CN106128536A - A kind of system of safety coefficient when can improve nuclear energy power generation - Google Patents

A kind of system of safety coefficient when can improve nuclear energy power generation Download PDF

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Publication number
CN106128536A
CN106128536A CN201610500784.3A CN201610500784A CN106128536A CN 106128536 A CN106128536 A CN 106128536A CN 201610500784 A CN201610500784 A CN 201610500784A CN 106128536 A CN106128536 A CN 106128536A
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China
Prior art keywords
control valve
steam turbine
feed
pipe
containment
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Pending
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CN201610500784.3A
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Chinese (zh)
Inventor
贺昶明
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Sichuan Xingzhi Intellectual Property Operation Service Co Ltd
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Sichuan Xingzhi Intellectual Property Operation Service Co Ltd
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Priority to CN201610500784.3A priority Critical patent/CN106128536A/en
Publication of CN106128536A publication Critical patent/CN106128536A/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • G21D3/06Safety arrangements responsive to faults within the plant
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses a kind of system of safety coefficient when can improve nuclear energy power generation, reactor building is provided with containment, containment is provided with pressure vessel, pressure vessel is provided with steam-water separator and reactor fuel rod, containment is provided with circulation pipe, circulating pump it is provided with on circulation pipe, reactor building is provided with constrain pond, constrain pond is provided with liquid level sensor, it is provided with filler pipe below constrain pond, it is provided with open and close valve and water pump on filler pipe, steam turbine Factory Building is provided with steam turbine high-pressure cylinder, steam turbine and electromotor;Condenser it is provided with below steam turbine, condenser is provided with cooling tube, it is provided with cooling water pump, control valve two and control valve three on cooling tube, condenser is provided with feed pipe, feed pipe is provided with condensate pump, feed-water heater, feed pump, control valve four and control valve five.This system can take maltilevel security measure when utilizing nuclear energy power generation, improves safety coefficient, and it is more lasting to run.

Description

A kind of system of safety coefficient when can improve nuclear energy power generation
Technical field
The present invention relates to a kind of system, especially relate to a kind of system of safety coefficient when can improve nuclear energy power generation.
Background technology
All materials are all by atomic building in the world, and atom is again to be made up of atomic nucleus and the electronics around it. The fusion of light atom core and the division of Der schwere Atomkern can produce substantial amounts of energy, are called nuclear fusion energy and nuclear fission energy, It is called for short nuclear energy.The fuel of nuclear power plant is uranium.Uranium is a Heavy Metallic Elements, and natural uranium is by three kinds of isotopics: uranium-235 contains Amount 0.71%, uranium-238 content 99.28%, uranium-234 content 0.0058%.Uranium-235 be nature exist be prone to fission Unique nucleic.When neutron bombardment uranium-235 atomic nucleus, this atomic energy splits into two lighter atomic nucleus, with Time produce 2 to 3 neutrons and ray, and release energy.If newly generated neutron hits again another uranium-235 atomic nucleus, energy Cause new fission.In chain reaction, energy can discharge continuously.1 kilogram of uranium-235 all fission releasing The energy that energy equivalence is released in 2700 tons of standard coal burnings.Therefore, utilizing nuclear energy power generation is that one can quickly realize the energy The technology utilized, in existing nuclear energy power generation structure, owing to structure design is unreasonable so that there is nuclear energy uses rate during generating Low, safety precautions is not in place, there is the biggest potential safety hazard when generating.
Summary of the invention
It is an object of the invention to overcome in above-mentioned existing nuclear energy power generation structure, owing to structure design is unreasonable so that send out There is nuclear energy uses rate during electricity low, safety precautions is not in place, the problem that there is the biggest potential safety hazard when generating, design A kind of system of safety coefficient when can improve nuclear energy power generation, this system can take multiple peace when utilizing nuclear energy power generation Full measure, improves safety coefficient so that power generation process is safer, and it is more lasting to run, and the utilization rate for nuclear energy is higher, Solve in existing nuclear energy power generation structure, owing to structure design is unreasonable so that there is nuclear energy uses rate during generating low, safety is protected Protect measure not in place, the problem that there is the biggest potential safety hazard when generating.
The purpose of the present invention is achieved through the following technical solutions: a kind of when can improve nuclear energy power generation safety coefficient be System, including reactor building, steam turbine Factory Building and cooling tower, is provided with containment, sets in containment in described reactor building It is equipped with pressure vessel, pressure vessel is provided with steam-water separator and reactor fuel rod, and reactor fuel rod is arranged on soda pop and divides From the underface of device and being connected with steam-water separator, be provided with control rod in the bottom of pressure vessel, control rod is arranged on safety In shell, being additionally provided with circulation pipe in containment, the two ends of circulation pipe all connect with pressure vessel, and connectivity part is positioned at soda pop and divides Below device, being provided with circulating pump on circulation pipe, be provided with constrain pond in reactor building, constrain pond is communicated with row Trachea, and connect with constrain pond and containment inside while of exhaustor, constrain pond is provided with liquid level sensor, constrain Being provided with filler pipe below pond, filler pipe connects with the bottom in constrain pond, and is provided with open and close valve and water on filler pipe Pump, open and close valve can completely cut through filler pipe, and open and close valve is arranged between water pump and constrain pond, and liquid level sensor is by number It is connected with open and close valve and water pump according to line simultaneously;Described steam turbine Factory Building is provided with steam turbine high-pressure cylinder, steam turbine and electromotor, Being provided with connecting shaft on steam turbine high-pressure cylinder, steam turbine is arranged in connecting shaft, and connecting shaft is connected with electromotor, steam turbine High pressure cylinder connects jet chimney one, and jet chimney one is connected with steam turbine high-pressure cylinder and pressure vessel simultaneously, and steam pipe Being provided with control valve one on road one, control valve one can completely cut through jet chimney one, and control valve one is arranged on reactor factory Fang Zhong;Being provided with condenser below steam turbine, condenser is provided with jet chimney two, jet chimney two connects with steam turbine After be connected with steam turbine high-pressure cylinder again, condenser is provided with cooling tube, the two ends of cooling tube all connect with cooling tower, cooling Being provided with cooling water pump, control valve two and control valve three on pipe, cooling water pump, control valve two and control valve three are arranged at steamer In machine Factory Building, control valve two is arranged between cooling water pump and condenser, and control valve three is arranged between condenser and cooling tower, Being provided with feed pipe on condenser, feed pipe connects with pressure vessel, and the connectivity part of feed pipe and pressure vessel is positioned at steam The lower section of the connectivity part of pipeline one and pressure vessel, is provided with condensate pump, feed-water heater, feed pump, control on feed pipe Valve four processed and control valve five, condensate pump is arranged between feed-water heater and condenser, and control valve four is arranged on condensate pump And and feed-water heater between, feed pump is arranged between pressure vessel and feed-water heater, control valve five be arranged on pressure hold Between device and feed pump.
The quantity of described steam turbine is three, and three steam turbines are sequentially arranged in connecting shaft, jet chimney two respectively with Three steam turbine connections.
The quantity in described constrain pond is two, and is arranged at the lower section of containment, and two constrain ponds are along safety The centrage of shell is symmetrical arranged, and two constrain ponds all connect, with two the while of filler pipe by exhaustor and containment are internal Constrain pond connects, and is provided with liquid level sensor in each constrain pond.
In sum, the invention has the beneficial effects as follows: this system can take maltilevel security when utilizing nuclear energy power generation Measure, improves safety coefficient so that power generation process is safer, and it is more lasting to run, and the utilization rate for nuclear energy is higher, solves Determine in existing nuclear energy power generation structure, owing to structure design is unreasonable so that there is nuclear energy uses rate during generating low, safeguard protection Measure is not in place, the problem that there is the biggest potential safety hazard when generating.
Accompanying drawing explanation
Fig. 1 is the structural representation of the present invention.
Labelling and corresponding parts title in accompanying drawing: 1 pressure vessel;2 containments;3 reactor buildings;4— Jet chimney one;5 control valves one;6 steam turbine high-pressure cylinders;7 steam turbines;8 steam turbine Factory Buildings;9 condensers;10— Electromotor;11 control valves three;12 cooling towers;13 cooling water pumps;14 control valves two;15 condensate pumps;16 controls Valve four processed;17 feed-water heaters;18 feed pumps;19 control valves five;20 feed pipes;21 exhaustors;22 control Rod;23 constrain ponds;24 dry-wells;25 circulating pumps;26 circulation pipes;27 reactor fuel rods;28 steam-water separators; 29 connecting shafts;30 jet chimneys two;31 cooling tubes;32 water pumps;33 filler pipes;34 open and close valves;35 liquid levels Sensor.
Detailed description of the invention
Below in conjunction with embodiment and accompanying drawing, the present invention is described in further detail, but embodiments of the present invention are not It is only limitted to this.
Embodiment:
As it is shown in figure 1, a kind of system of safety coefficient when can improve nuclear energy power generation, including reactor building 3, steam turbine Factory Building 8 and cooling tower 12, described reactor building 3 is provided with containment 2, containment 2 is provided with pressure vessel 1, pressure vessel 1 In be provided with steam-water separator 28 and reactor fuel rod 27, and reactor fuel rod 27 be arranged on steam-water separator 28 underface and Being connected with steam-water separator 28, be provided with control rod 22 in the bottom of pressure vessel 1, control rod 22 is arranged in containment 2, peace Being additionally provided with circulation pipe 26 in full shell 2, the two ends of circulation pipe 26 all connect with pressure vessel 1, and connectivity part is positioned at soda pop and divides Below device 28, circulation pipe 26 is provided with circulating pump 25, reactor building 3 is provided with constrain pond 23, constrain water Pond 23 is communicated with exhaustor 21, and exhaustor 21 connects with constrain pond 23 and containment 2 inside simultaneously, sets in constrain pond 23 Being equipped with liquid level sensor 35, be provided with filler pipe 33 below constrain pond 23, filler pipe 33 connects with the bottom in constrain pond 23 Logical, and on filler pipe 33, it is provided with open and close valve 34 and water pump 32, open and close valve 34 can completely cut through filler pipe 33, open and close valve 34 It is arranged between water pump 32 and constrain pond 23, and liquid level sensor 35 is connected with open and close valve 34 and water pump 32 by data wire simultaneously Connect;Described steam turbine Factory Building 8 is provided with steam turbine high-pressure cylinder 6, steam turbine 7 and electromotor 10, steam turbine high-pressure cylinder 6 is arranged Having connecting shaft 29, steam turbine 7 to be arranged in connecting shaft 29, and connecting shaft 29 is connected with electromotor 10, steam turbine high-pressure cylinder 6 is even Being connected to jet chimney 1, jet chimney 1 is connected with steam turbine high-pressure cylinder 6 and pressure vessel 1 simultaneously, and jet chimney 1 On be provided with control valve 1, control valve 1 can completely cut through jet chimney 1, and control valve 1 is arranged on reactor factory In room 8;Below steam turbine 7, it is provided with condenser 9, condenser 9 is provided with jet chimney 2 30, jet chimney 2 30 and vapour Being connected with steam turbine high-pressure cylinder 6 after turbine 7 connection again, be provided with cooling tube 31 in condenser 9, the two ends of cooling tube 31 are all with cold But tower 12 connects, and is provided with cooling water pump 13, control valve 2 14 and control valve 3 11, cooling water pump 13, control on cooling tube 31 Valve 2 14 processed and control valve 3 11 are arranged in steam turbine Factory Building 8, and control valve 2 14 is arranged on cooling water pump 13 and condenser 9 Between, control valve 3 11 is arranged between condenser 9 and cooling tower 12, is provided with feed pipe 20, feed pipe 20 on condenser 9 Connecting with pressure vessel 1, the connectivity part of feed pipe 20 and pressure vessel 1 is positioned at jet chimney 1 and the connectivity part of pressure vessel 1 Lower section, feed pipe 20 is provided with condensate pump 15, feed-water heater 17, feed pump 18, control valve 4 16 and control valve 5 19, condensate pump 15 is arranged between feed-water heater 17 and condenser 9, control valve 4 16 be arranged on condensate pump 15 and and Between feed-water heater 17, feed pump 18 is arranged between pressure vessel 1 and feed-water heater 17, and control valve 5 19 is arranged on pressure Between force container 1 and feed pump 18;The quantity of described steam turbine 7 is three, and three steam turbines 7 are sequentially arranged at connecting shaft 29 On, jet chimney 2 30 connects with three steam turbines 7 respectively;The quantity in described constrain pond 23 is two, and is arranged at peace The lower section of full shell 2, two constrain ponds 23 are symmetrical arranged along the centrage of containment 2, and two constrain ponds 23 are all by arranging Trachea 21 is internal with containment 2 to be connected, and filler pipe 33 is connected with two constrain ponds 23 simultaneously, in each constrain pond 23 all It is provided with liquid level sensor 35.In the present embodiment, the cavity within containment 2 is also referred to as dry-well 24, and constrain pond 23 Also referred to as wet-well, since being wet-well, then illustrates when generator operation, needs to be carved with when keeping the state of water in constrain pond 23, But when actually used, not being monitored constrain pond 23 middle water level, be all that artificial experience is added, this existence is the biggest Potential safety hazard, therefore this programme adds liquid level sensor 35 and is monitored the water level in constrain pond 23, works as water level Time too low, open open and close valve 34 and water pump 32 to add water, after reaching designated water level, close open and close valve 34 and water pump 32, it is achieved Automatically controlling, it is ensured that the water level in constrain pond 23 meets the requirements, prevent constrain pond 23 from drying up, its program used is existing There is program, it is achieved synchronize to open.Circulation pipe 26 is two, and it is symmetricly set on pressure vessel 1 both sides, on every circulation pipe 26 It is fitted with circulating pump 25 for keeping recycling to steam, pressure vessel 1 is provided with steam-water separator 28, passes through heap Core fuel rod 27 action, high temperature makes the water of inside be evaporated producing steam, and the water of operative liquid is returned to by exhaustor 21 In constrain pond 23, and the top of pressure vessel 1 cavity is to there is a large amount of steam, and it enters into steamer by jet chimney 1 In machine high pressure cylinder 6, producing high pressure under the effect of steam turbine high-pressure cylinder 6, then pushing turbine 7 rotates and carries out so that generating Machine 10 generates electricity, and the electric energy of generation exports the place needed by power transmission network, after Steam Actuation steam turbine 7 rotates, and its pressure Power is used for pushing turbine 7 and does work, but its high temperature still possessed, it is impossible to it is directly discharged in air, so being provided with Condenser 9, utilizes condenser 9 that high-temperature steam carries out cooling condensation, enters back in cooling tower 12 and discharge after cooling, and part is steamed The water that vapour condenses into, at condenser 9 congregate, is again passed in pressure vessel 1 by feed pipe 20 and uses, it is achieved Recycling to water resource, and in order to increase the efficiency of feed pipe 20 water delivery, and it can keep pressure vessel 1 center Efficiency when can generate electricity, will install water pump in feed pipe 20 so that it meets requirement, and owing to existing in pressure vessel 1 High temperature, the water of feed pipe 20 input was condensed by condenser, if directly inputted, then the temperature difference produced is easily caused safety Accident, so being provided with feed-water heater 17 on feed pipe 20, preheats feedwater, reduces the temperature difference, thus ensures fortune Row safety, and this programme is provided with multiple control valve the most in the duct and is controlled pipeline so that and safety coefficient is higher, Also improving the utilization rate of nuclear energy, this system can take maltilevel security measure when utilizing nuclear energy power generation, improves safety Coefficient so that power generation process is safer, it is more lasting to run, and the utilization rate for nuclear energy is higher, solves existing nuclear energy and sends out In electricity structure, owing to structure design is unreasonable so that there is nuclear energy uses rate during generating low, safety precautions is not in place, The problem that there is the biggest potential safety hazard during generating.
The above, be only presently preferred embodiments of the present invention, and the present invention not does any pro forma restriction, every depends on Any simple modification of substantially being made above example according to the technology of the present invention, method, equivalent variations, each fall within the present invention Protection domain within.

Claims (3)

1. the system of safety coefficient when can improve nuclear energy power generation, it is characterised in that: include reactor building (3), steamer Machine Factory Building (8) and cooling tower (12), be provided with containment (2) in described reactor building (3), containment is provided with pressure in (2) Force container (1), is provided with steam-water separator (28) and reactor fuel rod (27), and reactor fuel rod (27) in pressure vessel (1) It is arranged on the underface of steam-water separator (28) and is connected with steam-water separator (28), being provided with in the bottom of pressure vessel (1) Control rod (22), control rod (22) is arranged in containment (2), is additionally provided with circulation pipe (26), circulation pipe in containment (2) (26) two ends all connect with pressure vessel (1), and connectivity part is positioned at steam-water separator (28) lower section, on circulation pipe (26) Being provided with circulating pump (25), be provided with constrain pond (23) in reactor building (3), constrain pond (23) are communicated with exhaustor (21), and exhaustor (21) connects with constrain pond (23) and containment (2) inside simultaneously, and constrain pond is provided with liquid in (23) Level sensor (35), is provided with the end in filler pipe (33), filler pipe (33) and constrain pond (23) in constrain pond (23) lower section Portion connects, and is provided with open and close valve (34) and water pump (32) on filler pipe (33), and open and close valve (34) can completely cut through and add water Pipe (33), open and close valve (34) is arranged between water pump (32) and constrain pond (23), and liquid level sensor (35) passes through data wire It is connected with open and close valve (34) and water pump (32) simultaneously;Described steam turbine Factory Building (8) is provided with steam turbine high-pressure cylinder (6), steamer Machine (7) and electromotor (10), steam turbine high-pressure cylinder (6) is provided with connecting shaft (29), and steam turbine (7) is arranged on connecting shaft (29) On, and connecting shaft (29) is connected with electromotor (10), and steam turbine high-pressure cylinder (6) connects jet chimney one (4), jet chimney One (4) is connected with steam turbine high-pressure cylinder (6) and pressure vessel (1) simultaneously, and is provided with control valve one on jet chimney one (4) (5), control valve one (5) can completely cut through jet chimney one (4), and control valve one (5) is arranged in reactor building (8); Steam turbine (7) lower section is provided with condenser (9), condenser (9) is provided with jet chimney two (30), jet chimney two (30) It is connected with steam turbine high-pressure cylinder (6) again after connecting with steam turbine (7), condenser (9) is provided with cooling tube (31), cooling tube (31) two ends all connect with cooling tower (12), cooling tube (31) is provided with cooling water pump (13), control valve two (14) and Control valve three (11), cooling water pump (13), control valve two (14) and control valve three (11) be arranged in steam turbine Factory Building (8), Control valve two (14) is arranged between cooling water pump (13) and condenser (9), and control valve three (11) is arranged on condenser (9) and cold But between tower (12), being provided with feed pipe (20) on condenser (9), feed pipe (20) connects with pressure vessel (1), feed pipe And the connectivity part of pressure vessel (1) is positioned at the lower section of connectivity part of jet chimney one (4) and pressure vessel (1), in feedwater (20) It is provided with condensate pump (15), feed-water heater (17), feed pump (18), control valve four (16) and control valve five on pipe (20) (19), condensate pump (15) is arranged between feed-water heater (17) and condenser (9), and control valve four (16) is arranged on condensation water Pump (15) and and feed-water heater (17) between, feed pump (18) is arranged between pressure vessel (1) and feed-water heater (17), Control valve five (19) is arranged between pressure vessel (1) and feed pump (18).
A kind of system of safety coefficient when can improve nuclear energy power generation the most according to claim 1, it is characterised in that: described The quantity of steam turbine (7) is three, and three steam turbines (7) are sequentially arranged in connecting shaft (29), and jet chimney two (30) is respectively Connect with three steam turbines (7).
A kind of system of safety coefficient when can improve nuclear energy power generation the most according to claim 1, it is characterised in that: described The quantity in constrain pond (23) is two, and is arranged at the lower section of containment (2), and two constrain ponds (23) are along containment (2) centrage is symmetrical arranged, and two constrain ponds (23) all connect by exhaustor (21) and containment (2) are internal, add water Pipe (33) is connected with two constrain ponds (23) simultaneously, is provided with liquid level sensor (35) in each constrain pond (23).
CN201610500784.3A 2016-06-30 2016-06-30 A kind of system of safety coefficient when can improve nuclear energy power generation Pending CN106128536A (en)

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110957052A (en) * 2018-09-26 2020-04-03 中国船舶重工集团公司第七一九研究所 Nuclear power platform water supplementing system and water supplementing method
CN114242284A (en) * 2021-12-17 2022-03-25 中国核动力研究设计院 Nuclear reactor thermal hydraulic test system and regulation and control method

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2012255660A (en) * 2011-06-07 2012-12-27 Tohoku Univ Powerless reactor cooling system
CN103000236A (en) * 2011-09-08 2013-03-27 韩电原子力燃料株式会社 Passive apparatus for cooling spent fuel storage tub
CN202855316U (en) * 2012-09-11 2013-04-03 中科华核电技术研究院有限公司 Containment cooling system for PWR (pressurized water reactor) nuclear power plant
CN103489488A (en) * 2012-06-11 2014-01-01 中国核动力研究设计院 Module type pressurized water reactor
CN204760043U (en) * 2015-06-17 2015-11-11 中科华核电技术研究院有限公司 Containment that two -stage is constrain and constrain pond system thereof
CN105047235A (en) * 2015-06-09 2015-11-11 中国核动力研究设计院 Melt in-pile retention passive cooling system in nuclear reactor severe accident state

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2012255660A (en) * 2011-06-07 2012-12-27 Tohoku Univ Powerless reactor cooling system
CN103000236A (en) * 2011-09-08 2013-03-27 韩电原子力燃料株式会社 Passive apparatus for cooling spent fuel storage tub
CN103489488A (en) * 2012-06-11 2014-01-01 中国核动力研究设计院 Module type pressurized water reactor
CN202855316U (en) * 2012-09-11 2013-04-03 中科华核电技术研究院有限公司 Containment cooling system for PWR (pressurized water reactor) nuclear power plant
CN105047235A (en) * 2015-06-09 2015-11-11 中国核动力研究设计院 Melt in-pile retention passive cooling system in nuclear reactor severe accident state
CN204760043U (en) * 2015-06-17 2015-11-11 中科华核电技术研究院有限公司 Containment that two -stage is constrain and constrain pond system thereof

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110957052A (en) * 2018-09-26 2020-04-03 中国船舶重工集团公司第七一九研究所 Nuclear power platform water supplementing system and water supplementing method
CN114242284A (en) * 2021-12-17 2022-03-25 中国核动力研究设计院 Nuclear reactor thermal hydraulic test system and regulation and control method
CN114242284B (en) * 2021-12-17 2024-05-28 中国核动力研究设计院 Nuclear reactor thermal hydraulic test system and regulation and control method

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Application publication date: 20161116