CN108511094A - It is a kind of to be used to monitor reactor core liquid level and the device and method of vacuole - Google Patents
It is a kind of to be used to monitor reactor core liquid level and the device and method of vacuole Download PDFInfo
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- CN108511094A CN108511094A CN201710111721.3A CN201710111721A CN108511094A CN 108511094 A CN108511094 A CN 108511094A CN 201710111721 A CN201710111721 A CN 201710111721A CN 108511094 A CN108511094 A CN 108511094A
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- guided wave
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- wave radar
- reactor core
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- 239000007788 liquid Substances 0.000 title claims abstract description 68
- 238000000034 method Methods 0.000 title claims abstract description 27
- 210000003934 vacuole Anatomy 0.000 title claims abstract description 21
- 239000000523 sample Substances 0.000 claims abstract description 76
- 239000011800 void material Substances 0.000 claims abstract description 9
- 238000012544 monitoring process Methods 0.000 claims description 33
- 239000002826 coolant Substances 0.000 claims description 11
- 239000007791 liquid phase Substances 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 6
- 238000004891 communication Methods 0.000 claims description 5
- 230000005514 two-phase flow Effects 0.000 claims description 5
- 239000003507 refrigerant Substances 0.000 claims description 4
- 238000013461 design Methods 0.000 claims description 3
- 230000002093 peripheral effect Effects 0.000 claims description 3
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 2
- 229910045601 alloy Inorganic materials 0.000 claims description 2
- 239000000956 alloy Substances 0.000 claims description 2
- 230000007774 longterm Effects 0.000 claims description 2
- 230000005855 radiation Effects 0.000 claims description 2
- 239000012530 fluid Substances 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 4
- 239000012071 phase Substances 0.000 description 4
- 230000005540 biological transmission Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000018044 dehydration Effects 0.000 description 2
- 238000006297 dehydration reaction Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 229910001257 Nb alloy Inorganic materials 0.000 description 1
- 238000009924 canning Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- GFUGMBIZUXZOAF-UHFFFAOYSA-N niobium zirconium Chemical compound [Zr].[Nb] GFUGMBIZUXZOAF-UHFFFAOYSA-N 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/035—Moderator- or coolant-level detecting devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)
Abstract
It is a kind of to be used to monitor reactor core liquid level and the device and method of vacuole, it includes at least：Two coaxial guided wave radar probes of electromagnetic wave signal transceiver are connected in parallel to, the coaxial guided wave radar probe includes guided wave bar and coaxial sleeve；One coaxial guided wave radar pops one's head in only bottom opening to monitor the true liquid level H of reactor core l , and the coaxial sleeve tube wall trepanning of other coaxial guided wave radar probe is to monitor the mixing liquid level H of reactor core m , by the true liquid level H monitored l With mixing liquid level H m Obtain reactor core void fraction.。
Description
Technical field
The present invention relates to a kind of for monitoring liquid level and the technology of vacuole, and relates more specifically to a kind of anti-for monitoring
The device and method for answering heap core level and vacuole.
Background technology
U.S.'s Three Mile Island accident shows that in the case where reactor dehydration causes the operating mode of accident, simple voltage-stablizer water level is difficult
To characterize fluid level condition in Loop Water loading amount and pressure vessel, it is necessary to directly acquire core level information and be judged with auxiliary operator
Reactor core dehydration situation simultaneously accurately selects accident treatment code.
In existing reactor heap-type, it is generally equipped with the instrument system for pressure vessel level monitoring, and propose
The method of level gauging in a variety of pressure vessels, pressure differential method [1] therein and temperature differential method [2] are most commonly seen two methods.
Differential pressure method is to calculate liquid level by measuring the pressure difference of pressure vessel bottom and top.Differential pressure type liquid level measuring system is at least
It needs to configure 3 pressure transmitters and a plurality of impulse pipeline, system structure is considerably complicated.The liquid level of practical application calculates
In, it is necessary to first verification is debugged to obtain calibration parameter repeatedly before system comes into operation, and also needs to accurately obtain other
External parameter information, such as the pressure of reactor building, temperature etc..In short, differential pressure type level is measured by factors
Influence, including environmental condition etc. in coolant temperature and containment in main pump operating condition, heap, and measure inaccuracy compared with
Greatly.In addition, differential pressure method, which measures, needs the presence of the danger for causing Core cooling agent leakage in pressure vessel bottom trepanning pressure, this
Apparent design concept and the requirement for not meeting advanced reactor.Temperature differential method is according to metallic object in vapour（Gas）Mutually and in liquid phase exchange heat
The difference of ability differentiates vapour（Gas）/ liquid phase and then monitoring key point liquid level.Heat in thermal type level measuring method is transmitted（It rises
Temperature）Need the regular hour, i.e., it is longer to the response time of liquid level variation, and also critical component electric heater is irradiated in High Voltage
The shortcomings that there are reduced service life under environment.In addition, thermal type level sensor is just for single level monitoring point, Bu Nengjian
Continuous liquid level is surveyed, and under the emergency conditions that reactor core is in Gas- liquid two-phase flow, detector may be ineffective.
Invention content
In view of the deficiencies of the prior art, the present invention provides a kind of device and sides for monitoring core level and vacuole
Method, the device and method are not necessarily in reactor pressure vessel bottom opening, simple in structure, dependable performance, are not necessarily to field adjustable school
It tests, under reactor start and stop operating mode and accident conditions while the continuous liquid level of reactor core and vacuole information can be obtained, and can also
The variation of quick response core level provides information promptly and accurately for operator.
According to an aspect of the present invention, a kind of device for monitoring reactor core liquid level and vacuole, includes at least：
Electromagnetic wave signal transceiver；The two coaxial guided wave radar probes arranged parallel, top and the electromagnetic wave signal transceiver
Connection, to share the electromagnetic wave signal transceiver, and the coaxial guided wave radar probe includes guided wave bar and coaxial sleeve
Pipe, one of them coaxial guided wave radar probe only bottom opening is to monitor the true liquid level of reactor core, and other same spindle guide
The coaxial sleeve tube wall trepanning of wave radar probe is to monitor the mixing liquid level of reactor core.
According to another aspect of the present invention, a method of for monitoring reactor core liquid level and vacuole, include at least：
Two coaxial guided wave radar probes are made to be connected in parallel to electromagnetic wave signal transceiver, the coaxial guided wave radar probe includes guided wave
Bar and coaxial sleeve；By the true of the first coaxial guided wave radar probe monitors reactor core in described two coaxial guided wave radar probes
Liquid level H l , the first coaxial guided wave radar probe only bottom opening is to make the coolant in coaxial sleeve be liquid phase；By institute
State the mixing liquid level H of the second other coaxial guided wave radar probe monitors reactor core in two coaxial guided wave radar probes m , described
The tube wall trepanning of the coaxial sleeve of second coaxial guided wave radar probe is to make the refrigerant flow communication inside and outside coaxial sleeve；By
The true liquid level H of reactor core l With mixing liquid level H m Obtain reactor core void fraction。
Description of the drawings
Fig. 1 is the structural schematic diagram according to the present invention for monitoring the device of reactor core liquid level and vacuole；Wherein：
1- signal transmitting devices, 2- electromagnetic wave signal transceivers, 3- mounting brackets, 4- fixing brackets, the first coaxial guided wave radars of 5- probe,
The second coaxial guided wave radars of 6- are popped one's head in, 7- coaxial sleeves, 8- guided wave bars, 9- trepannings.
Specific implementation mode
Explain the present invention in detail below in conjunction with the accompanying drawings.It limits as example but not, for monitoring shown in Fig. 1
The device of reactor core liquid level and vacuole includes two coaxial guided wave radar probes 5,6, this two coaxial guided wave radar probes
5,6 are preferably isometric and arrange parallel.The coaxial guided wave radar probe 5,6 is same including guided wave bar 8 and with guided wave bar 8
The coaxial sleeve 7 of axis.The guided wave bar 8 and coaxial sleeve 7 of coaxial guided wave radar probe 5,6 form the electricity similar to coaxial transmission line
Magnetic wave transmission structure.The top connection electromagnetic wave signal transceiver 2 of two coaxial guided wave radars probes 5,6, the electromagnetic wave signal
Transceiver 2 can emit and receive electromagnetic wave signal.The top of electromagnetic wave signal transceiver 2 is connected with signal transmitting device 1, signal
Integrated design can be used in transmitter 1 and electromagnetic wave signal transceiver 2, is arranged on the outside of pressure vessel upper cover.Two coaxial
Guided wave radar probe 5,6 can share electromagnetic wave signal transceiver and signal transmitting device.Core level is monitored according to following principle
Information：When transmission reaches coolant fluid face to the electromagnetic wave that electromagnetic wave signal transceiver 2 emits in coaxial guided wave radar probe 5,6
When, a part for electromagnetic wave can be reflected by coolant liquid level and reverse transfer returns to signal transceiver 2, and by signal transceiver
2 receive, and signal transmitting device 1 emits according to electromagnetic wave signal transceiver 2 and receives the time difference of electromagnetic wave to obtain reactor core liquid
Position information.
Two 5,6 structures of coaxial guided wave radars probe arranged parallel in Fig. 1 are slightly different, wherein the first coaxial guided wave thunder
Tube wall up to the coaxial sleeve 7 of probe 5 does not set recirculation hole, and coolant is only capable of entering from bottom opening, so that cooling in pipe
Agent is pure liquid phase（Liquid level is true liquid level）；And the tube wall of the coaxial sleeve 7 of the second coaxial guided wave radar probe 6 is equipped in an axial direction
Upper continuous trepanning 9, trepanning 9 are used to manage inside and outside fluid communication so that coolant state is identical as reactor core state in pipe.It is described
Trepanning 9 is preferably longitudinal narrow slit, to stablize coaxial sleeve while ensureing the refrigerant flow communication inside and outside coaxial sleeve 7
Flow field in pipe 7 prevents peripheral core level fluctuation from causing the inaccuracy of level monitoring.
As shown in fig. 1, two coaxial guided wave radar probes 5,6 are fixed by logical multiple fixing brackets 4 fixed vertically
Position, probe tip are fixed on by mounting bracket 3 on pressure vessel upper cover, and shockproof requirements are met.Coaxial guided wave radar probe
5,6 bottom ends are located at reactor core bottom hereinafter, meeting the continuous level gauging area in pressure vessel from reactor core bottoms level to full liquid level
Between require.Main material of popping one's head in is ZIRLO alloys（Zirconium-niobium alloy, AP1000 fuel canning materials）, or it is anticorrosive to meet
Radiation resistance and under high temperature and high pressure environment the requirement of long-term work other materials.Alternatively, can realize probe function and
In the case of capable of for a long time working in reactor core environment, other materials also can separately be selected to make probe.Alternatively, can expire
In the case of the continuous level gauging section of foot and required precision, rod-type can be popped one's head in and replace with cable formula probe or by guided wave sensor
It is substituted for thermal resistance liquid level sensor etc..
In accident, the coolant of reactor core and upper area can be in two-phase fluid state（That is vapour（Gas）Liquid mixing shape
State）, it is same that two-phase fluid can enter second by the trepanning 9 on the tube wall of the coaxial sleeve 7 of the second coaxial guided wave radar probe 6
Spindle guide wave radar probe 6 so that coolant state is identical as reactor core state holding in pipe, therefore the second coaxial guided wave radar probe
The liquid level information of the reactor core of 6 monitorings should be the mixing liquid level information of two-phase fluid.However because the first coaxial guided wave radar probe 5
The tube wall of coaxial sleeve 7 does not set recirculation hole, so the liquid level information of the reactor core of monitoring should be the true liquid level letter of pure liquid phase state
Breath.In accident, if assuming, the true liquid level of the reactor core of the first coaxial 5 monitoring of guided wave radar probe is H l , second is coaxial
The mixing liquid level of the reactor core of 6 monitoring of guided wave radar probe is H m , then the size of reactor core void fraction can be calculated。
This void fraction value characterizes the total vacuole information of reactor core, unrelated with partial cavity share, core temperature and velocity flow profile unevenness.When
In the case that two phase flow is not present in reactor core, the level monitoring value of two probes is identical, and void fraction value is 0 at this time.
The specific implementation process of vacuole acquisition of information is：Signal transmitting device 1 emits and connects according to electromagnetic wave signal transceiver 2
The time difference of electromagnetic wave is received to obtain core level information.The data processing module of signal transmitting device 1 is same by comparison first
The core level information of 6 monitoring of spindle guide wave radar probe 5 and the second coaxial guided wave radar probe judges whether reactor core is in two
Phase flow regime simultaneously calculates void fraction value.When the level value of two probe monitors is equal, it is believed that it is in single-phase flow state, it is empty
It is 0 to steep share value；When the level value of the first coaxial 5 monitoring of guided wave radar probe is less than the second coaxial 6 monitoring of guided wave radar probe
Level value（I.e. the true liquid level of reactor core is less than mixing liquid level）When, then judge that reactor core is in two-phase flow state.According to vacuole part
Volume calculating formula simultaneously combines the level value of the first and second coaxial guided wave radar probe monitors to show that void fraction value, processing generate 4-
20mA liquid levels and vacuole analog signal.Meanwhile key liquid level point of the signal transmitting device 1 based on user preset, in conjunction with real-time level
Information generates the alarm signal of crucial measuring point.According to actual demand, multigroup key liquid level measuring point, such as hot pipe section can be freely set
Top, hot pipe section bottom, reactor core top and reactor core bottom etc., to realize the alarm of multiple key liquid level monitoring points.
The device and method of monitoring core level and vacuole proposed in this paper can simply and reliably work so that
Without in reactor pressure vessel bottom opening, being verified without field adjustable, and can be in reactor start and stop operating mode and thing
Therefore the variation of the continuous liquid level of reactor core and vacuole information and quick response core level is obtained under operating mode simultaneously.Signal transmitting device is simultaneously
The alarm signal for providing crucial measuring point further strengthens accident process under emergency conditions and monitors, provided promptly and accurately for operator
Information.
Although some embodiments and general correlating method, the change of these embodiments and methods has been described in the disclosure
Change and replace and will be apparent for a person skilled in the art.Therefore, the above description of exemplary embodiment is simultaneously
The disclosure is not limited or constrained.In the case where not departing from the spirit and scope of the present disclosure as being defined by the following claims,
Other changes, replacement and variation are also possible.
Bibliography
[1] Wang Xin, Kong Fanrun pressurized-water reactor nuclear power plants reactor core level measuring principle [J] science and technology visual fields, 2013 (34):
373-373.
[2] He Zhengxi, Li Fulin, Gou Tuo wait thermal type pressure vessel level detection technical research [C] // China's core dynamic
Power studying and designing institute science and technology annual report 2011.
Claims (17)
1. a kind of device for monitoring reactor core liquid level and vacuole includes at least：
Electromagnetic wave signal transceiver；
The two coaxial guided wave radar probes arranged parallel, top is connect with the electromagnetic wave signal transceiver, to share
The electromagnetic wave signal transceiver, and the coaxial guided wave radar probe includes guided wave bar and coaxial sleeve, it is characterised in that：
One coaxial guided wave radar probe only bottom opening is to monitor the true liquid level of reactor core, and other coaxial guided wave thunder
Up to the coaxial sleeve tube wall trepanning of probe to monitor the mixing liquid level of reactor core.
2. the apparatus according to claim 1, it is characterised in that：It further include the letter being used cooperatively with electromagnetic wave signal transceiver
Number transmitter, to generate liquid level analog signal, and/or vacuole analog signal, and/or the alarm signal of key liquid level monitoring point.
3. the apparatus of claim 2, it is characterised in that：The electromagnetic wave signal transceiver is used with signal transmitting device
Integrated design, and be disposed on the outside of pressure vessel upper cover.
4. the apparatus according to claim 1, it is characterised in that：Described two coaxial guided wave radar probes are equal length
First coaxial guided wave radar probe and the second coaxial guided wave radar probe, wherein the first coaxial guided wave radar probe only bottom
It is open to monitor the true liquid level of reactor core and the tube wall of the coaxial sleeve of the second coaxial guided wave radar probe is equipped with edge
Continuous trepanning is so as to continuously monitoring the mixing liquid level of reactor core in axial direction.
5. device according to claim 4, it is characterised in that：The continuous trepanning is longitudinal narrow slit, to ensure
Stablize pipe flow field inside and outside coaxial sleeve while refrigerant flow communication, prevents the influence of peripheral core level fluctuation.
6. the apparatus according to claim 1, it is characterised in that：Described two coaxial guided wave radar probes pass through vertically
Multiple fixing bracket stationary positioneds, probe tip are fixed on by mounting bracket on pressure vessel upper cover, and shockproof requirements are met.
7. the apparatus according to claim 1, it is characterised in that：The coaxial guided wave radar probe bottom reactor core bottom with
Under, to meet in pressure vessel from reactor core bottoms level to the continuous level monitoring of full liquid level.
8. the apparatus of claim 2, it is characterised in that：Multigroup key liquid level monitoring point is set to realize multiple passes
The alarm of key level monitoring point.
9. the apparatus according to claim 1, it is characterised in that：The main material of the coaxial guided wave radar probe is
ZIRLO alloys, or for can anticorrosive, radiation resistance and can be in the other materials of long-term work under high temperature and high pressure environment.
10. the apparatus according to claim 1, it is characterised in that：In reactor core there are in the case of two phase flow, if described first
The true liquid level of the reactor core of coaxial guided wave radar probe monitors is H l , and the heap of the second coaxial guided wave radar probe monitors
The mixing liquid level of core is H m , then the void fraction of reactor core。
11. it is a kind of for monitoring reactor core liquid level and the method for vacuole, it includes at least：
Two coaxial guided wave radar probes are made to be connected in parallel to electromagnetic wave signal transceiver, the coaxial guided wave radar probe includes
Guided wave bar and coaxial sleeve；
By the true liquid level H of the first coaxial guided wave radar probe monitors reactor core in described two coaxial guided wave radar probes l , institute
The first coaxial guided wave radar probe only bottom opening is stated to make the coolant in coaxial sleeve be liquid phase；
By the mixed liquor of the second other coaxial guided wave radar probe monitors reactor core in described two coaxial guided wave radar probes
Position H m , the tube wall trepanning of the coaxial sleeve of the second coaxial guided wave radar probe is to make the coolant flow inside and outside coaxial sleeve
Body is connected to；
By the true liquid level H of reactor core l With mixing liquid level H m Obtain the void fraction of reactor core。
12. according to the method for claim 11, it is characterised in that：Further include being used cooperatively with electromagnetic wave signal transceiver
Signal transmitting device generates liquid level analog signal, and/or vacuole analog signal, and/or the alarm signal of key liquid level monitoring point.
13. according to the method for claim 11, it is characterised in that：Described two coaxial guided wave radar probes are equal length
The first coaxial guided wave radar probe and the second coaxial guided wave radar probe, wherein the first coaxial guided wave radar probe only bottom
Portion's opening is equipped with to monitor the tube wall of the true liquid level of reactor core and the coaxial sleeve of the second coaxial guided wave radar probe
Continuous trepanning vertically is so as to continuously monitoring the mixing liquid level of reactor core.
14. according to the method for claim 13, it is characterised in that：The continuous trepanning is longitudinal narrow slit, to protect
Stablize pipe flow field while demonstrate,proving refrigerant flow communication inside and outside coaxial sleeve, prevents the influence of peripheral core level fluctuation.
15. according to the method for claim 11, it is characterised in that：Described two coaxial guided wave radar probes lead to vertically
It crosses and leads to multiple fixing bracket stationary positioneds, probe tip is fixed on by mounting bracket on pressure vessel upper cover, and antidetonation is met
It is required that.
16. according to the method for claim 11, it is characterised in that：The bottom of the coaxial guided wave radar probe is at reactor core bottom
Portion is hereinafter, to meet in pressure vessel from reactor core bottoms level to the continuous level monitoring of full liquid level.
17. according to the method for claim 12, it is characterised in that：It is multiple to realize to set multigroup key liquid level monitoring point
The alarm of key liquid level monitoring point.
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| CN201710111721.3A CN108511094A (en) | 2017-02-28 | 2017-02-28 | It is a kind of to be used to monitor reactor core liquid level and the device and method of vacuole |
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| CN201710111721.3A CN108511094A (en) | 2017-02-28 | 2017-02-28 | It is a kind of to be used to monitor reactor core liquid level and the device and method of vacuole |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109243641A (en) * | 2018-10-18 | 2019-01-18 | 中国核动力研究设计院 | Reactor pressure vessel for presurized water reactor loss of-coolant accident (LOCA) tests analogue body |
| CN113533420A (en) * | 2021-07-15 | 2021-10-22 | 中国核动力研究设计院 | Cavitation share measuring method and device for lead-bismuth reactor bubble reactor core distribution experiment |
| CN114137006A (en) * | 2021-11-04 | 2022-03-04 | 散裂中子源科学中心 | High-temperature furnace for small-angle scattering experiment |
Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4406011A (en) * | 1981-06-16 | 1983-09-20 | Burns Thomas J | Gamma thermometer based reactor core liquid level detector |
| US4639349A (en) * | 1982-03-22 | 1987-01-27 | Research Corporation | Non-invasive liquid level and density gauge for nuclear power reactor pressure vessels |
| CN1477648A (en) * | 2002-08-21 | 2004-02-25 | 中国核动力研究设计院 | Core level monitoring device for reactor |
| US20080310576A1 (en) * | 2007-06-14 | 2008-12-18 | General Electric Company | System and method for determining coolant level and flow velocity in a nuclear reactor |
| KR20120086826A (en) * | 2011-01-27 | 2012-08-06 | 한국수력원자력 주식회사 | Liquid zone control level assessment method using response of neutron overpower protection detector |
| CN102737740A (en) * | 2012-06-13 | 2012-10-17 | 中国核动力研究设计院 | Guiding device of pressurized water reactor in-core instrumentation system |
| CN102982853A (en) * | 2012-12-03 | 2013-03-20 | 中国核动力研究设计院 | Water level detector for reactor core and water level measuring method of detector |
| CN103390437A (en) * | 2013-07-22 | 2013-11-13 | 中国核动力研究设计院 | Liquid-gas separation structure and water level detector guiding structure comprising the liquid-gas separation structure |
| US20140159944A1 (en) * | 2012-12-06 | 2014-06-12 | Rosemount Tank Radar Ab | Probe spacing element |
| US20140191898A1 (en) * | 2011-09-06 | 2014-07-10 | Stamicarbon B.V. | Radar level measurement |
| US20150276461A1 (en) * | 2014-03-31 | 2015-10-01 | Rosemount Tank Radar Ab | Level gauging system for long narrow nozzles |
| CN207068485U (en) * | 2017-02-28 | 2018-03-02 | 国核华清（北京）核电技术研发中心有限公司 | A kind of device for being used to monitor reactor core liquid level and vacuole |
-
2017
- 2017-02-28 CN CN201710111721.3A patent/CN108511094A/en active Pending
Patent Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4406011A (en) * | 1981-06-16 | 1983-09-20 | Burns Thomas J | Gamma thermometer based reactor core liquid level detector |
| US4639349A (en) * | 1982-03-22 | 1987-01-27 | Research Corporation | Non-invasive liquid level and density gauge for nuclear power reactor pressure vessels |
| CN1477648A (en) * | 2002-08-21 | 2004-02-25 | 中国核动力研究设计院 | Core level monitoring device for reactor |
| US20080310576A1 (en) * | 2007-06-14 | 2008-12-18 | General Electric Company | System and method for determining coolant level and flow velocity in a nuclear reactor |
| KR20120086826A (en) * | 2011-01-27 | 2012-08-06 | 한국수력원자력 주식회사 | Liquid zone control level assessment method using response of neutron overpower protection detector |
| US20140191898A1 (en) * | 2011-09-06 | 2014-07-10 | Stamicarbon B.V. | Radar level measurement |
| CN102737740A (en) * | 2012-06-13 | 2012-10-17 | 中国核动力研究设计院 | Guiding device of pressurized water reactor in-core instrumentation system |
| CN102982853A (en) * | 2012-12-03 | 2013-03-20 | 中国核动力研究设计院 | Water level detector for reactor core and water level measuring method of detector |
| US20140159944A1 (en) * | 2012-12-06 | 2014-06-12 | Rosemount Tank Radar Ab | Probe spacing element |
| CN103390437A (en) * | 2013-07-22 | 2013-11-13 | 中国核动力研究设计院 | Liquid-gas separation structure and water level detector guiding structure comprising the liquid-gas separation structure |
| US20150276461A1 (en) * | 2014-03-31 | 2015-10-01 | Rosemount Tank Radar Ab | Level gauging system for long narrow nozzles |
| CN207068485U (en) * | 2017-02-28 | 2018-03-02 | 国核华清（北京）核电技术研发中心有限公司 | A kind of device for being used to monitor reactor core liquid level and vacuole |
Non-Patent Citations (5)
| Title |
|---|
| 何正熙 等: "温差式压力容器液位探测技术研究", 《中国核动力研究设计院科学技术年报（2009）》, 1 January 2011 (2011-01-01) * |
| 幸奠川;孙立成;阎昌琪;田道贵;: "竖直圆管内泡状流空泡份额径向分布实验研究", 原子能科学技术, no. 02, 20 February 2013 (2013-02-20) * |
| 张鹏;李纬;邸智;胡啸;张蕾;邹亚亨;陈炼;常华健;陈培培;: "池式夹带高速区试验研究", 原子能科学技术, no. 12, 20 December 2016 (2016-12-20) * |
| 李沛颖;向延;孙都成;张大林;张鹏;秋穗正;苏光辉;: "AP1000 ADS-4夹带卸压试验模拟分析", 原子能科学技术, no. 01, 20 January 2016 (2016-01-20) * |
| 邸智 等: "使用导波雷达液位计测量两相混合液位的研究", 《第十四届全国反应堆热工流体学术会议暨 中核核反应堆热工水力技术重点实验室2015 年度学术年会》, 23 September 2015 (2015-09-23) * |
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