CN102063947A - Liquid level measuring device for nuclear reactor pool - Google Patents
Liquid level measuring device for nuclear reactor pool Download PDFInfo
- Publication number
- CN102063947A CN102063947A CN2010105310650A CN201010531065A CN102063947A CN 102063947 A CN102063947 A CN 102063947A CN 2010105310650 A CN2010105310650 A CN 2010105310650A CN 201010531065 A CN201010531065 A CN 201010531065A CN 102063947 A CN102063947 A CN 102063947A
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- liquid level
- guiding pipe
- pressure guiding
- pile
- differential pressure
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- 239000007788 liquid Substances 0.000 title claims abstract description 25
- 238000005259 measurement Methods 0.000 claims abstract description 16
- 230000007246 mechanism Effects 0.000 claims description 12
- 230000035515 penetration Effects 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 7
- 238000009434 installation Methods 0.000 abstract description 4
- 238000012544 monitoring process Methods 0.000 abstract description 3
- 230000000149 penetrating effect Effects 0.000 abstract 1
- 238000005516 engineering process Methods 0.000 description 6
- 238000001816 cooling Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 241000283216 Phocidae Species 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007667 floating Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000004080 punching Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000010079 rubber tapping Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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Classifications
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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 invention belongs to the technical field of nuclear industry measurement, and particularly relates to a nuclear reactor pool liquid level measuring device which comprises an in-pile pressure guiding pipe, an out-pile pressure guiding pipe, a pressure guiding pipe and a differential pressure transmitter. The differential pressure transmitter is a nuclear safety level differential pressure transmitter. The pressure-leading pipe outside the pile penetrates out of the cofferdam at the upper end of the water pool, and the height of the penetrating point is higher than the highest liquid level of the water pool. The technical scheme provided by the invention does not need to punch, so that the potential safety hazard is not increased. In addition, the device has low cost, convenient installation and simple interface with a control system, and can realize continuous monitoring.
Description
Technical field
The invention belongs to the nuclear industry field of measuring technique, be specifically related to a kind of nuclear reactor pond liquid level measurement mechanism.
Background technology
In industrial processes, level gauging need ubiquity, be mainly used to monitor pond, water tank, and the liquid level of various liquid storage tanks etc.
The device kind that is used for the pond liquid level measurement is a lot, mainly contain Floating Ball Liquid Level measurement mechanism, outer float level measurement mechanism, throw-in type liquid level emasuring device, ultrasonic wave liquid level measuring apparatus etc., because working environment and safe class is different, various measurement mechanisms are also installed, safeguard the restriction of conditions such as safe class.
Heap water level in water pool in the nuclear reactor is the condition precedent that can reactor Natural Circulation cooling set up, and is the nuclear safe level parameter, therefore, to the measurement requirement safety of cooling pond water level in the reactor, accurately, and can not punch on the sidewall in pond.
Summary of the invention
(1) goal of the invention
The object of the invention is to realize that the water level to the nuclear reactor cooling water pond carries out safety, monitoring accurately.
(2) technical scheme
For achieving the above object, the invention provides following technical scheme:
The pond liquid level measurement mechanism comprises pressure guiding pipe, out-pile pressure guiding pipe, connecting pipe and differential pressure transmitter in the heap, and pressure guiding pipe links to each other with the out-pile pressure guiding pipe in the described heap, and the out-pile pressure guiding pipe links to each other with connecting pipe, and connecting pipe passes tight penetration and links to each other with differential pressure transmitter.
Described differential pressure transmitter is the nuclear safe level differential pressure transmitter.
Described out-pile pressure guiding pipe passes from the cofferdam of upper end, pond, and the height of exit points is higher than the highest liquid level in pond.
(3) beneficial effect
Technical scheme provided by the invention need not punched, thereby can not increase potential safety hazard.And this installation cost is low, easy for installation, simple with the control system interface, can realize continuous monitoring.
Description of drawings
Fig. 1 is the synoptic diagram of nuclear reactor pond liquid level measurement mechanism;
Fig. 2 is the measuring principle figure of absolute pressure/differential pressure transmitter;
Wherein, 1 differential pressure transmitter, 2 factory building floors, 3 tight penetrations, 4 connecting pipes, pressure guiding pipe in the 5 out-pile pressure guiding pipes, 6 heaps.
Embodiment
Below in conjunction with accompanying drawing preferred embodiment of the present invention is described further.
Present embodiment discloses applied narrow range pond liquid level measuring system in the Chinese advanced research reactor (CARR), and this system is used for the liquid level in CARR heap pond is monitored, to guarantee the safe operation of reactor.Can the pond liquid level of CARR determining the natural circulation cooling system of CARR set up, and is the nuclear safe level parameter.And, can not destroy the integrality of pool wall to the level gauging of reactor pit, otherwise can increase accident risk.
The pond liquid level measurement mechanism that present embodiment provides comprises pressure guiding pipe, connecting pipe 4 and nuclear safe level differential pressure transmitter 1, and wherein pressure guiding pipe comprises pressure guiding pipe 6 and out-pile pressure guiding pipe 5 in the heap.Pressure guiding pipe 6 links to each other with out-pile pressure guiding pipe 5 in the described heap, and out-pile pressure guiding pipe 5 links to each other with connecting pipe 4, and connecting pipe 4 passes tight penetration 3 and links to each other with nuclear safe level differential pressure transmitter 1.Out-pile pressure guiding pipe 5 passes from the cofferdam of upper end, pond, and the height of exit points is higher than the highest liquid level in pond, thereby avoids guaranteeing that at pool wall side punching impulse pool wall is complete, reduces and leaks.Pressure guiding pipe 6 is from the pond impulse in the described heap, and process out-pile pressure guiding pipe 5 and connecting pipe 4 are sent to nuclear safe level differential pressure transmitter 1 with the pressure of measured point.
In differential pressure transmitter 1 was installed between the instrument technology of piling outside the pond, differential pressure transmitter 1 positive chamber pressure tappings absolute altitude was higher than ground 0.5m between instrument technology; Pressure guiding pipe 6 is lower than between instrument technology ground 0.5m place along the pool wall vertical run from piling absolute altitude in the pond in the heap, and is fixing on the way; Out-pile pressure guiding pipe 5 is higher than by absolute altitude and passes the heap pond in the cofferdam hole to be provided at 6.65m place in ground between instrument technology; The tight penetration 3 self sealss factory buildings of connecting pipe 4 through presetting enter between differential pressure transmitter 1 place technology, join with nuclear safe level differential pressure transmitter 1 then.After the installation, the connecting portion of pressure guiding pipe and transmitter is carried out the sealing property inspection, guarantee the connecting portion ne-leakage.
The output signal of nuclear safe level differential pressure transmitter 1 divides two-way to deliver to any two protection system I/O racks in two redundant channels.
Through test, the result proves that the pond liquid level measurement mechanism that present embodiment provides satisfies the requirement of process system to parameter measurement to the measuring accuracy that CARR piles the narrow range liquid level in pond.
Above content be in conjunction with preferred embodiment to specifying that the present invention did, can not assert that the specific embodiment of the present invention only limits to these explanations.Concerning the general technical staff of the technical field of the invention, without departing from the inventive concept of the premise, can also make some simple deductions and conversion, all should be considered as belonging to protection scope of the present invention.
Claims (3)
1. nuclear reactor pond liquid level measurement mechanism, comprise pressure guiding pipe (6), out-pile pressure guiding pipe (5), connecting pipe (4) and differential pressure transmitter (1) in the heap, pressure guiding pipe (6) links to each other with out-pile pressure guiding pipe (5) in the described heap, out-pile pressure guiding pipe (5) links to each other with connecting pipe (4), and connecting pipe (4) passes tight penetration (3) and links to each other with differential pressure transmitter (1).
2. pond liquid level measurement mechanism according to claim 1 is characterized in that: described differential pressure transmitter (1) is the nuclear safe level differential pressure transmitter.
3. pond liquid level measurement mechanism according to claim 1 and 2 is characterized in that: described out-pile pressure guiding pipe (5) passes from the cofferdam of upper end, pond, and the height of exit points is higher than the highest liquid level in pond.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010105310650A CN102063947A (en) | 2010-10-29 | 2010-10-29 | Liquid level measuring device for nuclear reactor pool |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010105310650A CN102063947A (en) | 2010-10-29 | 2010-10-29 | Liquid level measuring device for nuclear reactor pool |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102063947A true CN102063947A (en) | 2011-05-18 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2010105310650A Pending CN102063947A (en) | 2010-10-29 | 2010-10-29 | Liquid level measuring device for nuclear reactor pool |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102063947A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103219055A (en) * | 2013-04-09 | 2013-07-24 | 上海交通大学 | Device for detecting clearance flow instability phenomenon in nuclear reactor |
| CN103871522A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | Pressurizer water level measurement method based on digitalization technology |
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN111145928A (en) * | 2018-11-06 | 2020-05-12 | 中核核电运行管理有限公司 | Cofferdam device for sealing and isolating nuclear reactor refueling water pool |
-
2010
- 2010-10-29 CN CN2010105310650A patent/CN102063947A/en active Pending
Non-Patent Citations (1)
| Title |
|---|
| 《原子能科学技术》 20060120 李松等 中国先进研究堆堆水池窄量程液位测量方案选择及误差分析 , 第01期 * |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103871522A (en) * | 2012-12-11 | 2014-06-18 | 中国核动力研究设计院 | Pressurizer water level measurement method based on digitalization technology |
| CN103219055A (en) * | 2013-04-09 | 2013-07-24 | 上海交通大学 | Device for detecting clearance flow instability phenomenon in nuclear reactor |
| CN103219055B (en) * | 2013-04-09 | 2015-06-24 | 上海交通大学 | Device for detecting clearance flow instability phenomenon in nuclear reactor |
| CN105719707A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Differential pressure measuring point layout structure in pressurized water reactor integral hydraulic simulation test |
| CN111145928A (en) * | 2018-11-06 | 2020-05-12 | 中核核电运行管理有限公司 | Cofferdam device for sealing and isolating nuclear reactor refueling water pool |
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| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C02 | Deemed withdrawal of patent application after publication (patent law 2001) | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20110518 |