CN203376652U - A temperature self-adjusting structure for a nuclear power station equipment cooling water system - Google Patents
A temperature self-adjusting structure for a nuclear power station equipment cooling water system Download PDFInfo
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- CN203376652U CN203376652U CN201320428896.4U CN201320428896U CN203376652U CN 203376652 U CN203376652 U CN 203376652U CN 201320428896 U CN201320428896 U CN 201320428896U CN 203376652 U CN203376652 U CN 203376652U
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- cooling water
- nuclear power
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- rri
- temperature self
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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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Abstract
The utility model discloses a temperature self-adjusting structure for a nuclear power station equipment cooling water system. The temperature self-adjusting structure comprises RRI/SEC heat exchangers and bypass branches connected in parallel with RRI heat exchanger sides. Differential pressure control valves are disposed at the downstream part of the RRI/SEC heat exchangers. Compared with a product in the prior art, with the differential pressure control valves disposed at the downstream part of the RRI/SEC heat exchangers, the temperature self-adjusting structure for a nuclear power station equipment cooling water system guarantees a negligible influence of the automatic adjustment of the bypass branches on the total differential pressure of a parallel loop. Therefore, the total flow of a system is hardly changed and a problem of downstream flow distribution change is effectively prevented.
Description
Technical field
The utility model relates to the design of pressurized-water reactor nuclear power plant cooling water system, and more particularly, the utility model relates to a kind of nuclear power plant equipment cooling water system temperature self-regulating joint structure.
Background technology
Two generations and two generation the pressure (hydraulic) water reactor of nuclear power plant, require component cooling water system (RRI, Component Cooling Water System) and essential service water system (SEC, Essential Service Water System) the potential site condition of overall design in can the larger latitude scope in the domestic north and south of envelope, it is-2.5～33.5 ℃ that instant heating trap (sea, rivers, atmosphere) temperature design needs limit of consideration.In design process, mainly need reply cold climate condition, therefore, the ocean temperature that may cause under extreme weather conditions factory site is distinguished and is defined: 1) low temperature factory site: refer under historical extreme cold condition, the area of ocean temperature≤0 ℃, this type of factory site appears at domestic North of Yangtze River area usually; 2) warm factory site in: refer under historical extreme cold condition, ocean temperature meets the area of 0 ℃<ocean temperature≤15 ℃, and this type of factory site appears on the south domestic the Changjiang river, to the north of the Zhujiang River usually; 3) high temperature factory site: refer to that under historical extreme cold condition, ocean temperature also is not less than the area of 15 ℃, this type of factory site appears at domestic Zhujiang River areas to the south usually.That is to say, select 15 ℃ as high, middle temperature factory site boundary temperature, and in 0 ℃ of conduct, the boundary temperature in low temperature factory site, the actual temp in each factory site is as the criterion with oceanic observation over the years, locality data.
For the middle temperature factory site that freezing phenomenon does not occur, when hot trap temperature is low, the exchange capability of heat of RRI system will continue to strengthen, so that low-temperature cooling water has influence on part nuclear island user's safe and stable operation; Especially some HVAC system, its handpiece Water Chilling Units at low temperatures, can't set up by condenser pressure reduction, may cause the handpiece Water Chilling Units chaser, finally affects the safe and stable operation of unit.
In order to meet the downstream user requirement, in existing part, the RRI system in warm factory site adopts the heat exchanger bypass scheme: refer to Fig. 1, set up bypass line 12 by the RRI side of the RRI/SEC heat interchanger 10 in parallel in each series of RRI system and form the bypass branch road, electronic isolation valve 14 and electric control valve 16 are set on bypass line 12.When ocean temperature, during higher than 15 ℃, the electronic isolation valve 14 on bypass line 12 cuts out, and the bypass branch road is cut off and is inoperative; When ocean temperature is equal to or less than 15 ℃, the electronic isolation valve 14 of bypass line 12 is opened, electric control valve 16 is according to ocean temperature and load variations, automatic regulating switch state and degree, adjustment enters the flow of the RRI side of RRI/SEC heat interchanger 10, make coolingly by RRI/SEC heat interchanger 10 to establish the cold water mix of establishing that cold water and bypass branch road be not cooled, thus improve heat interchanger 10 the RRI system outlet establish cold water temperature, it is remained between 18 ℃-32 ℃; In this process, if electric control valve 16 has been adjusted to standard-sized sheet automatically, keep full-gear.
Although said temperature self-regulation structure can improve heat interchanger 10 the RRI side outlet establish cold water temperature, but, limit value due to the factory building condition, the space of on the bypass line 12 of RRI system heat exchanger 10, flow instrument not being installed, make the total flow of RRI side to measure, heat exchanger performance test calculates can only rely on the mode of averaging, and causes the thermal load result to have certain error.In addition, due to the existence of bypass branch road, make the pressure drop at heat interchanger 10 two ends reduce, cause the loop total flow to change, may under some extreme operating condition, cause the required underfed of user or super flow.
In view of this, necessaryly provide a kind of nuclear power plant equipment cooling water system temperature self-regulating joint structure that does not affect RRI side total flow.
The utility model content
The purpose of this utility model is: a kind of nuclear power plant equipment cooling water system temperature self-regulating joint structure that does not affect RRI side total flow is provided.
To achieve these goals, the utility model provides a kind of nuclear power plant equipment cooling water system temperature self-regulating joint structure, and it comprises RRI/SEC heat interchanger and the bypass branch road in parallel with heat interchanger RRI side, and RRI/SEC heat interchanger downstream is provided with differential pressure control valve.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described differential pressure control valve is positioned on the heat interchanger branch road with the bypass branch circuit parallel connection.
A kind of improvement as the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, the two ends of described differential pressure control valve are connected by pressure gauge, and the pressure reduction at manometry differential pressure control valve two ends is also regulated the aperture of differential pressure control valve by control loop.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, the pressure drop of described differential pressure control valve is set as steady state value, and steady state value can be modified according to different situations.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described differential pressure control valve be adjusted to automatic mode.
A kind of improvement as the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described heat exchanger bypass branch road comprises bypass line and bypass regulator valve, bypass line is located at the RRI side of RRI/SEC heat interchanger and in parallel with heat interchanger, and bypass regulator valve is located on bypass line and the flow of bypass branch road is regulated.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described bypass branch road is provided with the downstream line after the heat interchanger branch road converges the thermometer be connected with the control loop of bypass regulator valve.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described bypass regulator valve be adjusted to automatic mode.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, the control signal of described bypass regulator valve is safe level.
As a kind of improvement of the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure, described RRI/SEC heat interchanger is series heat interchanger in parallel, and each heat interchanger all is provided with separately the bypass branch road in parallel with its RRI side.
Compared with prior art, the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure arranges differential pressure control valve by the downstream at the RRI/SEC heat interchanger, guaranteed that the automatic adjusting of bypass branch road almost can ignore the impact of shunt circuit total pressure head, thereby the system total flow of making changes hardly, effectively avoided the problem that occurs that the downstream flow distribution changes.
The accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure and beneficial effect thereof are elaborated, wherein:
Fig. 1 is the schematic diagram of existing nuclear power plant equipment cooling water system temperature self-regulating joint structure.
The schematic diagram that Fig. 2 is the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure.
Embodiment
In order to make goal of the invention of the present 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 in order to explain the utility model, not in order to limit the utility model.
Refer to shown in Fig. 2, the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure comprises: RRI/SEC heat interchanger 30, bypass line 32, bypass regulator valve 34 and differential pressure control valve 36.
RRI/SEC heat interchanger 30 is series heat interchanger in parallel.Bypass line 32 is located at the RRI side of each heat interchanger 30 and in parallel with this heat interchanger 30 and form the heat exchanger bypass branch road.Bypass regulator valve 34 is located on bypass line 32 and the flow of bypass branch road is regulated.Differential pressure control valve 36 is located at the downstream of heat interchanger 30, it is positioned on the heat interchanger branch road with the bypass branch circuit parallel connection, and pressure drop is set as to a certain steady state value, less to guarantee that pressure reduction on heat interchanger 30 two ends pipelines changes, make the total flow of RRI system circuit be subject to hardly the impact of bypass branch road.
The bypass branch road is provided with the downstream line after the heat interchanger branch road converges the thermometer 42 be connected with the control loop of bypass regulator valve 34.
The two ends of differential pressure control valve 36 are connected by pressure gauge 44, and pressure gauge 44 is measured the pressure reduction at differential pressure control valve 36 two ends and by control loop, the aperture of poor operation valve 36 regulated.
The adjusting of bypass regulator valve 34 and differential pressure control valve 36 is all automatic mode, and the control signal of bypass regulator valve 34 is safe level.
During the nuclear power station Power operation, only need a pump 40 and heat interchanger 30 operations, or, according to reactor type difference, use a pump 40 and two heat interchanger 30 operations; During nuclear power station startup or shutdown, two pumps 40 and two heat interchanger 30 all need to put into operation.Due under above-mentioned different situations, the mode that the bypass branch road is regulated the cooling water system temperature is basically identical, and therefore no longer a minute situation is described.
At heat interchanger 30 run durations, when ocean temperature during higher than 15 ℃, bypass regulator valve 34 is in closed condition, equipment establish cold water all by heat interchanger 30 by cooled with seawater.
When ocean temperature is equal to or less than 15 ℃, 30 outlets of RRI heat interchanger detected once three thermometers 42 in heat interchanger 30 downstreams and establish the temperature of cold water lower than 18 ℃, just automatically by control signal, slowly open bypass regulator valve 34, bypass regulator valve 34 is slowly opened, and the temperature that the adoption rate integral method is established cold water by 30 outlets of RRI heat interchanger is controlled at 25 ℃ (thermometer 42 readings are 25 ℃); When RRI heat interchanger 30 outlet temperatures, during higher than 35 ℃, control signal slowly closing bypass regulator valve 34, be equally also the adoption rate integral method, and RRI heat interchanger 30 outlet temperatures are controlled to 25 ℃.In adjustment process, reason due to bypass regulator valve 34 apertures variations, the pressure reduction of bypass branch road will change, now pressure gauge 44 is measured the pressure reduction at differential pressure control valve 36 two ends the aperture of regulating differential pressure control valve 36, make the pressure reduction at its two ends be fixed on 0.35MPa (this numerical value is setting value, can be adjusted according to actual conditions).
Under the LOCA accident conditions, no matter whether the temperature of seawater higher than 15 ℃, the reactor protection signal is all controlled bypass regulator valve 34 and is closed, and allows all RRI establish cold water all by cooled with seawater, to guarantee the safety of reactor.
Although above-mentioned embodiment is to take nuclear power station that hot trap is seawater to describe as example, apparent, the utility model is equally applicable to the inland nuclear power station that hot trap is rivers or atmosphere.
Known by above description, the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure has the following advantages:
1) in the winter time under operational mode, can utilize the hot fluid of RRI heat interchanger 30 bypass branch roads, improve the coolant outlet water temperature, meet user's water temperature low temperature requirement, for the stable operation that guarantees these users provides guarantee;
2) differential pressure control valve 36 is set on the heat interchanger branch road, and the automatic adjusting of differential pressure control valve 36 is fixed on some setting differential pressures, guarantee that the automatic adjusting of bypass line 32 almost can ignore the impact of shunt circuit total pressure head, thereby the system total flow of making changes hardly, also with regard to having avoided, bring downstream flow to distribute the problem changed;
3) adjusting of bypass regulator valve 34 and differential pressure control valve 36 is automatic mode, does not need Operator actions, and operation is simple;
4) control signal is safe level, can make bypass regulator valve 34 close after unit has an accident, and effectively guarantees the safety of unit.
Visible, compared with prior art, the utility model nuclear power plant equipment cooling water system temperature self-regulating joint structure has not only solved the problem that lower the brought cooling water temperature of middle temperature nuclear power station ocean temperature in winter does not meet the user in certain usable range, realized the automatic adjusting of ocean temperature in 0～15 ℃ of interval, RRI system outlet temperature is controlled between 15 ℃～35 ℃, and can not have influence on the total flow of RRI system circuit, the required underfed of user or super problems of liquid flow under some extreme operating condition of having avoided the bypass branch road to cause.
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 modification to above-mentioned embodiment.Therefore, the utility model is not limited to embodiment disclosed and described above, to modifications and changes more of the present utility model, also should fall in the protection domain of claim 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. a nuclear power plant equipment cooling water system temperature self-regulating saves structure, and it is characterized in that: comprise RRI/SEC heat interchanger and the bypass branch road in parallel with heat interchanger RRI side, RRI/SEC heat interchanger downstream is provided with differential pressure control valve.
2. nuclear power plant equipment cooling water system temperature self-regulating according to claim 1 joint structure is characterized in that: described differential pressure control valve is positioned on the heat interchanger branch road with the bypass branch circuit parallel connection.
3. nuclear power plant equipment cooling water system temperature self-regulating according to claim 2 saves structure, it is characterized in that: the two ends of described differential pressure control valve are connected by pressure gauge, and the pressure reduction at manometry differential pressure control valve two ends is also regulated the aperture of differential pressure control valve by control loop.
4. nuclear power plant equipment cooling water system temperature self-regulating according to claim 2 saves structure, and it is characterized in that: the pressure drop of described differential pressure control valve is set as steady state value, and steady state value can be modified according to different situations.
5. nuclear power plant equipment cooling water system temperature self-regulating according to claim 2 joint structure is characterized in that: described differential pressure control valve be adjusted to automatic mode.
6. nuclear power plant equipment cooling water system temperature self-regulating according to claim 1 saves structure, it is characterized in that: described heat exchanger bypass branch road comprises bypass line and bypass regulator valve, bypass line is located at the RRI side of RRI/SEC heat interchanger and in parallel with heat interchanger, and bypass regulator valve is located on bypass line and the flow of bypass branch road is regulated.
7. nuclear power plant equipment cooling water system temperature self-regulating according to claim 6 joint structure is characterized in that: described bypass branch road is provided with the downstream line after the heat interchanger branch road converges the thermometer be connected with the control loop of bypass regulator valve.
8. nuclear power plant equipment cooling water system temperature self-regulating according to claim 6 joint structure is characterized in that: described bypass regulator valve be adjusted to automatic mode.
9. nuclear power plant equipment cooling water system temperature self-regulating according to claim 6 saves structure, and it is characterized in that: the control signal of described bypass regulator valve is safe level.
10. according to the described nuclear power plant equipment cooling water system of any one in claim 1 to 9 temperature self-regulating joint structure, it is characterized in that: described RRI/SEC heat interchanger is series heat interchanger in parallel, and each heat interchanger all is provided with separately the bypass branch road in parallel with its RRI side.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201320428896.4U CN203376652U (en) | 2013-07-18 | 2013-07-18 | A temperature self-adjusting structure for a nuclear power station equipment cooling water system |
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| CN201320428896.4U CN203376652U (en) | 2013-07-18 | 2013-07-18 | A temperature self-adjusting structure for a nuclear power station equipment cooling water system |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105551548A (en) * | 2016-01-25 | 2016-05-04 | 中国核电工程有限公司 | Nuclear power plant equipment cooling water system and water temperature adjusting method therefor |
| CN110176319A (en) * | 2019-05-27 | 2019-08-27 | 中国船舶重工集团公司第七一九研究所 | A kind of marine PWR center cooling system of fresh water |
-
2013
- 2013-07-18 CN CN201320428896.4U patent/CN203376652U/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105551548A (en) * | 2016-01-25 | 2016-05-04 | 中国核电工程有限公司 | Nuclear power plant equipment cooling water system and water temperature adjusting method therefor |
| CN110176319A (en) * | 2019-05-27 | 2019-08-27 | 中国船舶重工集团公司第七一九研究所 | A kind of marine PWR center cooling system of fresh water |
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Granted publication date: 20140101 |