CN203858868U - Temperature control device for nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in cold region - Google Patents
Temperature control device for nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in cold region Download PDFInfo
- Publication number
- CN203858868U CN203858868U CN201420294575.4U CN201420294575U CN203858868U CN 203858868 U CN203858868 U CN 203858868U CN 201420294575 U CN201420294575 U CN 201420294575U CN 203858868 U CN203858868 U CN 203858868U
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- Prior art keywords
- boron
- rea
- pipeline
- temperature control
- passes
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- Expired - Lifetime
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title abstract description 3
- 238000009413 insulation Methods 0.000 claims abstract description 11
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 78
- 229910052796 boron Inorganic materials 0.000 claims description 78
- 239000000523 sample Substances 0.000 claims description 16
- 238000012544 monitoring process Methods 0.000 claims description 6
- 239000002184 metal Substances 0.000 claims description 3
- 238000013461 design Methods 0.000 abstract description 8
- 239000002699 waste material Substances 0.000 abstract description 3
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 6
- 239000004327 boric acid Substances 0.000 description 6
- 238000002425 crystallisation Methods 0.000 description 5
- 230000008025 crystallization Effects 0.000 description 5
- 238000010438 heat treatment Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 239000002253 acid Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000008439 repair process Effects 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- 240000007594 Oryza sativa Species 0.000 description 1
- 235000007164 Oryza sativa Nutrition 0.000 description 1
- 150000001638 boron Chemical class 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005485 electric heating Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 235000009566 rice Nutrition 0.000 description 1
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model discloses a temperature control device for a nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in a cold region. The temperature control device comprises a heat insulation layer wrapped on the outer surface of the REA boron-conveying pipeline and at least two temperature control series, wherein each temperature control series comprises a plurality of heat tracing cables coated on the outer surfaces of the different pipe sections of the REA boron-conveying pipeline. Compared with the prior art, according to the temperature control device for the nuclear power plant REA boron-conveying pipeline in the cold region, disclosed by the utility model, a mode of left and right parallel heat tracing cables is added on the basis of the original heat tracing design, thus greatly realizing the purpose of extending the heat tracing pipeline of an REA boron-conveying loop, and avoiding the waste caused by detaching the original heat tracing equipment.
Description
Technical field
The utility model relates to debugging and the operation field of nuclear power station, relates in particular to a kind of attemperating unit of cold district nuclear power station REA biography boron pipeline.
Background technology
In nuclear power station, boric acid closed circuit is as a subsystem of RIS (safety injection system) high-pressure safety injection function, act on very importantly, the dense boric acid that its medium is 7000ppm, all comes from REA (reactor boron and water make-up system) and passes boron pipeline; And the function of boron heating system is exactly to heat to the pipeline that has boric acid medium, valve and pump, to prevent boric acid crystallization.
The temperature control series of boron heating system comprises the hot components and parts of multiple companions, and the accompanying heat cable of the pipe surface that is wherein laid in and heat-insulation layer are the force at the cores that maintains heating function.Existing REA passes boron pipeline attemperating unit and comprises the heat-insulation layer and two the independently temperature control series that are wrapped in REA biography boron pipeline outside surface; Each temperature control series all comprises that the REA that is laid in passes an accompanying heat cable and the mechanical temperature controller on boron pipeline outside surface, and the power supply upstream of accompanying heat cable is provided with relay; With time limit temperature-control range by the break-make of pilot relay, and extend the serviceable life of accompanying heat cable by interruption work.
Refer to Fig. 1, because existing nuclear power station is positioned at the torrid zone or temperate zone mostly, therefore REA passes on boron pipeline 40 (REA is connected to the biography boron pipeline of RIS) only has part pipeline section BC to be provided with accompanying heat cable 42.But along with the development of nuclear power, a lot of nuclear power stations need to be built in cold district, therefore the shorter accompanying heat cable 42 of existing companion's thermal region is under cold climate, and the medium temperature that often cannot make REA pass in boron pipeline 40 reaches the designing requirement that prevents boric acid crystallization, so that has affected the realization that passes boron function.
Large, with high costs in view of redesigning and install electrically heat tracing workload, and can affect the construction progress of nuclear power station, therefore need by existing attemperating unit being improved to solve the not enough problem of companion's heat.For this reason, someone proposes to accompany the input voltage grade of hot loop to reach the object of hoisting power by raising, but there is following problem in this scheme: 1) be limited by the impact of the output voltage grade of RRB electric heating plate cabinet transformer, the selection degree of freedom of voltage is lower; 2) be limited by the design characteristics (according to the requirement of producer companion thermal design calculated description, the rice power of accompanying heat cable 42 can not exceed this safety load of 75W) of accompanying heat cable 42, power ascension limited space; 3) increase the load of accompanying heat cable 42, may affect its serviceable life and reliability; 4) companion's thermal design omission of REA biography boron pipeline 40 is more, realizes the overall object of heating by promoting amount of localized heat, less feasible.
In view of this, the necessary attemperating unit that a kind of cold district nuclear power station REA biography boron pipeline that can prevent the crystallization of REA biography boron pipeline mesoboric acid is provided.
Utility model content
The purpose of this utility model is: provide a kind of and can prevent that REA from passing the attemperating unit of the cold district nuclear power station REA biography boron pipeline of boron pipeline mesoboric acid crystallization.
To achieve these goals, the attemperating unit that the utility model provides a kind of cold district nuclear power station REA to pass boron pipeline, it comprises the heat-insulation layer and at least two the temperature control series that are wrapped in REA biography boron pipeline outside surface; Each temperature control series comprises that being laid in REA passes many accompanying heat cables on boron pipeline different pipe sections outside surface.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and the common companion's thermal region forming of many accompanying heat cables of described arbitrary temperature control series has covered at least 90% pipeline section of REA biography boron pipeline.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and the common companion's thermal region forming of many accompanying heat cables of described arbitrary temperature control series is preferably the whole pipeline sections that cover REA and pass boron pipeline.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and many accompanying heat cables of described arbitrary temperature control series are in parallel and by same Power supply.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and many accompanying heat cables of described arbitrary temperature control series are by same relay temperature control.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and described each temperature control series also comprises that at least one is provided with the temperature controller of temperature probe, and the temperature probe of temperature controller is laid in REA and passes the minimum warm spot on boron pipeline.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, the quantity of described temperature control series is two and for subsequent use each other, each temperature control series only comprises a temperature controller, and the temperature controller temperature probe of two temperature control series is closely adjacent to each other and is arranged at the minimum warm spot on REA biography boron pipeline.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and described temperature controller selects mechanical temperature controller to improve accuracy of temperature control.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, described each temperature control series also comprises a master control temperature monitoring probe that is arranged at REA biography boron pipeline outside surface, and master control temperature monitoring probe is close to the temperature probe setting of temperature controller and the temperature value of REA biography boron pipeline is monitored.
The one that passes the attemperating unit of boron pipeline as the utility model cold district nuclear power station REA is improved, and described heat-insulation layer is provided with coat of metal outward, and accompanying heat cable is laid in REA and passes the outside surface of boron pipeline and wrapped up by heat-insulation layer together with passing boron pipeline with REA.
Compared with prior art, the utility model cold district nuclear power station REA passes the attemperating unit of boron pipeline by increasing the mode of left and right accompanying heat cable in parallel on the basis in original companion's thermal design, realize well prolongation REA biography boron loop and accompanied hot object, avoided removing the waste that the hot equipment of original companion causes.
Brief description of the drawings
Below in conjunction with the drawings and specific embodiments, the attemperating unit and the beneficial effect thereof that the utility model cold district nuclear power station REA are passed to boron pipeline are elaborated.
Fig. 1 is companion's thermal region schematic diagram that existing REA passes boron pipeline attemperating unit.
Fig. 2 is companion's thermal region schematic diagram that the utility model cold district nuclear power station REA passes the attemperating unit of boron pipeline.
Fig. 3 is the cross-sectional schematic that the utility model cold district nuclear power station REA passes boron pipeline.
Fig. 4 is the electrical schematic diagram that the utility model cold district nuclear power station REA passes the attemperating unit of boron pipeline.
Embodiment
In order to make the purpose of this utility model, technical scheme and useful technique effect thereof more clear, below in conjunction with the drawings and specific embodiments, the utility model is further elaborated.Should be understood that, the embodiment of describing in this instructions is only used to explain the utility model, is not intended to limit the utility model.
Refer to Fig. 2 and Fig. 3, the attemperating unit that the utility model cold district nuclear power station REA passes boron pipeline comprises that being wrapped in REA passes the heat-insulation layer 20 of boron pipeline 10 (REA is connected to the biography boron pipeline of RIS) outside surface and two independent temperature series for subsequent use each other.Wherein, the outer coat of metal 200 that is provided with of heat-insulation layer 20.
Each temperature control series all comprises many accompanying heat cables 22 (in Fig. 2 illustrated embodiment being three), a mechanical temperature controller 24 and a master control temperature monitoring probe 26.Wherein, many accompanying heat cables 22 are laid in end to end REA and pass on boron pipeline 10 different pipe sections outside surfaces, as can be seen from Figure 2, the common companion's thermal region AD forming of many accompanying heat cables 22 of same temperature control series has covered 90% above pipeline section of REA biography boron pipeline 10, but in different embodiments, this ratio is more high better, is preferably and covers whole pipeline sections.The accompanying heat cable 22 of two temperature control series is located at the diverse location of REA biography boron pipeline 10 outside surfaces, 240 of the temperature probes of two mechanical temperature controllers 24 are closely adjacent to each other and are laid in REA and pass the minimum warm spot on boron pipeline 10, and master control temperature monitoring probe 26 is arranged on REA and passes and on boron pipeline 10 outside surfaces, be close to temperature probe 240 places and the temperature value that REA passes boron pipeline 10 is monitored.
Refer to Fig. 4, many accompanying heat cables 22 of same temperature control series form shunt circuit and are powered by same power supply 28; The upstream of accompanying heat cable 22 is provided with the relay 30 that many accompanying heat cables 22 in parallel are carried out to temperature control, with time limit temperature-control range by the break-make of pilot relay 30, and extend the serviceable life of accompanying heat cable 22 by interruption work.
Known by above description, the attemperating unit that the utility model cold district nuclear power station REA passes boron pipeline is on the basis of original companion's thermal design, by increasing accompanying heat cable 22 in parallel and adopting the mode of integrated temperature control to reach the object that extends REA biography boron pipeline 10 trace pipe sections, it at least has the following advantages:
1) by the mode in accompanying heat cable in parallel 22 loops, newly-increased left and right, realize well the object that extends REA biography boron loop trace pipe section, avoid removing the waste that the hot equipment of original companion causes;
2) the utility model still adopts original temperature controller 24 and temperature control measuring point to carry out temperature control, what choose due to original point for measuring temperature is the minimum warm spot of the hot relevant range of whole companion, therefore such design can ensure that companion's heat that whole REA passes boron pipeline 10 reaches designing requirement, has effectively stopped dense boric acid and occur in flow process the risk of crystallization;
3) adopt same relay 30 to carry out temperature control to original loop and two newly-increased loops, scheme simply and is technically easy to realize simultaneously, only need carry out certain amendment to the wire jumper of the relay circuit in temperature control dish cabinet;
4) with using newly-increased loop compared with the design of independent temperature control loop, integrated temperature control mode drops into more resource without extra, is conducive to cost savings, and can be that Maintenance and Repair in the future reduce workload and investigate difficulty;
5) compared with accompanying the isometric accompanying heat cable companion heat of thermal region with one of employing with REA biography boron pipeline 10, being designed with of many accompanying heat cables 22 is beneficial to the workload of minimizing Maintenance and Repair and investigates difficulty.
The announcement of book and instruction according to the above description, the utility model those skilled in the art can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, the utility model is not limited to embodiment disclosed and described above, also should fall in the protection domain of claim of the present utility model modifications and changes more of the present utility model.In addition,, although used some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the utility model.
Claims (10)
1. cold district nuclear power station REA passes an attemperating unit for boron pipeline, it is characterized in that: comprise the heat-insulation layer and at least two the temperature control series that are wrapped in REA biography boron pipeline outside surface; Each temperature control series comprises that being laid in REA passes many accompanying heat cables on boron pipeline different pipe sections outside surface.
2. cold district nuclear power station REA according to claim 1 passes the attemperating unit of boron pipeline, it is characterized in that: the common companion's thermal region forming of many accompanying heat cables of described arbitrary temperature control series has covered at least 90% pipeline section of REA biography boron pipeline.
3. cold district nuclear power station REA according to claim 2 passes the attemperating unit of boron pipeline, it is characterized in that: the common companion's thermal region forming of many accompanying heat cables of described arbitrary temperature control series is preferably the whole pipeline sections that cover REA biography boron pipeline.
4. cold district nuclear power station REA according to claim 1 passes the attemperating unit of boron pipeline, it is characterized in that: many accompanying heat cables of described arbitrary temperature control series are in parallel and by same Power supply.
5. cold district nuclear power station REA according to claim 4 passes the attemperating unit of boron pipeline, it is characterized in that: many accompanying heat cables of described arbitrary temperature control series are by same relay temperature control.
6. cold district nuclear power station REA according to claim 1 passes the attemperating unit of boron pipeline, it is characterized in that: described each temperature control series also comprises that at least one is provided with the temperature controller of temperature probe, the temperature probe of temperature controller is laid in REA and passes the minimum warm spot on boron pipeline.
7. cold district nuclear power station REA according to claim 6 passes the attemperating unit of boron pipeline, it is characterized in that: the quantity of described temperature control series is two and for subsequent use each other, each temperature control series only comprises a temperature controller, and the temperature controller temperature probe of two temperature control series is closely adjacent to each other and is arranged at the minimum warm spot on REA biography boron pipeline.
8. the attemperating unit that passes boron pipeline according to the cold district nuclear power station REA described in claim 6 or 7, is characterized in that: described temperature controller is mechanical temperature controller.
9. cold district nuclear power station REA according to claim 7 passes the attemperating unit of boron pipeline, it is characterized in that: described each temperature control series also comprises a master control temperature monitoring probe that is arranged at REA biography boron pipeline outside surface, and master control temperature monitoring probe is close to the temperature probe setting of temperature controller and the temperature value of REA biography boron pipeline is monitored.
10. cold district nuclear power station REA according to claim 1 passes the attemperating unit of boron pipeline; it is characterized in that: described heat-insulation layer is provided with coat of metal outward, accompanying heat cable is laid in REA and passes the outside surface of boron pipeline and wrapped up by heat-insulation layer together with passing boron pipeline with REA.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420294575.4U CN203858868U (en) | 2014-06-04 | 2014-06-04 | Temperature control device for nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in cold region |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420294575.4U CN203858868U (en) | 2014-06-04 | 2014-06-04 | Temperature control device for nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in cold region |
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| Publication Number | Publication Date |
|---|---|
| CN203858868U true CN203858868U (en) | 2014-10-01 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201420294575.4U Expired - Lifetime CN203858868U (en) | 2014-06-04 | 2014-06-04 | Temperature control device for nuclear power plant REA (reactor tent and water supply system) boron-conveying pipeline in cold region |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106448759A (en) * | 2016-10-19 | 2017-02-22 | 中国核电工程有限公司 | Nuclear power station heater automatic control system effectiveness detecting method |
| TWI649763B (en) * | 2016-02-04 | 2019-02-01 | 日商三菱重工業股份有限公司 | Identification system, vibration generating device and identification method |
| CN106598098B (en) * | 2016-12-16 | 2019-04-16 | 中广核工程有限公司 | Intelligent nuclear power plant technique pipeline tracing device |
-
2014
- 2014-06-04 CN CN201420294575.4U patent/CN203858868U/en not_active Expired - Lifetime
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| TWI649763B (en) * | 2016-02-04 | 2019-02-01 | 日商三菱重工業股份有限公司 | Identification system, vibration generating device and identification method |
| CN106448759A (en) * | 2016-10-19 | 2017-02-22 | 中国核电工程有限公司 | Nuclear power station heater automatic control system effectiveness detecting method |
| CN106448759B (en) * | 2016-10-19 | 2021-09-17 | 中国核电工程有限公司 | Effectiveness detection method for automatic control system of nuclear power station heater |
| CN106598098B (en) * | 2016-12-16 | 2019-04-16 | 中广核工程有限公司 | Intelligent nuclear power plant technique pipeline tracing device |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20141001 |