CN104361913A - Secondary side passive waste heat removal system - Google Patents
Secondary side passive waste heat removal system Download PDFInfo
- Publication number
- CN104361913A CN104361913A CN201410663621.8A CN201410663621A CN104361913A CN 104361913 A CN104361913 A CN 104361913A CN 201410663621 A CN201410663621 A CN 201410663621A CN 104361913 A CN104361913 A CN 104361913A
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- China
- Prior art keywords
- containment
- steam generator
- water tank
- cooling water
- secondary side
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Classifications
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- 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
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- 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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- 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
-
- 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
Abstract
The invention discloses a secondary side passive waste heat removal system which comprises a steam pipeline and a water feeding pipeline, wherein the steam pipeline hermetically penetrates through a containment and is connected with the outlet of a steam generator in the containment as well as a cooling water tank which is arranged outside the containment; the water feeding pipeline hermetically penetrates through the containment and is connected with the cooling water tank and the inlet of the steam generator; the steam pipeline, the feeding water pipeline and the cooling water tank form a circulating channel so as to remove decay heat in the containment out of the containment. The steam pipeline and the feeding water pipeline are directly connected with the steam generator on the secondary side so as to prevent the steam generator from being burned and a coolant from being leaking. The cooling water tank is arranged outside the containment, so that available space of the containment is saved. Moreover, by using an open circuit, a heat exchanger which is required by the conventional passive waste heat removal system in the cooling water tank is not arranged, and no emergency equipment is required, so that the expenditure of design and construction of the system is lowered.
Description
Technical field
The present invention relates to nuclear plant safety apparatus field, particularly relating to a kind of secondary side passive residual heat guiding system of the PWR nuclear power plant for having once-through type steam generator.
Background technology
The use of nuclear power is the important breakthroughs of the mankind in energy utilization history, utilize nuclear fission reaction, the incomparable high-energy of other all traditional fossil energy can be produced export, and these high-energy export often only to be needed to expend a small amount of nuclear fuel, the characteristic of this low input high production, makes mankind's pay attention to day by day to the utilization of nuclear energy, and continues to increase the research and development in nuclear energy field, even to this day, nuclear energy has become the important energy source ingredient of many countries in the world.But; while nuclear power has high value, also may bring very large harm, in the process utilizing nuclear power; if protect improper and cause major accidents such as occurring nuclear leakage, extremely serious nuclear pollution disaster will be brought to the environment of nuclear power plant's periphery and even the whole mankind.
In nuclear power station, containment is the important safety facility of reactor, is to prevent radioactive product to be discharged into last one barrier in atmospheric environment.In the pressurized-water reactor nuclear power plant of active service, for ensureing that reactor is when design basis accident and beyond design basis accident occur, the decay heat of reactor core can both by lasting discharge, usually at primary side design residual heat removal system, cooling water tank is arranged in containment by this mode, occupies the free space of containment, but also need the newly-increased heat interchanger be positioned in material-changing water tank, thus the design of system and expenditure of construction are increased, once it is damaged that heat-transfer pipe occurs, also primary Ioops refrigerant leaks can be made.In addition, this residual heat removal system is under accident conditions, need the intervention of the power supply outside Chang Nei factory, emergency equipment (such as expensive Emergency diesel) and operator, this increases the risk of operator's human-equation error on the one hand, considerably increase number of devices on the other hand, increase the expense of equipment purchase, installation, operation and maintenance etc. thus, the construction cost of corresponding increase nuclear power plant and operation and maintenance expenses are used.
Therefore, be necessary to provide a kind of complete non-realize reactor core decay heat under accident actively derivation, reduce and build and the secondary side passive residual heat guiding system of O&M cost, to solve above-mentioned the deficiencies in the prior art.
Summary of the invention
The object of the present invention is to provide a kind of complete non-realize reactor core decay heat under accident actively derivation, reduce and build and the secondary side passive residual heat guiding system of O&M cost.
For achieving the above object, technical scheme of the present invention is: provide a kind of secondary side passive residual heat guiding system, for deriving the reactor core decay heat in containment, it comprises vapour line and water-supply line, described vapour line runs through containment and the outlet being connected to the steam generator be located in described containment and the cooling water tank be located at outside described containment hermetically, described water-supply line runs through described containment hermetically and is connected to the entrance of described cooling water tank and described steam generator, described vapour line, described water-supply line, described cooling water tank forms circulation passage the decay heat in described containment to be derived outside described containment.
Preferably, the position of described cooling water tank is higher than the position of described steam generator.
Preferably, the inlet end of described vapour line is connected to the outlet of described steam generator, and the endpiece of described vapour line stretches into below the liquid level of the chilled water in described cooling water tank.
Preferably, the inlet end of described water-supply line is connected to the bottom of described cooling water tank, and the endpiece of described water-supply line is connected to the entrance of described steam generator.
Preferably, described vapour line is provided with the first valve, and described first valve is positioned at described containment.
Preferably, described water-supply line is provided with the second valve and the 3rd valve, and described second valve is positioned at outside described containment, and described 3rd valve is positioned at described containment.
Preferably, the outlet of described steam generator is positioned at upper end, and the entrance of described steam generator is positioned at lower end.
Preferably, described steam generator is connected with the reactor pressure vessel in described containment, and described steam generator also connects main feed water pipe line and main steam pipe respectively.
Preferably, described main feed water pipe line is provided with the 4th valve, and described main steam pipe is provided with the 5th valve, and described 4th valve, described 5th valve are all positioned at described containment.
Preferably, described cooling water tank is uncovered setting.
Preferably, described steam generator is once-through type steam generator.
Compared with prior art, due to secondary side passive residual heat guiding system of the present invention, comprise vapour line and water-supply line, described vapour line runs through described containment and the outlet being connected to the steam generator be located in containment and the cooling water tank be located at outside containment hermetically, described water-supply line runs through described containment hermetically and is connected to the entrance of described cooling water tank and described steam generator, and described vapour line, described water-supply line, described cooling water tank form circulation passage the decay heat in described containment to be derived outside described containment.During accident, steam in steam generator enters cooling water tank through vapour line, be condensed in cooling water tank, water in cooling water tank flows back to steam generator through water-supply line, described circulation passage relies on density difference to form non-active natural convection loop, by the chilled water in heating cooling water tank by discharge of steam in air, after the cooling-water consumption in cooling water tank is complete, steam is directly discharged in air, therefore can the complete non-active discharge realizing reactor core decay heat after accident, reduce the possibility of thrashing greatly, it also avoid because lose the harm of factory's internal/external power and operator's human-equation error, improve the security of nuclear power plant, do not need emergency equipment, thus greatly reduce number of devices, reduce the expenses such as equipment purchase, installation, operation and maintenance, the construction cost of corresponding minimizing nuclear power plant and operation and maintenance expenses are used.In addition, vapour line, water-supply line are directly connected with the steam generator of secondary side, avoid steam generator under accident to dryout and the situation of refrigerant leaks occurs, cooling water tank is arranged at outside containment, save the free space of containment, and utilize open circuit, do not need to arrange the heat interchanger in the cooling water tank required for traditional Heat Discharging System of Chinese, reduce design and the expenditure of construction of system.
Accompanying drawing explanation
Fig. 1 is the structural representation of secondary side passive residual heat guiding system of the present invention.
Fig. 2 is the using state schematic diagram of secondary side passive residual heat guiding system of the present invention.
Fig. 3 is another using state schematic diagram of secondary side passive residual heat guiding system of the present invention.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, element numbers similar in accompanying drawing represents similar element.
As shown in Figure 1, secondary side passive residual heat guiding system 100 provided by the present invention, the complete non-derivation realizing reactor core decay heat in containment 110 under accident actively, and construction and O&M cost can be reduced.The reactor pressure vessel 120 be connected and steam generator 130 is provided with in described containment 110, generally speaking, PWR nuclear power plant is designed with two to four steam generators 130, only illustrate wherein one in the present embodiment, all the other steam generators 130 be set to technology well-known to those skilled in the art.And steam generator 130 is heat transmission equipments unique in native system, derive for primary Ioops heat.
In the present invention, described steam generator 130 is once-through type steam generator, once-through type steam generator (OTSG) is one of basis of the present invention, because the water loading amount of once-through type steam generator is less, therefore, the water of cooling water tank 150 (referring to aftermentioned) is easy to be full of once-through type steam generator, the Natural Circulation that initial formation is single-phase; According to traditional steam generator, then do not possess this ability.
Wherein, described secondary side passive residual heat guiding system 100 can only arrange one group, and this group secondary side passive residual heat guiding system 100 is corresponding with multiple steam generator 130 respectively; Certainly, also can arrange many group secondary side passive residual heat guiding systems 100, each group secondary side passive residual heat guiding system 100 is corresponding with a steam generator 130.
Continue below to consult shown in Fig. 1, the one group of secondary side passive residual heat guiding system 100 arranged for a corresponding steam generator 130, is described its structure.
As shown in Figure 1, described secondary side passive residual heat guiding system 100 comprises vapour line 140 and water-supply line 160, described vapour line 140 runs through described containment 110 and the outlet being connected to the steam generator 130 be located in containment 110 and the cooling water tank 150 be located at outside containment 110 hermetically, described water-supply line 160 runs through described containment 110 hermetically and is connected to the entrance of described cooling water tank 150 and described steam generator 130, described vapour line 140, water-supply line 160, cooling water tank 150 forms circulation passage the decay heat in described containment 110 to be derived outside described containment 110.
Particularly, described cooling water tank 150 is in uncovered setting, and the position of cooling water tank 150 is higher than the position of steam generator 130, cooling water tank 150 is built with the water yield can taken away in certain hour after accident needed for reactor core decay heat, arranged by a high position for cooling water tank 150, itself and steam generator 130 is made to form high potential difference needed for Natural Circulation, therefore, after vapour line 140 is communicated with water-supply line 160, chilled water in cooling water tank 150 automatically can enter steam generator 130 and be heated, and takes away primary Ioops heat; Because cooling water tank 150 is in uncovered setting, when the cooling water evaporation therefore in 150 is complete, steam is directly discharged in air through vapour line 140, does not need to add water in cooling water tank 150.And cooling water tank 150 is located at outside containment 110, the space in containment 110 need not be occupied, thus save the free space in containment 110.
Wherein, the outlet of described steam generator 130 is positioned at upper end, the entrance of steam generator 130 is positioned at lower end, the inlet end 140a of vapour line 140 is connected to the outlet of steam generator 130, the endpiece 140b of vapour line 140 inserts into the inner from the top of cooling water tank 150, and the endpiece 140b of vapour line 140 stretches into the following certain depth of liquid level of the chilled water in cooling water tank 150; The inlet end 160a of described water-supply line 160 is connected to the bottom of cooling water tank 150, and the endpiece 160b of described water-supply line 160 is connected to the entrance of described steam generator 130; Steam generator 130, vapour line 140, cooling water tank 150, water-supply line 160 form the circulation passage of open circuit, because vapour line 140, water-supply line 160 are directly connected with the steam generator 130 of secondary side, avoid steam generator 130 under accident and to dryout and the situation of primary Ioops refrigerant leaks occurs.
In addition, described vapour line 140 is provided with the first valve 141, and described first valve 141 is positioned at described containment 110.Described water-supply line 160 is provided with the second valve 161 and the 3rd valve 162, and described second valve 161 is positioned at outside containment 110, and the 3rd valve 162 is positioned at containment 110.When nuclear power plant normally runs, the first valve 141, second valve 161, the 3rd valve 162 are all closed; After accident, open the first valve 141, second valve 161 and the 3rd valve 162 to start described secondary side passive residual heat guiding system 100.
The present invention, one end of steam generator 130 is also connected with main feed water pipe line 170, and the outlet of steam generator 130 is also connected with main steam pipe 180.When nuclear power station normally runs, the heat energy that primary Ioops reactor core is huge because fuel fission produces, utilize the heat heated feed water of primary Ioops and produce steam, when steam passes through the heat-transfer pipe in steam generator 130, by tube wall heat energy passed to the secondary circuit chilled water outside heat-transfer pipe, the feedwater of release heat is sent back to reactor core by main pump again and is reheated and enter steam generator 130 again.Secondary circuit chilled water is heated thus becomes steam, and steam enters steam turbine acting by main steam pipe 180, thus is electric power thermal energy; Finish the steam after merit and enter condenser cooling, return steam generator 130 through main feed water pipe line 170 again after condensing into water, reheat into steam.
Wherein, described main feed water pipe line 170 is provided with the 4th valve 171, and described main steam pipe 180 is provided with the 5th valve 181, and described 4th valve 171, the 5th valve 181 are all positioned at containment 110, when nuclear power plant normally runs, the 4th valve 171, the 5th valve 181 are in open mode.
Shown in Fig. 1-Fig. 3, the principle of work of secondary side passive residual heat guiding system 100 of the present invention is described.
As shown in Figure 1, when nuclear power plant normally runs, described secondary side passive residual heat guiding system 100 does not start, but be in upstate, now, the first valve 141, second valve 161 and the 3rd valve 162 are in closed condition, and the 4th valve 171, the 5th valve 181 are in open mode.
As shown in Figure 2, under accident conditions (design basis accident is to beyond design basis accidents such as station blackouts), reactor shutdown, corresponding guard signal triggers described secondary side passive residual heat guiding system 100 and makes it start.Now, 4th valve 171, the 5th valve 181 are isolated, first valve 141, second valve 161, the 3rd valve 162 are opened successively, steam in steam generator 130 enters vapour line 140 by its outlet, cooling water tank 150 is entered again through the endpiece 140b of vapour line 140, be condensed in cooling water tank 150, the water in cooling water tank 150 flows back to steam generator 130 through water-supply line 160, relies on density difference to form non-active natural convection loop in described circulation passage.And steam is in cooling water tank 150 during condensation heat transfer, transfer heat to the chilled water in cooling water tank 150, early stage in accident, the temperature of the chilled water in cooling water tank 150 is due to heating and continuous rising, by the chilled water in heating cooling water tank 150 by discharge of steam in air, seethe with excitement after arriving 100 DEG C, the water level in cooling water tank 150 starts to decline gradually.
As shown in Figure 3, when after the cooling-water consumption certain hour in cooling water tank 150, the endpiece 140b of vapour line 140 is exposed in air, and steam is directly discharged in air, heat no longer enters cooling water tank 150, but the sustainable consumption of water in cooling water tank 150 is until emptying.When after the complete a period of time of the cooling-water consumption in cooling water tank 150, if not to cooling water tank 150 moisturizing, then systemic-function is lost.
Vapour line 140, water-supply line 160 are directly connected with the steam generator 130 of secondary side and form open circulation loop by the present invention, can the complete non-active discharge realizing reactor core decay heat after accident, reduce the possibility of thrashing greatly.
Due to secondary side passive residual heat guiding system 100 of the present invention, comprise vapour line 140 and water-supply line 160, described vapour line 140 runs through described containment 110 and the outlet being connected to the steam generator 130 be located in containment 110 and the cooling water tank 150 be located at outside containment 110 hermetically, described water-supply line 160 runs through described containment 110 hermetically and is connected to the entrance of described cooling water tank 150 and described steam generator 130, described vapour line 140, described water-supply line 160, described cooling water tank 150 forms circulation passage the decay heat in described containment 110 to be derived outside described containment 110.During accident, steam in steam generator 130 enters cooling water tank 150 through vapour line 140, be condensed in cooling water tank 150, chilled water in cooling water tank 150 flow back into steam generator 130 through water-supply line 160, density difference is relied on to form non-active natural convection loop in described circulation passage, by the chilled water in heating cooling water tank 150 by discharge of steam in air, after the cooling-water consumption in cooling water tank 150 is complete, steam is directly discharged in air, therefore can the complete non-active discharge realizing reactor core decay heat after accident, reduce the possibility of thrashing greatly, it also avoid because lose the harm of factory's internal/external power and operator's human-equation error, improve the security of nuclear power plant, do not need emergency equipment, thus greatly reduce number of devices, reduce the expenses such as equipment purchase, installation, operation and maintenance, the construction cost of corresponding minimizing nuclear power plant and operation and maintenance expenses are used.In addition, vapour line 140, water-supply line 160 are directly connected with the steam generator 130 of secondary side, avoid steam generator 130 under accident and to dryout and the situation of refrigerant leaks occurs; And cooling water tank 150 is arranged at outside containment 110, save the free space of containment 110; And utilize open circuit, do not need to arrange the heat interchanger in the cooling water tank 150 required for traditional Heat Discharging System of Chinese, reduce design and the expenditure of construction of system.
The setting of reactor pressure vessel 120 and steam generator 130 in the present invention, for well known to those of ordinary skill in the art, is no longer described in detail at this.
Above disclosedly be only the preferred embodiments of the present invention, certainly can not limit the interest field of the present invention with this, therefore according to the equivalent variations that the present patent application the scope of the claims is done, still belong to the scope that the present invention is contained.
Claims (11)
1. a secondary side passive residual heat guiding system, for deriving the reactor core decay heat in containment, it is characterized in that: comprise vapour line and water-supply line, described vapour line runs through containment and the outlet being connected to the steam generator be located in described containment and the cooling water tank be located at outside described containment hermetically, described water-supply line runs through described containment hermetically and is connected to the entrance of described cooling water tank and described steam generator, described vapour line, described water-supply line, described cooling water tank forms circulation passage the decay heat in described containment to be derived outside described containment.
2. secondary side passive residual heat guiding system as claimed in claim 1, is characterized in that: the position of described cooling water tank is higher than the position of described steam generator.
3. secondary side passive residual heat guiding system as claimed in claim 1, it is characterized in that: the inlet end of described vapour line is connected to the outlet of described steam generator, the endpiece of described vapour line stretches into below the liquid level of the chilled water in described cooling water tank.
4. secondary side passive residual heat guiding system as claimed in claim 1, it is characterized in that: the inlet end of described water-supply line is connected to the bottom of described cooling water tank, the endpiece of described water-supply line is connected to the entrance of described steam generator.
5. secondary side passive residual heat guiding system as claimed in claim 1, it is characterized in that: described vapour line is provided with the first valve, described first valve is positioned at described containment.
6. secondary side passive residual heat guiding system as claimed in claim 1, it is characterized in that: described water-supply line is provided with the second valve and the 3rd valve, and described second valve is positioned at outside described containment, described 3rd valve is positioned at described containment.
7. secondary side passive residual heat guiding system as claimed in claim 1, it is characterized in that: the outlet of described steam generator is positioned at upper end, the entrance of described steam generator is positioned at lower end.
8. secondary side passive residual heat guiding system as claimed in claim 1, is characterized in that: described steam generator is connected with the reactor pressure vessel in described containment, and described steam generator also connects main feed water pipe line and main steam pipe respectively.
9. secondary side passive residual heat guiding system as claimed in claim 8, it is characterized in that: described main feed water pipe line is provided with the 4th valve, described main steam pipe is provided with the 5th valve, and described 4th valve, described 5th valve are all positioned at described containment.
10. secondary side passive residual heat guiding system as claimed in claim 1, is characterized in that: described cooling water tank is uncovered setting.
11. secondary side passive residual heat guiding systems as claimed in claim 1, is characterized in that: described steam generator is once-through type steam generator.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410663621.8A CN104361913A (en) | 2014-11-19 | 2014-11-19 | Secondary side passive waste heat removal system |
| GB1600378.2A GB2535848B (en) | 2014-11-19 | 2015-03-31 | Secondary side passive residual heat removal system |
| PCT/CN2015/075498 WO2016078285A1 (en) | 2014-11-19 | 2015-03-31 | Secondary side passive waste heat removal system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410663621.8A CN104361913A (en) | 2014-11-19 | 2014-11-19 | Secondary side passive waste heat removal system |
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| Publication Number | Publication Date |
|---|---|
| CN104361913A true CN104361913A (en) | 2015-02-18 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
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| CN201410663621.8A Pending CN104361913A (en) | 2014-11-19 | 2014-11-19 | Secondary side passive waste heat removal system |
Country Status (3)
| Country | Link |
|---|---|
| CN (1) | CN104361913A (en) |
| GB (1) | GB2535848B (en) |
| WO (1) | WO2016078285A1 (en) |
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|---|---|---|---|---|
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| CN107727421A (en) * | 2017-09-14 | 2018-02-23 | 中广核研究院有限公司 | The experimental system of model steam generator secondary side operating mode |
| CN108447570A (en) * | 2018-05-15 | 2018-08-24 | 中广核研究院有限公司 | Naval reactor and its Passive residual heat removal system |
| CN108831573A (en) * | 2018-06-28 | 2018-11-16 | 哈尔滨工程大学 | A kind of nuclear power station secondary side passive residual heat removal security system |
| CN109903862A (en) * | 2019-02-20 | 2019-06-18 | 哈尔滨工程大学 | A kind of low pressure natural-circulation capacity lifting scheme |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN114023470A (en) * | 2021-09-17 | 2022-02-08 | 中国船舶重工集团公司第七一九研究所 | Passive heat exchange system and reactor system |
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| RU2643785C1 (en) * | 2016-09-29 | 2018-02-06 | Общество с ограниченной ответственностью Научно-производственная фирма "МКТ-АСДМ" | Control unit of passive pipeline protection system |
| CN107403650B (en) * | 2017-08-25 | 2023-11-03 | 中国船舶重工集团公司第七一九研究所 | Secondary side passive waste heat discharging system of offshore floating nuclear power station |
| GB2568692B (en) * | 2017-11-23 | 2020-01-22 | Rolls Royce Plc | Nuclear power plants |
| CN109346196B (en) * | 2018-11-13 | 2022-04-15 | 中国核动力研究设计院 | Active and passive cooling combined molten material in-pile retention system |
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| GB2535848A (en) * | 2014-11-19 | 2016-08-31 | China Nuclear Power Technology Res Inst Co Ltd | Secondary side passive waste heat removal system |
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| CN107727421A (en) * | 2017-09-14 | 2018-02-23 | 中广核研究院有限公司 | The experimental system of model steam generator secondary side operating mode |
| CN107727421B (en) * | 2017-09-14 | 2023-12-01 | 中广核研究院有限公司 | Experimental system for simulating secondary side working condition of steam generator |
| CN108447570A (en) * | 2018-05-15 | 2018-08-24 | 中广核研究院有限公司 | Naval reactor and its Passive residual heat removal system |
| CN108447570B (en) * | 2018-05-15 | 2023-12-26 | 中广核研究院有限公司 | Marine reactor and secondary side passive waste heat discharging system thereof |
| CN108831573A (en) * | 2018-06-28 | 2018-11-16 | 哈尔滨工程大学 | A kind of nuclear power station secondary side passive residual heat removal security system |
| CN109903862A (en) * | 2019-02-20 | 2019-06-18 | 哈尔滨工程大学 | A kind of low pressure natural-circulation capacity lifting scheme |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113035393B (en) * | 2021-03-05 | 2022-11-18 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN114023470A (en) * | 2021-09-17 | 2022-02-08 | 中国船舶重工集团公司第七一九研究所 | Passive heat exchange system and reactor system |
| CN114023470B (en) * | 2021-09-17 | 2024-04-16 | 中国船舶重工集团公司第七一九研究所 | Passive heat exchange system and reactor system |
Also Published As
| Publication number | Publication date |
|---|---|
| GB2535848A (en) | 2016-08-31 |
| WO2016078285A1 (en) | 2016-05-26 |
| GB2535848B (en) | 2020-05-06 |
| GB201600378D0 (en) | 2016-02-24 |
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