the interior compartment 68 of containment member 60 via flexible tubes 148 and 156 which helps to maintain maximum cooling conditions in the interior compartment 68 of containment member 60 during emergency cooling.
  • the numeral 166 refers to a conventional condenser.
  • a pipe or tube 168 connects turbine 96 and condenser 166.
  • An inlet pipe or tube 170 extends from a large source of water preferably fed by gravity to the condenser 166.
  • Inlet tube 170 has a flexible, slack and folded tubular section 172 imposed therein.
  • 174 and 176 are imposed in tube 170.
  • An optional pump 178 may be imposed in tube 170.
  • a water inlet pipe or tube 184 extends inwardly from the tank water to the condenser 166.
  • a valve 186 is imposed in tube 184.
  • the purpose of tube 184 is to fill water from the tank 16 into the condenser 166 by gravity.
  • Tube 184 functions as a back-up in case of a break in tube 170.
  • An outlet pipe or tube 188 extends from condenser 166 to a location outwardly of tank 16 by gravity. Tube 188 drains hot water from the condenser
  • Valves 190 and 192 are imposed in tube 188.
  • Optional pump 194 may also be imposed in tube 188.
  • Tube 188 includes a flexible, slack and folded tubular section 196 positioned in tank 12 as seen in Fig. 8.
  • the valves 174 and 176 in tube 170 adjust the flow of inlet water into the condenser 166 with the optional pump 178 accelerating the inlet flow of water if necessary.
  • the valves 190 and 192 in tube 188 adjust the outlet flow of water from the condenser 166 with the pump 194 accelerating the outlet of water if necessary.
  • the valves 174, 176, 190 and 192 maintain optimal cooling temperature of the cooling water in condenser 166.
  • the valves 174 and 190 serve as backups to valves 176 and 192 respectively. As seen, the valves 176 and 192 are located on land while valves 174 and 190 are located inside the barge 16.
  • the numeral 198 refers to an outlet pipe or tube for draining the water from tank 16 preferably by gravity.
  • a valve 200 is imposed in tube 198 for controlling the flow of water from tank 16.
  • the outlet tube 198 with the valve 200 imposed therein helps to maintain the water level and temperature of the water in tank 12 at an optimal range.
  • An optional pump 202 may be provided in tube 198 to accelerate the flow of water from tank 16 if needed.
  • a pipe or tube 204 extends from condenser 166 to interior compartment 92.
  • the flexible tubing sections 154, 162, 172 and 196, with slack, allow the barge 16 to move while maintaining the integrity of the tubes or pipes 148, 156, 170 and 188 respectively.
  • the inlet pipe 142 brings water from a large source of water preferably by gravity to the water tank 12.
  • the valve 144 in the pipe 142 controls the rate of flow of water to help maintain the temperature and water level of the tank at optimal range.
  • An optional pump 146 is imposed in the inlet pipe 142 to accelerate the water flow if needed.
  • Water inlet pipes 148 and 156 bring water from a large source of water preferably by gravity to the interior compartment 68 of containment member 60. Both of the tubes 148 and 156 deliver cold water directly to the interior compartment 68 of containment member 60 by utilizing the valves and optional pumps. The system helps to deliver cold water directly into the interior compartment 68 of containment member 60 during emergency cooling to cool the cooling loops and the reactor wall. By adjusting the flow of water using the valves and optional pumps, the temperature of water inside the interior compartment 68 of containment member 60 is optimized during emergency cooling.
  • the valves associated with the pipes 148 and 156 could be controlled from a location farther away from the nuclear reactor.
  • the gate 164 is open during emergency cooling of the reactor. Water would flow out of the interior compartment 68 of containment member 60 via the gate 164. The outflow from the interior compartment 68 of containment member
  • Inlet pipe 170 brings water from a large source of water to feed cooling water to the condenser 166 preferably by gravity.
  • Outlet pipe 188 drains hot water from the condenser.
  • the valves in pipes 170 and 188 would adjust the flow of inlet and outlet water and the optional pumps in pipes 170 and 188 would accelerate the flow if needed. Together, they maintain optimal cooling temperature of the water in the condenser 166 to enable the condenser 166 to function with maximal efficiency.
  • the valve 174 in pipe 170 controls the inlet flow of water to the condenser 166 and the valve 190 in pipe 188 controls the outlet flow of water from the condenser to optimize the temperature of the cooling water in the condenser 166.
  • the valves in pipes 170 and 188 adjust the inflow and outflow of water to and from the condenser 166 to optimize the temperature of the cooling water in the condenser 166.
  • the pipe 198 functions to drain the tank preferably by gravity.
  • the valve 200 in pipe 198 and the optional pump 202 would accelerate the drainage if needed. This helps to maintain the water level and temperature of the water in the tank at optimal range.
  • the flexible, slack and folded tube sections 154, 162, 172 and 196 have slack to allow the barge to move while maintaining the integrity of the tubes.
  • the pipe 184, having valve 186 imposed therein, permits water from the tank to flow into the condenser 166.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

L'invention concerne un système destiné à être utilisé avec un réacteur nucléaire qui est monté sur une barge et qui flotte dans un réservoir d'eau. Le système comprend au moins un tuyau d'eau qui s'étend à partir d'une source d'eau vers l'intérieur du réservoir. Le système comprend également un tuyau qui permet le drainage de l'eau contenue dans le réservoir d'eau. Des vannes sont agencées dans la tuyauterie de telle sorte que l'eau contenue dans le réservoir présente un niveau et une température souhaités. Le système permet également de fournir de l'eau douce à l'enceinte de confinement du réacteur. En outre, le système comprend une tuyauterie et des vannes destinées à fournir de l'eau au condenseur et à évacuer l'eau du condenseur. Le système comprend également des sections tubulaires souples et molles positionnées dans la tuyauterie entre la barge et le réservoir d'eau, ce qui permet à la barge de se déplacer tout en préservant l'intégrité du tube.
PCT/US2020/040957 2019-08-13 2020-07-07 Système de protection de réacteur nucléaire flottant WO2021029985A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US16/539,581 US11107595B2 (en) 2019-06-28 2019-08-13 Floating nuclear reactor protection system
US16/539,581 2019-08-13

Publications (1)

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WO2021029985A1 true WO2021029985A1 (fr) 2021-02-18

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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090129530A1 (en) * 2007-11-15 2009-05-21 The State Of Or Acting By And Through The State System Of Higher Education On Behalf Of Or State U Passive emergency feedwater system
US20090232267A1 (en) * 2008-03-17 2009-09-17 Korea Atomic Energy Research Institute Emergency core cooling system having core barrel injection extension ducts
US8867691B1 (en) * 2011-08-26 2014-10-21 Warren N. Root Seismic safe nuclear power plant
US20190139657A1 (en) * 2017-11-08 2019-05-09 Palvannanathan Ganesan Floating nuclear power reactor with a self-cooling containment structure and an emergency heat exchange system
US20190244719A1 (en) * 2017-11-08 2019-08-08 Palvannanathan Ganesan Floating nuclear reactor protection system

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20090129530A1 (en) * 2007-11-15 2009-05-21 The State Of Or Acting By And Through The State System Of Higher Education On Behalf Of Or State U Passive emergency feedwater system
US20090232267A1 (en) * 2008-03-17 2009-09-17 Korea Atomic Energy Research Institute Emergency core cooling system having core barrel injection extension ducts
US8867691B1 (en) * 2011-08-26 2014-10-21 Warren N. Root Seismic safe nuclear power plant
US20190139657A1 (en) * 2017-11-08 2019-05-09 Palvannanathan Ganesan Floating nuclear power reactor with a self-cooling containment structure and an emergency heat exchange system
US20190244719A1 (en) * 2017-11-08 2019-08-08 Palvannanathan Ganesan Floating nuclear reactor protection system

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