CN203572546U - Liquid level measurement device of nuclear power plant spent fuel water pool - Google Patents
Liquid level measurement device of nuclear power plant spent fuel water pool Download PDFInfo
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- CN203572546U CN203572546U CN201320724428.1U CN201320724428U CN203572546U CN 203572546 U CN203572546 U CN 203572546U CN 201320724428 U CN201320724428 U CN 201320724428U CN 203572546 U CN203572546 U CN 203572546U
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- 239000007788 liquid Substances 0.000 title claims abstract description 95
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims abstract description 93
- 238000005259 measurement Methods 0.000 title abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title abstract description 20
- 239000012530 fluid Substances 0.000 claims description 13
- 238000010276 construction Methods 0.000 claims description 12
- 238000009434 installation Methods 0.000 claims description 6
- 238000009530 blood pressure measurement Methods 0.000 claims description 5
- 238000007789 sealing Methods 0.000 claims description 4
- 238000012544 monitoring process Methods 0.000 abstract description 5
- 238000012937 correction Methods 0.000 abstract description 4
- 238000002347 injection Methods 0.000 description 6
- 239000007924 injection Substances 0.000 description 6
- 230000005855 radiation Effects 0.000 description 6
- 238000013461 design Methods 0.000 description 5
- 239000000446 fuel Substances 0.000 description 5
- 238000002955 isolation Methods 0.000 description 5
- 238000012545 processing Methods 0.000 description 5
- 238000009529 body temperature measurement Methods 0.000 description 4
- 238000013459 approach Methods 0.000 description 3
- 230000001066 destructive effect Effects 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 241000196324 Embryophyta Species 0.000 description 1
- 240000007594 Oryza sativa Species 0.000 description 1
- 235000007164 Oryza sativa Nutrition 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 230000003044 adaptive effect Effects 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 230000000977 initiatory effect Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000011900 installation process Methods 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005381 potential energy Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 235000009566 rice Nutrition 0.000 description 1
- -1 two pipes Substances 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a liquid level measurement device of a nuclear power plant spent fuel water pool. According to the liquid level measurement device, under the circumstance that serious accidents of a nuclear power plant occur and the nuclear power plant loses all power supplies or loses most power supplies, continuous monitoring of the liquid level of the nuclear power plant spent fuel water pool is achieved. The liquid level measurement device comprises an n-shaped siphon, one end (A) of the n-shaped siphon stretches into the spent fuel water pool, the other end (C) of the n-shaped siphon is located outside the spent fuel water pool, the liquid level height or pressure of the other end (C) is measured, and temperature correction is utilized when needed. The liquid level measurement device can be used for measuring the liquid level of the spent fuel water pool under the conditions that the nuclear power plant is normal and the serious accidents of the nuclear power plant occur.
Description
Technical field
The utility model relates to a kind of used in nuclear power station measurement mechanism, particularly a kind of nuclear power station spent fuel reservoir liquid level emasuring device.
Background technology
There is serious nuclear accident because the tsunami of earthquake and initiation thereof causes nuclear power station in Fukushima, Japan nuclear power station in March, 2011.There is Hou Ge nuclear power plant and all carried out Safety Inspection Summery-up Conference in accident, and takes a series of innovative approach.After China national nuclear safety office has also issued < < Fukushima nuclear accident, nuclear power plant improves action current techique requirement > > trial version, be called for short < < current techique and require > >, in order to instruct nuclear plant safety rectification.< < current techique requires > > the 4th chapter, and to nuclear power station spent fuel reservoir, monitoring has proposed detailed technical requirement.
According to this requirement, nuclear power station need to be installed liquid level and device for detecting temperature at Spent Fuel Pool, and this device need can normally be worked in nuclear power station design basis earthquake SSE situation.Require measurement point can comprise the exposed front all water levels of nuclear fuel simultaneously.If measuring sensor is arranged on to the position that approaches fuel, the radiation dose rate at this place is about 2.3Gy/h, causes the radiation resistance of measuring sensor to require very high.If same signal processing unit is also arranged in Spent Fuel Pool factory building, also require relevant product to meet the environmental baseline of the Spent Fuel Pool in major accident situation.
Can not meet at present < < current techique requirement > > completely, directly in Spent Fuel Pool, carry out the very ripe product of level gauging.
Utility model content
The technical problems to be solved in the utility model is to provide a kind of liquid level emasuring device, guarantees that nuclear power station, in major accident situation, comprises that nuclear power station loses the continuous monitoring that realizes nuclear power station spent fuel reservoir liquid level in whole or most of electrical source of power situation.
For solving the problems of the technologies described above, the utility model is a kind of nuclear power station spent fuel reservoir liquid level emasuring device, comprise inverted U-shaped U trap and measuring unit of liquid level, inverted U-shaped U trap one end is stretched in Spent Fuel Pool, the other end is positioned at outside Spent Fuel Pool, and measuring unit of liquid level is measured another distolateral liquid level; Wherein, at the other end, form positive U-shaped pipeline structure, in the pipeline away from the described inverted U-shaped U trap other end of positive U-shaped tubular construction, measure liquid level.
Nuclear power station spent fuel reservoir liquid level emasuring device as above, wherein, the described inverted U-shaped U trap other end and described positive U-shaped pipeline structure are positioned at outside the factory building wall of Spent Fuel Pool, in described positive U-shaped tubular construction, away from the pipeline upper end of the described inverted U-shaped U trap other end, connect the pipeline of the factory building wall inside of returning to Spent Fuel Pool.
Nuclear power station spent fuel reservoir liquid level emasuring device as above, wherein, described nuclear power station spent fuel reservoir liquid level emasuring device also comprises: the thermopair of measuring Spent Fuel Pool fluid temperature.
Nuclear power station spent fuel reservoir liquid level emasuring device as above, wherein, described the installation of TC stretches on one end of Spent Fuel Pool in described inverted U-shaped U trap, is positioned at the minimum point that need to carry out level gauging.
The utility model or a kind of nuclear power station spent fuel reservoir liquid level emasuring device, comprise inverted U-shaped U trap, and inverted U-shaped U trap one end is stretched in Spent Fuel Pool, and the other end is positioned at outside Spent Fuel Pool; Wherein, described other end sealing, installs liquid pressure measurement device at the described other end, at the inner air pressure measuring apparatus of installing of factory building wall of Spent Fuel Pool.
Nuclear power station spent fuel reservoir liquid level emasuring device as above, wherein, described nuclear power station spent fuel reservoir liquid level emasuring device also comprises: the thermopair of measuring Spent Fuel Pool fluid temperature.
The utility model can be used in nuclear power station normally and Spent Fuel Pool level gauging in major accident situation.
This liquid level emasuring device adopts indirect measurement method, and measuring sensor and signal processing unit are arranged on outside Spent Fuel Pool factory building, and its radiation dose rate is negligible, therefore the radiation-resistant property of level gauging element is not done to requirement.While having avoided level gauging element directly to install in Spent Fuel Pool, its residing position and fuel distance is only had an appointment 0.5 meter, and the radiation dose rate at this place is the heap type that about 2.3Gy/h(is different, and this value can be different, but its order of magnitude is the same problem).
Meanwhile, antidetonation level level gauging element has ripe product on market, and measuring method is simple, accurate simultaneously; Equipment is installed also simple, feasible, very little on Spent Fuel Pool impact.In major accident situation, measured value is more credible, meets the relevant specification requirement of < < current techique requirement > >.
Accompanying drawing explanation
Fig. 1 is the structural representation of measurement mechanism embodiment one described in the utility model.
Fig. 2 is the structural representation of measurement mechanism embodiment two described in the utility model.
In figure: 1-Spent Fuel Pool liquid level emasuring device, A, B, C, D, E, F-pipeline, 2-isolation valve, 3-water injection valve, 4-liquid level gauge is installed and is used root valve, 5-liquid level gauge signal and thermocouple signal processing element, 6-siphon destructive emits, 7-measurement mechanism installation steel bracket, 8-thermopair, 9-thermopair line, 10-Spent Fuel Pool Brick wall, PT-pressure gauge.
Embodiment
Below in conjunction with drawings and Examples, the utility model is described in further detail.
The related device of the utility model mainly utilizes siphon principle, and siphon is a kind of fluid mechanics phenomenon, can be not by pump and pumping liquid.In the liquid of higher position, be full of an inverted U-shaped tubular structure (being called U trap) afterwards, be opened on lower position.Under this structure, the liquid potential energy difference at pipe two ends can promote liquid and cross peak, to the other end, discharges.Be mainly under Action of Gravity Field, toward low level mouth of pipe place, to be moved by peak liquid in U trap from Action of Gravity Field, form vacuum, under vacuum action, the liquid of the high-order mouth of pipe is sucked into peak, forms siphonage.
Below, for the utility model, enumerate embodiment one and embodiment two describes.
(1) embodiment one
Described in the utility model embodiment one, Spent Fuel Pool liquid level emasuring device 1 is mainly comprised of three parts: double U tube device, measuring unit of liquid level, temperature measurement unit; Described Spent Fuel Pool liquid level emasuring device 1 utilizes siphon principle, indirectly measures Spent Fuel Pool liquid level.
Below, each position is introduced respectively.
1) double U tube device
As shown in Figure 1, double U tube device is comprised of the A pipe being communicated with, B pipe, C pipe, D pipe, E pipe, F pipe.Wherein, A pipe, B pipe, an inverted-loop tube structure of C pipe composition, C pipe, D pipe, another U-shaped tubular construction of E pipe composition.
One end A pipe of an inverted-loop tube structure (A pipe, B pipe, C pipe) extend into the minimum point that needs to carry out level gauging in Spent Fuel Pool.By this U-shaped pipe upper horizontal tubes B pipe, through another positive U-shaped tubular construction of the backward lower formation of Spent Fuel Pool construction wall (C pipe, D pipe, E pipe), this U-shaped pipe top connects a horizontal tube F pipe again and gets back to Spent Fuel Pool top after through Spent Fuel Pool construction wall.
This principle of device is as follows, and first, inverted-loop tube structure (A pipe, B pipe, C pipe) realizes siphon principle.This inverted-loop tube structure (A pipe, B pipe, C pipe) is the syphon structure of standard,, when being full of liquid in this U-shaped tubular construction, and when A pipe, C pipe are dipped in respectively in liquid, due to A pipe side and the atmospheric relation of C pipe side, can make A pipe side liquid surface and C pipe side liquid surface height there is corresponding relation, and in the situation that uniform liquid, both sides air pressure are equal, both sides liquid surface is contour.
Then, for positive U-shaped tubular construction (C pipe, D pipe, E pipe), when only there is positive U-shaped tubular construction, there is corresponding relation in the liquid surface height in the liquid surface in C pipe and E pipe, and the in the situation that in uniform liquid, two pipes, air pressure being equal, the liquid surface in two pipes is contour.
So, according to structure of the present utility model, above-mentioned inverted-loop tube and positive U-shaped pipe are carried out to combination, realized the correspondence of the liquid level in A pipe side liquid level and E pipe, by detecting the liquid level in E pipe, can learn the height of A pipe side liquid level.
So, installing as shown in Figure 1 after this measurement mechanism, double U tube is full of to the liquid identical with Spent Fuel Pool, can be by the effect of siphon principle and U-shaped pipe, vertical tube (E pipe) liquid level in wall outside and the liquid level of Spent Fuel Pool are consistent.Then, by this pipe, liquid level emasuring device being installed, measure E pipe liquid level, can reach the object of monitoring Spent Fuel Pool liquid level.
Also, by the F pipe being connected with E pipe upper end is introduced to A pipe side, make two ends air pressure identical herein.
In addition, homogeneity question for liquid in A pipe side and E pipe describes, owing to being indirect measurement, vertical tube (E pipe) fluid temperature (normal temperature 20-30 ℃) outside wall has difference with the temperature of Spent Fuel Pool, particularly in major accident situation, the temperature of Spent Fuel Pool may approach 133.5 ℃, causes fluid density in measuring section fluid density and Spent Fuel Pool to create a difference.Therefore need to utilize Spent Fuel Pool temperature to revise level gauging value, so, in the present embodiment, inverted-loop tube extend into Spent Fuel Pool on the tube wall of vertical tube (A pipe), at need, carry out level gauging minimum point place core level thermopair is installed, to measure Spent Fuel Pool temperature, for the compensation of liquid surface height, meanwhile, also can be for the monitoring of Spent Fuel Pool temperature.
Correcting mode is as follows:
If to measure pipeline section lowest order as reference point, suppose that fuel pit liquid level is H1, temperature is T1, corresponding water-mass density is ρ 1, Spent Fuel Pool room external pelivimetry section fluid temperature is T2, corresponding water-mass density is ρ 2, and the liquid level of measuring in pipeline section is H2, and H1, H2 relational expression are: ρ 2H2=ρ 1H1.Be H1=ρ 2H2/ ρ 1.Because the relation of ρ and temperature is known, can calculate H1 by temperature T 1, T2, height H 2.
In addition, due to the characteristic of water, temperature raise and ρ diminishes, can draw thus a conclusion, when weary pond temperature is when measuring pipeline section temperature, the actual liquid level in weary pond is higher than the value of measuring, even if therefore measured value is not carried out to water temperature difference correction, measured value is also a too conservative value.And consider from water loading amount angle, not carrying out water temperature difference correction is also acceptable.Because liquid level height diminishes and causes because of density in weary pond, weary pond water loading amount is not because temperature variation changes.The key parameter that guarantees nuclear fuel safety is weary pond water loading amount and fluid temperature.
In addition, for fear of long-play, cause U-shaped pipe top (A, B, C pipeline section) accumulation incondensable gas, and affect the accuracy of level gauging.On the appropriate location of vertical pipeline section (E pipe), isolation valve 2 and water injection valve 3 are installed, during day-to-day operation, are needed regularly U-shaped pipe to be carried out to pressure water injection and catch up with gas, carry out inverted-loop tube leak check simultaneously.
When carrying out this process, first close isolation valve 2, then open water injection valve 3 pressure water injection, make to be full of liquid in U-shaped pipe, in pipe, gas is extruded, and then closes water injection valve 3, opens isolation valve 2, utilizes siphon principle, automatically recovers measuring state.
Because being utilizes siphon principle, so under a standard atmosphere condition, this device level gauging scope is: 0-10 rice.Herein, the implication that the maximal value of measurement range is 10 meters is to be under a standard atmosphere condition at Spent Fuel Pool factory building, below position, the top of inverted-loop tube (B pipe), can measure for 10 meters with interior liquid level.
Should illustrate, this maximal value depends on Spent Fuel Pool factory building atmospheric pressure.It is (20--80Pa) that nuclear power station spent fuel reservoir factory building keeps micro-negative pressure, its peak suction design load when normal operation, negligible on the impact of greatest measurement.In major accident situation, the atmospheric pressure of factory building is atmospheric pressure or malleation, maximum positive voltage power is 0.3MPa, therefore the measurement range of this measurement mechanism in major accident situation is larger, level gauging value confidence level is higher, for the Spent Fuel Pool liquid level in major accident situation, accurately measures new thinking is provided.
In addition, for fear of breaking because of measurement mechanism, cause Spent Fuel Pool to produce and leak through siphon, need determine according to the concrete condition in power station the caliber of inverted-loop tube part (A, B, C pipe), or determine at caliber, in the situation that is difficult to adjust, at the upper restriction orifice of installing of horizontal tube (B pipe) of inverted-loop tube, further to limit maximum siphon leakage flow, make leakage flow within the acceptable range.In addition, can also emit 6 at the upper siphon destructive of installing of the horizontal tube of inverted-loop tube (B pipe), make when needed B pipe become nonocclusive state, open this and emit, make B pipe identical with air, thereby break the siphon state of A pipe, B pipe, C pipe.
Should illustrate, also can, with the good valve of sealing property, as diaphragm valve, replace siphon destructive to emit.
2) measuring unit of liquid level
Measuring unit of liquid level comprises liquid level gauge LT, liquid level gauge Signal Processing Element.Measuring unit of liquid level adopts the product of anti-design basis earthquake SSE level, and as shown in Figure 1, by 2 liquid level gauges installations, with root valve 4, liquid level gauge LT is arranged on the vertical tube (E pipe) outside double U tube device Spent Fuel Pool factory building.Owing to being installed on outside Spent Fuel Pool, reduced the requirement of radiation resistance.
3) temperature measurement unit
Temperature measurement unit comprises thermopair 8 and thermocouple signal processing element, as shown in Figure 1, inverted-loop tube extend into Spent Fuel Pool on the tube wall of vertical tube (A pipe), core level thermopair 8 is installed in the minimum point that need to carry out level gauging, to measure Spent Fuel Pool temperature.When temperature measurement unit (core level thermopair) is arranged on A pipe as shown in Figure 1, A pipe need carry out adaptive design.
Should illustrate, thermopair is not must be installed on A pipe, as long as can accurately obtain the fluid temperature data in Spent Fuel Pool, according to the concrete condition of different power plant, thermopair also can be arranged separately in arbitrary position of Spent Fuel Pool.
In addition,, for the effect of assurance device, preferably there is following constraint condition.
Whole measurement mechanism is installed with steel bracket 7 and is installed and fix by measurement mechanism, and measurement mechanism and installation process are all by anti-SSE level Seismic Design, construction.
The in the situation that of Spent Fuel Pool conditions permit, A pipe extend into Spent Fuel Pool bottom as far as possible, to improve the scope of level gauging in major accident situation.B pipe should be close to the platform on Spent Fuel Pool top as far as possible, to improve the level gauging scope in normal when operation.
D pipe installation site must be lower than the minimum measuring position requiring, and as far as possible identical with A pipe minimum point.
The isolation valve installation site of F pipe and below thereof should be managed higher than B, and on liquid level gauge, root valve should at least maintain an equal level with B pipe simultaneously.
A, B, C pipe adopt overall pipeline section or welding as far as possible, to guarantee its sealing.
Measuring unit of liquid level is arranged on E pipe by two root valves.
(2) embodiment two
Conventionally Spent Fuel Pool room is provided with atmosphere measuring device, therefore, can use the not scheme containing D, E, F pipe, by the C seal of tube, and at C pipe appropriate location setting pressure transmitter.
Although in Fig. 2, represent reserve part D pipe, the scheme of setting pressure meter PT on D pipe,, D manages not necessarily, and whether D pipe retains depending on installing space.
Standard atmospheric pressure, i.e. a 1Kgf/cm
2approximate 10 meter water columns.This point pressure measured value and room, weary pond force value are carried out to subtraction calculations and draw the alternate position spike between weary pond liquid level and this point pressure measurement point, if pressure measurement point position is decided to be to 0 meter, weary pit level=(room, this point pressure measured value-weary pond force value) ÷ fluid density.
When U-shaped pipe two sides temperature is inconsistent, by temperature correction, can accurately obtain Spent Fuel Pool actual liquid level, correcting mode is as follows:
If take pressure measurement point as reference point, suppose that pressure measuring value is P2, Spent Fuel Pool room pressure is P1, fuel pit liquid level is H1, and temperature is T1, and corresponding water-mass density is ρ 1, outside Spent Fuel Pool room, U-shaped pipeline section fluid temperature is T2, corresponding water-mass density is ρ 2, and outside Spent Fuel Pool room, the horizontal pipeline section height of U-shaped pipe is H2, and H1, H2 relational expression are: P2+ ρ 2H2=P1-ρ 1(H2-H1).Be H1=［ P2-P1+H2(ρ 1-ρ 2) ］/ρ 1.Because the relation of ρ and temperature is known, can calculate fuel pit liquid level H1 by pressure P 1, pressure P 2, temperature T 1, T2, height H 2.
Above, by accompanying drawing and two specific embodiments, the utility model is had been described in detail, still, the present embodiment not limits the utility model, not departing from scope of the present utility model, can also carry out all changes and modification.
Claims (6)
1. a nuclear power station spent fuel reservoir liquid level emasuring device, comprise inverted U-shaped U trap and measuring unit of liquid level, inverted U-shaped U trap one end (A) is stretched in Spent Fuel Pool, and the other end (C) is positioned at outside Spent Fuel Pool, and measuring unit of liquid level is measured the liquid level of the other end (C) side; It is characterized in that, at the other end (C), form positive U-shaped pipeline structure (C, D, E), in the pipeline (E) away from the described inverted U-shaped U trap other end (C) of positive U-shaped tubular construction, measure liquid level.
2. nuclear power station spent fuel reservoir liquid level emasuring device as claimed in claim 1, it is characterized in that, the described inverted U-shaped U trap other end (C) and described positive U-shaped pipeline structure are positioned at outside the factory building wall of Spent Fuel Pool, in described positive U-shaped tubular construction, away from pipeline (E) upper end of the described inverted U-shaped U trap other end (C), connect the pipeline (F) of the factory building wall inside of returning to Spent Fuel Pool.
3. nuclear power station spent fuel reservoir liquid level emasuring device as claimed in claim 2, is characterized in that, described nuclear power station spent fuel reservoir liquid level emasuring device also comprises: the thermopair of measuring Spent Fuel Pool fluid temperature.
4. nuclear power station spent fuel reservoir liquid level emasuring device as claimed in claim 3, is characterized in that, one end (A) that described the installation of TC stretches into Spent Fuel Pool in described inverted U-shaped U trap is upper, is positioned at the minimum point that need to carry out level gauging.
5. a nuclear power station spent fuel reservoir liquid level emasuring device, comprises inverted U-shaped U trap, and inverted U-shaped U trap one end (A) is stretched in Spent Fuel Pool, and the other end (C) is positioned at outside Spent Fuel Pool; It is characterized in that, the described other end (C) sealing, installs liquid pressure measurement device at the described other end (C), at the inner air pressure measuring apparatus of installing of factory building wall of Spent Fuel Pool.
6. nuclear power station spent fuel reservoir liquid level emasuring device as claimed in claim 5, is characterized in that, described nuclear power station spent fuel reservoir liquid level emasuring device also comprises: the thermopair of measuring Spent Fuel Pool fluid temperature.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320724428.1U CN203572546U (en) | 2013-11-15 | 2013-11-15 | Liquid level measurement device of nuclear power plant spent fuel water pool |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320724428.1U CN203572546U (en) | 2013-11-15 | 2013-11-15 | Liquid level measurement device of nuclear power plant spent fuel water pool |
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| CN203572546U true CN203572546U (en) | 2014-04-30 |
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| CN201320724428.1U Expired - Lifetime CN203572546U (en) | 2013-11-15 | 2013-11-15 | Liquid level measurement device of nuclear power plant spent fuel water pool |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106768075A (en) * | 2017-02-14 | 2017-05-31 | 中国科学院合肥物质科学研究院 | A kind of thermal measurement system and method for pool device |
| CN108225481A (en) * | 2016-12-09 | 2018-06-29 | 国核华清（北京）核电技术研发中心有限公司 | Spent Fuel Pool level monitoring system and method under a kind of more operating conditions |
| CN110775816A (en) * | 2019-11-18 | 2020-02-11 | 中核核电运行管理有限公司 | Reactor core thermocouple lifting clamp |
-
2013
- 2013-11-15 CN CN201320724428.1U patent/CN203572546U/en not_active Expired - Lifetime
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108225481A (en) * | 2016-12-09 | 2018-06-29 | 国核华清（北京）核电技术研发中心有限公司 | Spent Fuel Pool level monitoring system and method under a kind of more operating conditions |
| CN106768075A (en) * | 2017-02-14 | 2017-05-31 | 中国科学院合肥物质科学研究院 | A kind of thermal measurement system and method for pool device |
| CN106768075B (en) * | 2017-02-14 | 2017-11-21 | 中国科学院合肥物质科学研究院 | A kind of thermal measurement system and method for pool device |
| CN110775816A (en) * | 2019-11-18 | 2020-02-11 | 中核核电运行管理有限公司 | Reactor core thermocouple lifting clamp |
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| GR01 | Patent grant | ||
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Granted publication date: 20140430 |