CN106297915A - A kind of passive safety injection system for nuclear power station - Google Patents
A kind of passive safety injection system for nuclear power station Download PDFInfo
- Publication number
- CN106297915A CN106297915A CN201510238671.6A CN201510238671A CN106297915A CN 106297915 A CN106297915 A CN 106297915A CN 201510238671 A CN201510238671 A CN 201510238671A CN 106297915 A CN106297915 A CN 106297915A
- Authority
- CN
- China
- Prior art keywords
- steam
- peace
- secondary side
- passive
- containment
- 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.)
- Granted
Links
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to a kind of passive safety injection system for nuclear power station, including cistern in containment, feed pipe, feedwater isolation valve, passive peace steam injection wheel pump, the relief valve of vaporizer secondary side, steam discharge pipe, peace note pipe, cooling water and peace note isolating valve, in containment, the bottom of cistern is higher than the top of U-tube, cooling water leaves in containment in cistern, in containment, cistern is connected with passive peace steam injection wheel pump with the feedwater isolation valve being arranged on feed pipe by feed pipe, passive peace steam injection wheel pump connect with vaporizer secondary side by the relief valve of steam discharge pipe and the vaporizer secondary side being disposed thereon and pass through peace note and manages and be arranged on and pacify the peace noted on pipe and note isolating valve and connect with vaporizer secondary side.When steam generator secondary side liquid level is reduced to low liquid level, it is carried out reliable passive moisturizing so that steam generator secondary side persistently sets out reactor core waste heat.
Description
Technical field
The present invention relates to a kind of passive safety injection system, in particular to a kind of passive safety injection system for nuclear power station.
Background technology
The nuclear power of safety is the clean energy resource of a kind of high-energy source density, to preserving the ecological environment, readjust the energy structure and ensure that energy security has important effect.But once safety problem occurs in nuclear power station, then staff, nearby residents and ecological environment etc. can be brought huge threat.For this nuclear plant safety problem be people apply nuclear power time must the problem that considers of emphasis.Nuclear power station tends to use non-passive safety technical finesse accident at present.So-called non-passive safety technology refers to utilize natural agent to complete various refrigerating function in the case of having an accident, and the driving force etc. that wherein natural agent can be produced by gravity, pressure accumulation gas pressure, Natural Circulation produces, it is not necessary to pump and external power source.Therefore, while improve nuclear plant safety reliability, it is greatly simplified the security system of nuclear power station of knowing clearly.
The nuclear power station of prior art includes the reactor core waste heat that primary heat transport system and the reactor core emergency cooling system reactor core emergency cooling system communicated therewith produce for taking away reactor core remnants in primary heat transport system to fission when having an accident.
Fig. 1 shows the primary heat transport system of current passive nuclear power station.nullAs shown in Figure 1,The primary heat transport system of current passive nuclear power station includes steam generator 6、U-tube 5、Primary heat transport system cold section 3、Primary heat transport system hot arc 4、Main pump 9、Reactor pressure vessel 2、It is positioned at the reactor core 1 of reactor pressure vessel 2、Surge line piping 10 and manostat 11,During wherein U-tube 5 is arranged on steam generator 6,The U-tube port of export is pooled to the cold chamber compartment 7 of steam generator bottom,Cold chamber compartment 7 is connected for cold with primary heat transport system section 3 by main pump 9,Primary heat transport system connects with reactor pressure vessel 2 for cold section 3,Reactor pressure vessel 2 also connects with primary heat transport system hot arc 4,Primary heat transport system hot arc 4 is connected with manostat 11 by Surge line piping 10 and passes through the hot chamber compartment 8 of steam generator bottom and connects with the arrival end of U-tube 5,Coolant enters reactor pressure vessel 2 for cold section 3 by primary heat transport system,Arrive the entrance of reactor core 1,The Q-value that reactor core produces is taken away when flowing through reactor core 1,Heated coolant (such as temperature is of about 321 DEG C) flows through primary heat transport system hot arc 4,Arrive the hot chamber compartment 8 of steam generator bottom and enter the arrival end of U-tube 5,Coolant in transferring heat to steam generator 6 by U-tube 5 and outside U-tube 5,Coolant temperature in U-tube 5 reduces (such as coolant temperature is 280 DEG C) and collects in steam generator bottom cold chamber compartment 7 by the port of export of U-tube,In cold chamber compartment, the coolant of 7 pumps into primary heat transport system cold section 3 by main pump 9,Turn again to reactor pressure vessel 2,Form the enclosed cooling circulation of primary heat transport system.In Fig. 1, arrow F1 is the coolant flow direction that temperature is relatively low, and arrow F2 is that the coolant that temperature is higher flows to.
For the pressure of stable primary heat transport system, primary heat transport system hot arc 4 is connected with manostat 11 by Surge line piping 10, is saturated solution and saturated vapor (for example, cooling water saturation liquid and saturated vapor), meets the voltage stabilizing requirement of primary heat transport system in manostat 11.Manostat 11 for maintaining properly functioning high pressure conditions (such as about 15.5MPa) by the pressure of primary heat transport system so that during reactor core 1 reaction in normal operation, the coolant in reactor pressure vessel 2 does not haves boiling.The cooling water of reacted heap reactor core 1 heating is when flowing through U-tube 5, cooling water in transferring heat to steam generator 6 and outside U-tube 5, the cooling water evaporation in steam generator 6 is made to form steam, in steam generator 6, steam passes through main steam pipe 12, it is fed to steam wheel pump (not shown in figure 1) by normally opened main steam isolation valve 13, drive the generating of steam wheel pump, thus the heat that reactor core produces is changed into electric energy.
In the case of nuclear power station generation is fully powered-off, owing to main steam isolation valve 13 is closed, the steam that saturation water evaporation in the secondary side of steam generator (space in steam generator 6 and outside U-tube 5) produces cannot flow to steam wheel pump (not shown in figure 1), and the secondary side of steam generator cannot utilize normal operation mode to take away reactor core remnants and fission the reactor core waste heat produced.Now, first passive nuclear power station relies on the Natural Circulation of primary heat transport system, a part of reactor core waste heat is passed to steam generator secondary side by the U-shaped heat-transfer pipe in steam generator, the saturated cooling water having in making steam generator secondary side constantly absorbs heat evaporation, in causing steam generator secondary side, pressure raises, when pressure is increased to the unlatching pressure of steam generator secondary side relief valve setting (such as 7.8MPa), steam generator secondary side relief valve is opened, high steam is discharged in containment, to steam generator secondary side pressure release, when pressure drop is as little as when the closing presure that steam generator secondary side relief valve sets (such as 7.6MPa), steam generator secondary side relief valve cuts out.After steam generator secondary side relief valve cuts out, steam generator secondary side raises again owing to the lasting heat exchange of U-tube absorbs its internal pressure of reactor core waste heat, the open and close and so forth of steam generator secondary side relief valve, discharge steam, until steam generator secondary side liquid level is reduced to the low liquid level that steam generator secondary side sets.Now, if reactor core waste heat cannot be continued to take away, then will have an accident.
Thus, need to provide a kind of passive safety injection system for nuclear power station, when steam generator secondary side liquid level is reduced to low liquid level, it is carried out reliable passive moisturizing, steam generator secondary side is made persistently to set out reactor core waste heat, reduce the risk that reactor core is exposed, response time after prolongation accident, improve the safety allowance of nuclear power station.
Summary of the invention
It is an object of the invention to provide a kind of passive safety injection system for nuclear power station, it can utilize passive mode that vaporizer secondary side persistently carries out moisturizing in the case of nuclear power station is fully powered-off, steam generator secondary side is made persistently to set out reactor core waste heat, it is to avoid to have an accident.
nullOne embodiment of the invention provides a kind of passive safety injection system for nuclear power station,The primary heat transport system of nuclear power station includes steam generator and the U-tube being positioned in containment,Wherein the passive safety injection system for nuclear power station includes cistern in containment、Feed pipe、Feedwater isolation valve、Passive peace steam injection wheel pump、The relief valve of vaporizer secondary side、Steam discharge pipe、Peace note pipe、Cooling water and peace note isolating valve,In containment, the bottom of cistern is higher than the top of U-tube,Cooling water leaves in containment in cistern,In containment, cistern is connected with passive peace steam injection wheel pump with the feedwater isolation valve being arranged on feed pipe by feed pipe,Passive peace steam injection wheel pump connect with vaporizer secondary side by the relief valve of steam discharge pipe and the vaporizer secondary side being disposed thereon and pass through peace note and manages and be arranged on and pacify the peace noted on pipe and note isolating valve and connect with vaporizer secondary side.
The passive safety injection system for nuclear power station that said one embodiment according to the present invention provides, wherein when having an accident, the pressure of steam generator secondary side raises, the relief valve of vaporizer secondary side is opened, discharging steam by steam discharge pipe, the steam of discharge takes away the decay heat of reactor core;The steam discharged is imported into passive peace steam injection wheel pump, promote passive peace steam injection wheel pump, cooling water in cistern in containment via feed pipe and the feedwater isolation valve that is arranged on feed pipe and is delivered to steam generator secondary side by peace note pipe and the peace note pump isolation valve that is arranged on peace note pipe and is carried out moisturizing by passive peace steam injection wheel pump, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube keeps being submerged;Now the primary side hot water in U-tube is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve of steam generator secondary side, the steam discharged is imported into passive peace steam injection wheel pump, passive peace steam injection wheel pump, passive peace steam injection wheel pump is promoted then to continue to add in steam generator by the cooling water in cistern in containment.
The passive safety injection system for nuclear power station that said one embodiment according to the present invention provides, wherein nuclear power station includes primary heat transport system and the reactor core emergency cooling system communicated therewith, the reactor core waste heat that reactor core emergency cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident.
nullAnother embodiment of the present invention provides a kind of passive safety injection system for nuclear power station,The primary heat transport system of nuclear power station includes steam generator and the U-tube being positioned in containment,Wherein the passive safety injection system for nuclear power station includes cistern in containment、Feed pipe、Feedwater isolation valve、Passive peace injected current pump、The relief valve of vaporizer secondary side、Steam discharge pipe、Peace note pipe、Cooling water and peace note isolating valve,In containment, the bottom of cistern is higher than the top of U-tube,Cooling water leaves in containment in cistern,In containment, cistern is connected with passive peace injected current pump with the feedwater isolation valve being arranged on feed pipe by feed pipe,Passive peace injected current pump connect with vaporizer secondary side by the relief valve of steam discharge pipe and the vaporizer secondary side being disposed thereon and pass through peace note and manages and be arranged on and pacify the peace noted on pipe and note isolating valve and connect with vaporizer secondary side.
The passive safety injection system for nuclear power station provided according to another embodiment of the present invention, wherein when having an accident, the pressure of steam generator secondary side raises, the relief valve of vaporizer secondary side is opened, discharging steam by steam discharge pipe, the steam of discharge takes away the decay heat of reactor core;The steam discharged is imported into passive peace injected current pump, promote passive peace injected current pump, cooling water in cistern in containment via feed pipe and the feedwater isolation valve that is arranged on feed pipe and is delivered to steam generator secondary side by peace note pipe and the peace note pump isolation valve that is arranged on peace note pipe and is carried out moisturizing by passive peace injected current pump, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube keeps being submerged;Now the primary side hot water in U-tube is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve of steam generator secondary side, the steam discharged is imported into passive peace injected current pump, passive peace injected current pump, passive peace injected current pump is promoted then to continue to add in steam generator by the cooling water in cistern in containment.
The passive safety injection system for nuclear power station according to the present invention runs in passive mode, all the time in guaranteeing vaporizer secondary side, liquid level is maintained at normal level scope, coolant in U-tube is cooled, the steam that saturation water heating evaporation in vaporizer secondary side produces is discharged in containment by the relief valve of vaporizer secondary side, in containment, the cooling water in cistern adds in steam generator secondary side by continuing, so that the heat produced by reactor core in primary heat transport system is persistently taken away, reactor core is continuously cooled by, ensure that the safety of nuclear power station.
Accompanying drawing explanation
The above and other aspect of invention is discussed in detail, in accompanying drawing below in conjunction with accompanying drawing:
Fig. 1 is the passive PIPING OF MAIN LOOPS IN NUCLEAR POWER STATION system schematic of prior art.
Fig. 2 is the passive safety injection system for nuclear power station according to the present invention.
Part numbers and list
1 | Reactor core |
2 | Reactor pressure vessel |
3 | Cold section of primary heat transport system |
4 | Primary heat transport system hot arc |
5 | U-tube |
6 | Steam generator |
7 | Steam generator cold chamber compartment |
8 | Steam generator hot chamber compartment |
9 | Main pump |
10 | Surge line piping |
11 | Manostat |
12 | Main steam pipe |
13 | Main steam isolation valve |
20 | Passive peace steam injection wheel pump |
21 | The relief valve of vaporizer secondary side |
22 | Steam discharge pipe |
23 | Peace note isolating valve |
24 | Peace note pipe |
25 | Feed pipe |
26 | Cistern in containment |
27 | Feedwater isolation valve |
Detailed description of the invention
How Fig. 1-2 and the optional embodiment following description describing the present invention are implemented with teaching those of ordinary skill in the art and reproduce the present invention.In order to instruct technical solution of the present invention, simplify or eliminated some conventional aspects.It should be understood by one skilled in the art that and be derived from the modification of these embodiments or replace and will be within the scope of the present invention.It should be understood by one skilled in the art that following characteristics can combine to be formed multiple modification of the present invention in every way.Thus, the invention is not limited in following optional embodiment, and only limited by claim and their equivalent.
Fig. 2 is the passive safety injection system for nuclear power station according to the present invention.The passive safety injection system for nuclear power station according to the present invention includes cistern 26 in containment, feed pipe 25, feedwater isolation valve 27, passive peace steam injection wheel pump 20, the relief valve 21 of vaporizer secondary side, steam discharge pipe 22, peace note pipe 24, cooling water and peace note isolating valve 23.In containment, the bottom of cistern 26 is higher than the top of U-tube 5, cooling water leaves in containment in cistern 26, in containment, cistern 26 is connected with passive peace steam injection wheel pump 20 with the feedwater isolation valve 27 being arranged on feed pipe 25 by feed pipe 25, and passive peace steam injection wheel pump 20 connect with vaporizer secondary side by the relief valve 21 of steam discharge pipe 22 and the vaporizer secondary side being disposed thereon and passes through to pacify and notes pipe 24 and being arranged on and pacify the peace noted on pipe 24 and note isolating valve 23 and connect with vaporizer secondary side.
At accidental conditions, peace note isolating valve 23 is in the closed position.When having an accident, the pressure of steam generator secondary side raises, and the relief valve 21 of vaporizer secondary side is opened, and discharges steam by steam discharge pipe 22, and the steam of discharge takes away the decay heat of reactor core 1;The steam discharged is imported into passive peace steam injection wheel pump 20, promote passive peace steam injection wheel pump 20, feedwater isolation valve 27 that cooling water in cistern in containment 26 via feed pipe 25 and is arranged on feed pipe 25 by passive peace steam injection wheel pump 20 is also pumped into steam generator secondary side by peace note pipe 24 and the peace note isolating valve 23 that is arranged on peace note pipe 24 and carries out moisturizing, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube 5 keeps being submerged;Now the primary side hot water in U-tube 5 is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve 21 of steam generator secondary side, the steam discharged is imported into passive peace steam injection wheel pump 20, passive peace steam injection wheel pump 20, passive peace steam injection wheel pump 20 is promoted then to continue to add in steam generator 6 by the cooling water in cistern in containment 26.The heat of reactor core 1 generation being positioned at reactor pressure vessel 2 is persistently taken away, and reactor core 1 persistently cools down, it is ensured that reactor core safety.
In another embodiment of the present invention, being from Fig. 2, the passive safety injection system for nuclear power station of offer is different, passive peace injected current pump 20 replaces with passive peace injected current pump.At accidental conditions, peace note isolating valve 23 is in the closed position.When having an accident, the pressure of steam generator secondary side raises, and the relief valve 21 of vaporizer secondary side is opened, and discharges steam by steam discharge pipe 22, and the steam of discharge takes away the decay heat of reactor core 1;The steam discharged is imported into passive peace injected current pump, promote passive peace injected current pump, feedwater isolation valve 27 that cooling water in cistern in containment 26 via feed pipe 25 and is arranged on feed pipe 25 by passive peace injected current pump is also pumped into steam generator secondary side by peace note pipe 24 and the peace note isolating valve 23 that is arranged on peace note pipe 24 and carries out moisturizing, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube 5 keeps being submerged;Now the primary side hot water in U-tube 5 is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve 21 of steam generator secondary side, the steam discharged is imported into passive peace injected current pump, passive peace injected current pump, passive peace injected current pump is promoted then to continue to add in steam generator 6 by the cooling water in cistern in containment 26.The heat of reactor core 1 generation being positioned at reactor pressure vessel 2 is persistently taken away, and reactor core 1 persistently cools down, it is ensured that reactor core safety.
The passive safety injection system for nuclear power station according to the present invention runs in passive mode, all the time in guaranteeing vaporizer secondary side, liquid level is maintained at normal level scope, coolant in U-tube is cooled, the steam that saturation water heating evaporation in vaporizer secondary side produces is discharged in containment by the relief valve of vaporizer secondary side, in containment, the cooling water in cistern adds in steam generator secondary side by continuing, so that the heat produced by reactor core in primary heat transport system is persistently taken away, reactor core is continuously cooled by, ensure that the safety of nuclear power station.
Claims (5)
- null1. the passive safety injection system for nuclear power station,The primary heat transport system of nuclear power station includes steam generator and the U-tube being positioned in containment,It is characterized in that,Cistern within the passive safety injection system of nuclear power station includes containment、Feed pipe、Feedwater isolation valve、Passive peace steam injection wheel pump、The relief valve of vaporizer secondary side、Steam discharge pipe、Peace note pipe、Cooling water and peace note isolating valve,In containment, the bottom of cistern is higher than the top of U-tube,Cooling water leaves in containment in cistern,In containment, cistern is connected with passive peace steam injection wheel pump with the feedwater isolation valve being arranged on feed pipe by feed pipe,Passive peace steam injection wheel pump connect with vaporizer secondary side by the relief valve of steam discharge pipe and the vaporizer secondary side being disposed thereon and pass through peace note and manages and be arranged on and pacify the peace noted on pipe and note isolating valve and connect with vaporizer secondary side.
- 2. the passive safety injection system for nuclear power station as claimed in claim 1, it is characterised in that when having an accident, the pressure of steam generator secondary side raises, the relief valve of vaporizer secondary side is opened, and discharges steam by steam discharge pipe, and the steam of discharge takes away the decay heat of reactor core;The steam discharged is imported into passive peace steam injection wheel pump, promote passive peace steam injection wheel pump, cooling water in cistern in containment via feed pipe and the feedwater isolation valve that is arranged on feed pipe and is delivered to steam generator secondary side by peace note pipe and the peace note pump isolation valve that is arranged on peace note pipe and is carried out moisturizing by passive peace steam injection wheel pump, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube keeps being submerged;Now the primary side hot water in U-tube is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve of steam generator secondary side, the steam discharged is imported into passive peace steam injection wheel pump, passive peace steam injection wheel pump, passive peace steam injection wheel pump is promoted then to continue to add in steam generator by the cooling water in cistern in containment.
- 3. the passive safety injection system for nuclear power station as claimed in claim 1, it is characterized in that, nuclear power station includes primary heat transport system and the reactor core emergency cooling system communicated therewith, the reactor core waste heat that reactor core emergency cooling system produces for taking away reactor core remnants in primary heat transport system to fission when having an accident.
- null4. the passive safety injection system for nuclear power station,The primary heat transport system of nuclear power station includes steam generator and the U-tube being positioned in containment,It is characterized in that,Cistern within the passive safety injection system of nuclear power station includes containment、Feed pipe、Feedwater isolation valve、Passive peace injected current pump、The relief valve of vaporizer secondary side、Steam discharge pipe、Peace note pipe、Cooling water and peace note isolating valve,In containment, the bottom of cistern is higher than the top of U-tube,Cooling water leaves in containment in cistern,In containment, cistern is connected with passive peace injected current pump with the feedwater isolation valve being arranged on feed pipe by feed pipe,Passive peace injected current pump connect with vaporizer secondary side by the relief valve of steam discharge pipe and the vaporizer secondary side being disposed thereon and pass through peace note and manages and be arranged on and pacify the peace noted on pipe and note isolating valve and connect with vaporizer secondary side.
- Passive safety injection system for nuclear power station the most according to claim 4, it is characterized in that, when having an accident, the pressure of steam generator secondary side raises, the relief valve of vaporizer secondary side is opened, discharging steam by steam discharge pipe, the steam of discharge takes away the decay heat of reactor core;The steam discharged is imported into passive peace injected current pump, promote passive peace injected current pump, cooling water in cistern in containment via feed pipe and the feedwater isolation valve that is arranged on feed pipe and is delivered to steam generator secondary side by peace note pipe and the peace note pump isolation valve that is arranged on peace note pipe and is carried out moisturizing by passive peace injected current pump, steam generator secondary side is continuously obtained supplementing of cooling water, and U-tube keeps being submerged;Now the primary side hot water in U-tube is cooled, the cooling water of steam generator secondary side is then heated to saturated and produces steam, the steam produced is discharged by the relief valve of steam generator secondary side, the steam discharged is imported into passive peace injected current pump, passive peace injected current pump, passive peace injected current pump is promoted then to continue to add in steam generator by the cooling water in cistern in containment.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201510238671.6A CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201510238671.6A CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Publications (2)
Publication Number | Publication Date |
---|---|
CN106297915A true CN106297915A (en) | 2017-01-04 |
CN106297915B CN106297915B (en) | 2020-04-17 |
Family
ID=57631549
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201510238671.6A Active CN106297915B (en) | 2015-05-12 | 2015-05-12 | Passive safety injection system for nuclear power station |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN106297915B (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2020098490A1 (en) * | 2018-11-14 | 2020-05-22 | 中广核研究院有限公司 | Reactor and reactor coolant emergency injection system |
CN111446013A (en) * | 2020-04-24 | 2020-07-24 | 上海核工程研究设计院有限公司 | Marine environment secondary side passive waste heat removal system and use method |
CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
US11348699B2 (en) * | 2018-01-04 | 2022-05-31 | Korea Atomic Energy Research Institute | Cooling water safety injection device powered by steam discharged during an accident and nuclear power plant having the same |
CN115376395A (en) * | 2022-08-05 | 2022-11-22 | 国家电投集团科学技术研究院有限公司 | Full-process simulation test system for loss of coolant accident |
WO2022252359A1 (en) * | 2021-05-31 | 2022-12-08 | 上海核工程研究设计院有限公司 | Novel automatic depressurizing system and method for nuclear power plant |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
CN102693673A (en) * | 2012-06-04 | 2012-09-26 | 华北电力大学 | Simulation running apparatus for passive safety master system of pressurized water reactor nuclear island |
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
CN104064231A (en) * | 2013-03-21 | 2014-09-24 | 中广核(北京)仿真技术有限公司 | Low replacement material water-tank emergency coolant system outside nuclear reactor containment vessel |
-
2015
- 2015-05-12 CN CN201510238671.6A patent/CN106297915B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
CN102426864A (en) * | 2011-12-12 | 2012-04-25 | 曾祥炜 | Passive emergency cooling system for severe accident in reactor |
CN102693673A (en) * | 2012-06-04 | 2012-09-26 | 华北电力大学 | Simulation running apparatus for passive safety master system of pressurized water reactor nuclear island |
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
CN104064231A (en) * | 2013-03-21 | 2014-09-24 | 中广核(北京)仿真技术有限公司 | Low replacement material water-tank emergency coolant system outside nuclear reactor containment vessel |
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US11348699B2 (en) * | 2018-01-04 | 2022-05-31 | Korea Atomic Energy Research Institute | Cooling water safety injection device powered by steam discharged during an accident and nuclear power plant having the same |
WO2020098490A1 (en) * | 2018-11-14 | 2020-05-22 | 中广核研究院有限公司 | Reactor and reactor coolant emergency injection system |
CN111446013A (en) * | 2020-04-24 | 2020-07-24 | 上海核工程研究设计院有限公司 | Marine environment secondary side passive waste heat removal system and use method |
CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
CN112071454B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
WO2022252359A1 (en) * | 2021-05-31 | 2022-12-08 | 上海核工程研究设计院有限公司 | Novel automatic depressurizing system and method for nuclear power plant |
CN115376395A (en) * | 2022-08-05 | 2022-11-22 | 国家电投集团科学技术研究院有限公司 | Full-process simulation test system for loss of coolant accident |
CN115376395B (en) * | 2022-08-05 | 2023-11-10 | 国家电投集团科学技术研究院有限公司 | Full-process simulation test system for water loss accident |
Also Published As
Publication number | Publication date |
---|---|
CN106297915B (en) | 2020-04-17 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
CN106297915A (en) | A kind of passive safety injection system for nuclear power station | |
CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
CN204480678U (en) | A kind of nuclear power station Heat Discharging System of Chinese | |
CN102169733B (en) | Passive and active combined special safety system for nuclear power plant | |
CN103903659B (en) | Floating nuclear power plant Heat Discharging System of Chinese | |
CN204991158U (en) | A active gravity ann notes system of non - for nuclear power station | |
US20180350472A1 (en) | Passive safe cooling system | |
CN203134395U (en) | Underground nuclear power plant | |
CN204614459U (en) | A kind of non-active nuclear power station pressure release condensation heat exchange system | |
CN102163469A (en) | Nuclear power station non-active engineering safety system | |
CN104272397B (en) | steam generator for nuclear reactor | |
CN104733060A (en) | Passive residual heat removal system of marine nuclear power device | |
JP6067173B1 (en) | Geothermal exchanger and geothermal power generator | |
KR102115043B1 (en) | Underwater electricity generation module | |
US10762995B2 (en) | Shutdown cooling system and nuclear facility having same | |
WO2016078285A1 (en) | Secondary side passive waste heat removal system | |
CN107644693B (en) | Naval reactor and once through steam generator Passive residual heat removal system | |
US20170098483A1 (en) | Heat exchange system and nuclear reactor system | |
JP2012233698A (en) | Nuclear power plant emergency cooling system | |
CN113808764B (en) | Method and system for guiding out residual heat of reactor core in containment | |
CN104205239A (en) | System for discharging residual power of pressurized water nuclear reactor | |
CN107403650A (en) | The Passive residual heat removal system of floating nuclear power plant | |
JP2013228281A (en) | Emergency reactor core cooling system and nuclear reactor facilities provided with the same | |
CN205004049U (en) | A active pressure accumulation ann notes system of non - for nuclear power station |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |