CN108511091A - A kind of pipe tube type pressurized water reactor system - Google Patents
A kind of pipe tube type pressurized water reactor system Download PDFInfo
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- CN108511091A CN108511091A CN201810444275.2A CN201810444275A CN108511091A CN 108511091 A CN108511091 A CN 108511091A CN 201810444275 A CN201810444275 A CN 201810444275A CN 108511091 A CN108511091 A CN 108511091A
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- reactor
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- pressurized water
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- tube type
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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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- 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
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of pipe tube type pressurized water reactor system, security system is equipped in the pipe tube type pressurized water reactor system, the security system includes：Lead-containing alloy pond, passive air cooling system, wherein, pressure-tube reactor is immersed in lead-containing alloy pond, heat exchanger in passive air cooling system is immersed in lead-containing alloy pond, realize pipe tube type pressurized water reactor system reasonable design, and the higher technique effect of pipe tube type pressurized water reactor security feature and economy.
Description
Technical field
The present invention relates to reactor safety design fields, and in particular, to a kind of pipe tube type pressurized water reactor system.
Background technology
Nuclear energy ensures energy peace as a kind of efficient, economic, reliable clean energy resource for China's Optimization of Energy Structure
Entirely, it reduces environmental pollution, pushes nuclear power go-global strategy, and safe and clean, efficient, the sustainable modern energy of structure
System has important strategic importance.
After Fukushima accident, though nuclear power developing by certain impact, in recent years, in General Promotion safety standard and safe skill
While art, domestic and international nuclear power is restarted paces and is just gradually accelerated.A nearest studies have shown that of International Atomic Energy Agency (IAEA)
Expect the year two thousand thirty, the growth rate conservative estimation of global nuclear power total amount is 17%, and optimistic estimate will be up to 94%, almost mesh
Twice of preceding whole world nuclear power generating capacity.In terms of global range, the 13%-15% of world power supply at present comes from nuclear power, generation
Main energy sources consumption big country of boundary is very high to the dependence of nuclear energy, and nuclear energy is still the important of many countries, especially developing country
Selection, nuclear power will play a significant role in long-range energy resource structure.
The current nuclear power installed capacity in China only accounts for the 2% of total electricity, well below developed countries such as American-European Japan and Korea S.With energy
The increase of source demand and the increasing of environmental pressure, demand of China's development to nuclear power will highlight.And so far, the country has runed
Nuclear power generating sets 26, total installed capacity scale are 24,420,000 kilowatts, are building unit 25, installation scale is 27,440,000 kilowatts.From above-mentioned
National planning and actual conditions are seen, to before the year two thousand twenty, the country is estimated also by newly-increased about 40,000,000 kilowatts of nuclear power projects.
To sum up, the continuous drive of the energy, especially developing country's future need the energy with human social development
The growth asked, along with the increasingly exhausted of traditional energy, nuclear power will be the reliable clean energy resource of most possible Large scale construction.
Currently, the nuclear power technology run in the world is mainly presurized water reactor and boiling-water reactor, the nuclear power generating sets of China's operation are main
Using two generation pressure (hydraulic) water heap nuclear power technologies, three generations's compacted clay liners and high temperature gas cooled reactor, sodium-cooled fast reactor are being built.When
Preceding presurized water reactor there are the problem of be：In the case where the extreme cases such as dehydration, power-off occur, reactor waste can not export, and then occur
Major accident, Fukushima nuclear power plant accident are exactly painful case.Thus, the safety for further increasing nuclear power technology is ground as the world
Study carefully direction, mainly further increase the safety of nuclear power technology using three kinds of modes at present, the first is by redundancy original
Then, increase active safety equipment, to reduce the probability that major accident occurs；Second is using the special passive peace configured
Residual heat of nuclear core is discharged by modes such as the gravity of the Nature, heat convections in full facility；The third is intrinsic by reactor
Reactor core heat is transferred to ultimate heat sink by security feature to ensure the safety of reactor, such as by the heat transfer of itself, radiation.
Current compressed water reactor nuclear power technology is unsatisfactory for inherent safety features, although and high temperature gas cooled reactor have it is inherently safe
Characteristic, but its reactor capability density is very low, compared with conventional pressurized water heap, economy is relatively poor.
In conclusion present inventor has found above-mentioned technology extremely during realizing the present application technical solution
It has the following technical problems less：
In the prior art, existing pressurized water reactor can not meet simultaneously there are inherent safety features and economy
Technical problem.
Invention content
The present invention provides a kind of pipe tube type pressurized water reactor systems, solve existing pressurized water reactor and exist inherently
The technical issues of security feature and economy can not meet simultaneously, realizes the design of pipe tube type pressurized water reactor system and closes
Reason, and the higher technique effect of pipe tube type pressurized water reactor security feature and economy.
In order to solve the above technical problems, this application provides a kind of pipe tube type pressurized water reactor system, the pressure pipe
Passive safety system is equipped in formula pressurized water reactor system, the passive safety system includes：It is lead-containing alloy pond, passive
Air cooling system, wherein pressure-tube reactor is immersed in lead-containing alloy pond, the heat exchange in passive air cooling system
Device is immersed in lead-containing alloy pond.
A kind of presurized water reactor of inherent safety features using lead-containing alloy as passive residual heat removal working medium in the application
On the one hand system can inherit the technology of current presurized water reactor maturation, presurized water reactor on the other hand can be made to have inherent safety, carried
The safety of high pressure water-water reactor；Third keeps the core power density of presurized water reactor and the power of reactor, higher to ensure to have
Economy.
Wherein, the pipe tube type pressurized water reactor system specifically includes：Pressure-tube reactor, pressure-tube reactor
Primary Ioops system, pressure-tube reactor secondary coolant circuit system, cooling system, passive safety system, pressure-tube reactor with
Pressure-tube reactor primary Ioops system, pressure-tube reactor secondary coolant circuit system, cooling system form circulating cooling system.
Wherein, a kind of inherently safe pipe tube type pressurized water reactor using lead-containing alloy as passive residual heat removal working medium
System is connected in sequence by pressure-tube reactor, main pump, voltage-stablizer, steam generator etc. by pipeline.Its security system
It is made of lead-containing alloy pond, passive air cooling system and corresponding pipeline on the outside of pressure pipe.Pressure-tube reactor impregnates
In lead-containing alloy pond, a heat exchanger section of passive air cooling system is immersed in lead-containing alloy pond, another is changed
Hot device is placed in air cooling tower.
Wherein, pressure-tube reactor, voltage-stablizer, steam generator, main coolant pump are sequentially connected composition by pipeline
The pressure-tube reactor primary Ioops system.
Wherein, steam generator, condenser are sequentially connected by pipeline forms pressure-tube reactor secondary circuit system
System.
Wherein, cooling system includes：Cooling water source, water circulating pump, circulating water pipeline.
Wherein, the passive air cooling system specifically includes：Heat exchanger in lead-containing alloy pond passive cools back
Road, aerial cooler and air cooling compressor composition.
Wherein, pressure pipe is internally provided with ball fuel or cylindrical fuel stick, ball fuel in pressure-tube reactor
Or cylindrical fuel stick involucrum uses heat safe crash-proof material.
The passive air cooling system specifically includes：Heat exchanger, passive cooling circuit, air in lead-containing alloy pond
Cooler and air cooling compressor form, and heat exchanger is connect with aerial cooler by passive cooling circuit in lead-containing alloy pond,
Aerial cooler is placed in air cooling compressor.It, will be in cooling pond using aerial cooler in air cooling tower under accident conditions
In heat derives to air.It will by the circuit that heat exchanger, passive cooling circuit and aerial cooler form in lead-containing alloy pond
In lead base pond in heat derives to aerial cooler.Aerial cooler is placed in air cooling tower, and the air in air cooling tower is natural
Cycle takes heat to air out of.
Wherein, pressure pipe is internally provided with ball fuel or cylindrical fuel stick in pressure-tube reactor, on the one hand profit
It is reacted with neutron fission and generates heat, on the other hand leave coolant flow channel, ball fuel or cylindrical fuel stick for coolant
Involucrum uses heat safe crash-proof material, such as carbofrax material.
Wherein, pressure-tube reactor is made of dozens or even hundreds of pressure pipe, arranged in parallel between each pressure pipe.
The ball fuel or cylindrical fuel stick of arrangement crash-proof, fuel can bear higher temperature (fuel quantity ga(u)ge inside pressure pipe
Face temperature can reach 1000 DEG C or more) and vigorous reaction, under the action of main pump, pressure does not occur with coolant at high temperature
Water is quickly flowed in pipe, and on the one hand water serves as coolant, on the other hand serve as moderator function.It is special that pressure inside pipe wall applies
The heat-barrier material with high light blackness, on the one hand this material has lower thermal conductivity (being less than 10W/m DEG C), another
Aspect has higher optics blackness (such as larger than 0.7).
Wherein, pressure inside pipe wall is coated with heat-barrier material in pressure-tube reactor, and the thermal conductivity of the heat-barrier material is less than
10W/m DEG C, the blackness of the heat-barrier material is more than 0.7, and receiving fuel radiation in accident transmits the heat of coming, and by heat
It exports into lead-containing alloy pond.
Wherein, lead or lead bismuth alloy are used in lead-containing alloy pond, by the decay of pressure pipe reactor under accident conditions
Waste heat is transmitted in passive air cooling system.
Wherein, under accidental conditions, the coolant temperature in reactor pressure tube is 300 DEG C or so and (is pressed with tradition
Water reactor parameter is suitable), lead-containing alloy temperature (300 DEG C of left sides consistent with Core cooling agent mean temperature on the outside of pressure pipe
It is right), the interior outside of pressure pipe reaches thermal balance, substantially without heat exchange.
Under ordinary accident operating mode (non-cooled dose of forfeiture accident), reactor is used active using traditional reactor at present
Device exports residual heat of nuclear core, while can also export heat by lead-containing alloy pond on the outside of pressure pipe and passive air cooling system
Amount.Due to the input of passive air cooling system, the temperature in lead-containing alloy pond will be less than nominal situation on the outside of pressure pipe, and heat will be from
Reactor exports on the outside of pressure pipe, alleviates accident progress.
Under the accident conditions that reactor is in Core cooling agent forfeiture and Core uncovering, fuel element temperature in reactor
Rise, fuel surface temperature reaches 1000 DEG C or so, and heat is transmitted to pressure inside pipe wall by radiation heat transfer, and inner wall temperature increases
Afterwards (higher than the temperature of pressure pipe under accidental conditions), the lead-containing alloy on the outside of pressure pipe is transferred heat to by heat transfer
Chi Zhong is calculated by inventor, and this device can export whole waste heats (being about the 2% of rated power), ensure reactor
It is inherently safe.
One or more technical solution provided by the present application, has at least the following technical effects or advantages：
Inherently safe water-cooled reactor of the present invention using lead-containing alloy as passive residual heat removal working medium has
Inherent safety features, occurring to lose coolant and in the case of station blackout, reactor can will be anti-by radiation heat transfer
It answers the waste heat (the 2% of rated power) of heap to be transferred in air, ensures the safety of reactor；
Inherently safe water-cooled reactor of the present invention using lead-containing alloy as passive residual heat removal working medium, with
Under the premise of inherent safety features, have and the comparable economy of traditional reactor.
Description of the drawings
Attached drawing described herein is used for providing further understanding the embodiment of the present invention, constitutes one of the application
Point, do not constitute the restriction to the embodiment of the present invention；
Fig. 1 is the structural schematic diagram of pipe tube type pressurized water reactor system in the application；
Fig. 2 is the structural schematic diagram of pressure-tube reactor in the application；
Wherein, 1-primary Ioops system, 2-reactors, 3-main coolant pumps, 4-control rods and driving mechanism, 5-is steady
Depressor, 6-steam generators, 7-secondary coolant circuit systems, 8-steam turbine generators, 9-condensers, 10-feed pumps, 11-pressure
Pipe, 12-lead-containing alloy ponds, 13-fuel, 14-main pipeline cold tube sections, 15-main pipeline hot pipe sections, 16-control rods, 17-
Heat exchanger, 18-passive air cooling systems.
Specific implementation mode
The present invention provides a kind of pipe tube type pressurized water reactor systems, solve existing pressurized water reactor and exist inherently
The technical issues of security feature and economy can not meet simultaneously, realizes the design of pipe tube type pressurized water reactor system and closes
Reason, and the higher technique effect of pipe tube type pressurized water reactor security feature and economy.
To better understand the objects, features and advantages of the present invention, below in conjunction with the accompanying drawings and specific real
Mode is applied the present invention is further described in detail.It should be noted that in the case where not conflicting mutually, the application's
Feature in embodiment and embodiment can be combined with each other.
Many details are elaborated in the following description to facilitate a thorough understanding of the present invention, still, the present invention may be used also
Implemented with being different from the other modes being described herein in range using other, therefore, protection scope of the present invention is not by under
The limitation of specific embodiment disclosed in face.
As shown in Figure 1 and Figure 2, in normal conditions, the operational process of reactor is：It is cold in reactor-loop system
But agent water is under the promotion of coolant pump 3, into pressure pipe 11 in reactor 2, after coolant absorbs the heat of reactor fuel 13
It by steam generator 6, transfers heat in secondary coolant circuit system, wherein voltage-stablizer 5 is used to stablize the pressure of primary Ioops.Two times
Road heat-transfer working medium into 6 secondary side of steam generator, and generates steam, steam is to turbine generator under the action of feed pump 10
Machine 8 becomes exhaust gas after doing work, and by condenser 9 by waste gas condensation, continues cycling through use.Under normal reactor operation, one
Divide Core cooling agent mean temperature equal with 12 temperature of lead-containing alloy pond on the outside of pressure pipe, without thermal loss, lead-containing alloy
Pond temperature remains unchanged.
Under accident conditions, if it is Non-LOCA accident, reactor is still mainly led heat by the fluid of main pipeline
Go out, while also passive air cooling system 18 ensures the safety of reactor fuel 13 together by heat derives.If it is loss of-coolant accident (LOCA)
And reactor fuel 13 is exposed, fuel transfers heat to the inner wall of pressure pipe 11 by surface high-temp radiation, and is transferred to lead base
In alloy pond 12, reactor core heat is exported eventually by heat transmitter 17 and passive air cooling system, ensures the safety of reactor.
Wherein, the inherently safe pipe tube type pressure using lead-containing alloy as passive residual heat removal working medium in the application
Water reactor system, reactor are made of dozens or even hundreds of pressure pipe, the fuel element of arrangement crash-proof inside pressure pipe,
Fuel can bear high temperature and vigorous reaction does not occur with coolant at high temperature, pressure inside pipe wall apply it is special have it is lower
The material of thermal conductivity and higher optics blackness.Pressure pipe is immersed in a lead-containing alloy pond, and passive residual heat is arranged in pond
Discharge system, in the case where reactor core is in coolant loss and exposed accident conditions, fuel element temperature rises, and heat is logical
Overshoot mode is transmitted to pressure inside pipe wall, and then is transmitted in the lead-containing alloy on the outside of pressure pipe, eventually by passive remaining
Waste heat is transmitted to air by hot discharge system, ensures the safety of reactor.Compared with existing presurized water reactor system, the present invention can protect
The inherent safety of pressurized water reactor is demonstrate,proved, meanwhile, the power density of reactor is suitable with existing presurized water reactor in this scheme, has good
Good economy.
Technical solution in above-mentioned the embodiment of the present application, at least has the following technical effect that or advantage：
Inherently safe water-cooled reactor of the present invention using lead-containing alloy as passive residual heat removal working medium has
Inherent safety features, occurring to lose coolant and in the case of station blackout, reactor can will be anti-by radiation heat transfer
It answers the waste heat (the 2% of rated power) of heap to be transferred in air, ensures the safety of reactor；
Inherently safe water-cooled reactor of the present invention using lead-containing alloy as passive residual heat removal working medium, with
Under the premise of inherent safety features, have and the comparable economy of traditional reactor.
Although preferred embodiments of the present invention have been described, it is created once a person skilled in the art knows basic
Property concept, then additional changes and modifications may be made to these embodiments.So it includes excellent that the following claims are intended to be interpreted as
It selects embodiment and falls into all change and modification of the scope of the invention.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and range.In this way, if these modifications and changes of the present invention belongs to the range of the claims in the present invention and its equivalent technologies
Within, then the present invention is also intended to include these modifications and variations.
Claims (9)
1. a kind of pipe tube type pressurized water reactor system, which is characterized in that be equipped in the pipe tube type pressurized water reactor system
Passive safety system, the passive safety system include：Lead-containing alloy pond, passive air cooling system, wherein pressure
Pipe reaction heap is immersed in lead-containing alloy pond, and the heat exchanger in passive air cooling system is immersed in lead-containing alloy pond.
2. pipe tube type pressurized water reactor system according to claim 1, which is characterized in that the pipe tube type pressure water is anti-
Shut-down system is answered to specifically include：Pressure-tube reactor, pressure-tube reactor primary Ioops system, pressure-tube reactor secondary circuit
System, cooling system, passive safety system, pressure-tube reactor and pressure-tube reactor primary Ioops system, pressure pipe
Formula reactor secondary circuit system, cooling system form circulating cooling system.
3. pipe tube type pressurized water reactor system according to claim 2, which is characterized in that pressure-tube reactor, steady
Depressor, steam generator, main coolant pump are sequentially connected the composition pressure-tube reactor primary Ioops system by pipeline.
4. pipe tube type pressurized water reactor system according to claim 2, which is characterized in that steam generator, condenser
It is sequentially connected the composition pressure-tube reactor secondary coolant circuit system by pipeline.
5. pipe tube type pressurized water reactor system according to claim 2, which is characterized in that cooling system includes：It is cooling
Water source, water circulating pump, circulating water pipeline.
6. pipe tube type pressurized water reactor system according to claim 1, which is characterized in that the passive air cooling
System specifically includes：Heat exchanger, passive cooling circuit, aerial cooler, air cooling compressor, lead-containing alloy in lead-containing alloy pond
Heat exchanger is connect with aerial cooler by passive cooling circuit in pond, and aerial cooler is placed in air cooling compressor；
It, will be in heat derives to air in cooling pond using aerial cooler in air cooling tower under accident conditions.
7. pipe tube type pressurized water reactor system according to claim 1, which is characterized in that pressed in pressure-tube reactor
Solenoid is internally provided with ball fuel or cylindrical fuel stick, on the one hand utilizes neutron fission reaction to generate heat, on the other hand
Coolant flow channel is left for coolant, ball fuel or cylindrical fuel stick involucrum use heat safe crash-proof material.
8. pipe tube type pressurized water reactor system according to claim 1, which is characterized in that pressed in pressure-tube reactor
Solenoid inner wall is coated with heat-barrier material, and the thermal conductivity of the heat-barrier material is less than 10W/m DEG C, and the blackness of the heat-barrier material is more than 0.7.
9. pipe tube type pressurized water reactor system according to claim 1, which is characterized in that use lead in lead-containing alloy pond
Or lead bismuth alloy, the Decay afterheat of pressure pipe reactor is transmitted in passive air cooling system under accident conditions.
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| CN201810444275.2A CN108511091A (en) | 2018-05-10 | 2018-05-10 | A kind of pipe tube type pressurized water reactor system |
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| CN201810444275.2A CN108511091A (en) | 2018-05-10 | 2018-05-10 | A kind of pipe tube type pressurized water reactor system |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109404071A (en) * | 2018-12-17 | 2019-03-01 | 广西电网有限责任公司电力科学研究院 | A kind of discrimination method of PWR steam generator model time constant |
| CN109613429A (en) * | 2018-12-17 | 2019-04-12 | 广西电网有限责任公司电力科学研究院 | A kind of PWR steam generator model time constant test macro and method |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH07159565A (en) * | 1993-12-13 | 1995-06-23 | Hitachi Ltd | Pressure tube type atomic reactor |
| CN1263978C (en) * | 2001-08-28 | 2006-07-12 | 法玛通Anp有限公司 | Method for reducing corrosion of connecting pipeline in primary return for CANDU nuclear power plant |
| CN103329207A (en) * | 2010-11-15 | 2013-09-25 | 加拿大原子能有限公司 | Nuclear fuel containing a neutron absorber |
| CN106229015A (en) * | 2016-08-24 | 2016-12-14 | 中国核动力研究设计院 | A kind of high-temperature molten salt manometer tube and pipe tube type graphite high-temperature molten salt reactor |
| CN106683720A (en) * | 2017-01-13 | 2017-05-17 | 中国核动力研究设计院 | Shell-and-tube lead base alloy cooling reactor |
-
2018
- 2018-05-10 CN CN201810444275.2A patent/CN108511091A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH07159565A (en) * | 1993-12-13 | 1995-06-23 | Hitachi Ltd | Pressure tube type atomic reactor |
| CN1263978C (en) * | 2001-08-28 | 2006-07-12 | 法玛通Anp有限公司 | Method for reducing corrosion of connecting pipeline in primary return for CANDU nuclear power plant |
| CN103329207A (en) * | 2010-11-15 | 2013-09-25 | 加拿大原子能有限公司 | Nuclear fuel containing a neutron absorber |
| CN106229015A (en) * | 2016-08-24 | 2016-12-14 | 中国核动力研究设计院 | A kind of high-temperature molten salt manometer tube and pipe tube type graphite high-temperature molten salt reactor |
| CN106683720A (en) * | 2017-01-13 | 2017-05-17 | 中国核动力研究设计院 | Shell-and-tube lead base alloy cooling reactor |
Non-Patent Citations (2)
| Title |
|---|
| 俞冀阳等: "《核电厂系统与运行》", 31 October 2016 * |
| 周涛等: "《非能动概念与技术》", 30 June 2016 * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109404071A (en) * | 2018-12-17 | 2019-03-01 | 广西电网有限责任公司电力科学研究院 | A kind of discrimination method of PWR steam generator model time constant |
| CN109613429A (en) * | 2018-12-17 | 2019-04-12 | 广西电网有限责任公司电力科学研究院 | A kind of PWR steam generator model time constant test macro and method |
| CN109613429B (en) * | 2018-12-17 | 2021-01-05 | 广西电网有限责任公司电力科学研究院 | Pressurized water reactor steam generator model time constant testing system and method |
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Application publication date: 20180907 |