CN112530617A - Primary loop cooling method and device under power loss working condition of whole plant - Google Patents
Primary loop cooling method and device under power loss working condition of whole plant Download PDFInfo
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- CN112530617A CN112530617A CN202011243555.0A CN202011243555A CN112530617A CN 112530617 A CN112530617 A CN 112530617A CN 202011243555 A CN202011243555 A CN 202011243555A CN 112530617 A CN112530617 A CN 112530617A
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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Abstract
The invention relates to a primary circuit cooling method and a primary circuit cooling device under the power loss working condition of a whole plant, wherein the method comprises the following steps: acquiring an emergency bus voltage signal, judging whether the time that the emergency bus voltage signal is less than a threshold value exceeds a preset time, if so, confirming the power loss of the whole plant, acquiring a core outlet coolant supercooling degree signal and a pressure vessel water level signal in a primary circuit, and judging whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold value; and if the supercooling degree signal of the coolant at the reactor core outlet and the water level signal of the pressure vessel are lower than the threshold values, confirming that the coolant loss accident occurs in the primary circuit and controlling the opening of the atmospheric release valve. The above-mentioned scheme that this application provided can whether take place the coolant loss under the whole factory power loss operating mode of rapid judgement, if take place the coolant loss accident, can implement automatic quick cooling to a return circuit through control atmosphere relief valve, and then reduced the possibility that the operator human error takes place, promoted nuclear power plant's safety level.
Description
Technical Field
The invention relates to the technical field of nuclear safety, in particular to a primary circuit cooling method and a primary circuit cooling device under the power-off working condition of a whole plant.
Background
The whole plant power loss is one of typical accidents which must be considered by a nuclear power plant. The Japanese Fudao nuclear accident shows that after the nuclear power plant has a power loss accident of the whole plant, if the countermeasure is unfavorable, the reactor core is finally melted and the radioactive environment is released, thereby causing serious influence on the environment and public health.
For a pressurized water reactor nuclear power plant, under the condition of power loss of the whole plant, all specially-designed safety facilities including a safety injection pump, a containment spray pump and an electric auxiliary water feeding pump lose power supplies, and only a storage battery is left to maintain the power supply of part of instrument control systems, so that the monitoring of a small amount of key safety parameters and the control of some important valves are ensured. Therefore, under the condition of power loss of the whole plant, the aim is to maintain the steam-driven auxiliary water feeding pump to supply water to the steam generator as much as possible, and discharge the heat of a primary loop by opening the steam atmosphere release valve, so that the temperature of a primary loop cold pipe section is stabilized at a high temperature to ensure that enough steam is generated on the secondary side of the steam generator, the steam-driven auxiliary water feeding pump is driven, and meanwhile, the consumption of secondary side water storage is reduced as much as possible.
However, under the power loss operating mode of whole plant, because main pump bearing seal injection line loses, the sealing performance of main pump bearing seal receives serious challenge and finally evolves into the bearing seal breach, the primary circuit coolant will discharge outward through the breach of bearing seal department, the continuous deterioration that will lead to reactor core cooling state of losing of primary circuit coolant, from the angle of protection reactor core integrality, should implement quick cooling to the primary circuit, reduce a circuit temperature and pressure as far as possible, restrict a circuit coolant loss rate, ensure reactor core safety, prevent or delay the reactor core and damage.
Under the condition of power loss of a whole plant, the temperature and the pressure of a primary circuit are required to be stable as much as possible from the viewpoint of ensuring that a steam-driven auxiliary water feeding pump is available and reducing the consumption of secondary side water storage, but under the condition of a superposed shaft seal break, the pressure and the temperature of the primary circuit are required to be reduced as soon as possible, and the control strategies of the pressure and the temperature conflict with each other, so that the control of a unit under an accident is extremely unfavorable, and the possibility of human error of an operator is increased.
Disclosure of Invention
Therefore, it is necessary to provide a method and a device for cooling a primary circuit under a power-loss condition of a whole plant, aiming at the problem that when a break-open coolant loss accident occurs in the primary circuit of a nuclear reactor under the power-loss condition of the whole plant, the accident is further worsened due to the probability of human error.
The invention provides a primary circuit cooling method under the power-loss working condition of a whole plant, which comprises the following steps:
acquiring an emergency bus voltage signal, judging whether the time that the emergency bus voltage signal is less than a threshold value exceeds preset time, if so, confirming power loss of the whole plant, and meanwhile, confirming power loss of the whole plant
Obtaining a core outlet coolant supercooling degree signal and a pressure vessel water level signal in a primary circuit, and judging whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than a threshold value;
and if the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit and controlling an atmospheric release valve to open.
According to the primary loop cooling method under the power-off working condition of the whole plant, whether coolant loss occurs or not can be quickly judged, if a coolant loss accident occurs, automatic and quick cooling can be carried out on the primary loop through controlling the atmospheric release valve, the possibility of human error occurrence of operators is further reduced, and the safety level of a nuclear power plant is improved.
In one embodiment, the obtaining the emergency bus voltage signal and determining whether the time that the emergency bus voltage signal is less than the threshold exceeds a preset time includes:
the method comprises the steps of obtaining two voltage signals corresponding to at least two emergency buses arranged in parallel, judging whether the time that the two voltage signals are smaller than a threshold value exceeds preset time, and if the time that the two voltage signals are smaller than the threshold value exceeds the preset time, confirming that the whole plant loses power.
In one embodiment, the pressure vessel water level signal threshold is the pressure vessel top.
In one embodiment, before the opening of the control atmosphere release valve, the method further comprises: and adjusting the discharge pressure on the atmospheric release valve to be a preset pressure value so that the cooling temperature on the primary loop is not lower than the steam temperature required by the steam-driven auxiliary water feeding pump on the secondary loop.
In one embodiment, the system further comprises a safety injection tank, the safety injection tank is connected with a main pipeline on a primary circuit through a connecting pipeline, and the preset pressure value is larger than the corresponding pressure value when the boron-containing water in the safety injection tank is exhausted.
In one embodiment, an isolation valve and a check valve are arranged on the connecting pipeline.
In one embodiment, the control atmosphere relief valve is open and comprises: and controlling the opening degree of the atmospheric relief valve.
In one embodiment, the controlling the opening degree of the atmospheric relief valve includes: and automatically adjusting the opening of the atmospheric release valve according to the difference value between the steam pressure value of the secondary side of the steam generator on the two loops and the preset pressure value.
The invention also provides a primary circuit cooling device under the power-off working condition of the whole plant, which comprises:
the first acquisition module is used for acquiring an emergency bus voltage signal;
the first judgment module is used for judging whether the time that the emergency bus voltage signal is smaller than the threshold value exceeds the preset time or not, and if the time exceeds the preset time, determining that the whole plant loses power;
the second acquisition module is used for acquiring a core outlet coolant supercooling degree signal and a pressure vessel water level signal in the primary circuit;
the second judgment module is used for judging whether the supercooling degree signal of the coolant at the reactor core outlet and the water level signal of the pressure vessel are lower than the threshold value or not; if the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit;
and the processing module is used for controlling the opening of the atmospheric release valve.
Drawings
FIG. 1 is a flow chart of a primary circuit cooling under a power loss condition of a plant according to an embodiment of the present invention;
fig. 2 is a schematic diagram of a primary circuit cooling apparatus under a power loss condition of a plant according to an embodiment of the present invention.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in detail below. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. This invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and are not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or intervening elements may also be present. When an element is referred to as being "connected" to another element, it can be directly connected to the other element or intervening elements may also be present. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and the like as used herein are for illustrative purposes only and do not denote a unique embodiment.
As shown in fig. 1, in an embodiment of the present invention, a method for cooling a primary circuit under a power loss condition of a plant is provided, the method includes:
and 150, controlling the opening of the atmospheric release valve.
Adopt above-mentioned technical scheme, can whether take place the coolant loss under the power failure operating mode of whole factory fast judgement, if take place the coolant loss accident, can implement automatic quick cooling to a return circuit through control atmosphere relief valve, and then reduced the possibility that the operator human error takes place, promoted nuclear power plant's safety level.
In some embodiments, the input end of the emergency bus in the present application is connected with an external power supply or a generator, and the output end of the emergency bus is connected with electrical elements in the first loop and the second loop.
Specifically, in order to implement the redundant configuration of the dedicated safety facility, the emergency bus in step 110 of the present application includes two emergency buses a and an emergency bus B which are arranged in parallel, wherein an input end of the emergency bus a is connected with an external power supply or a generator, an output end of the emergency bus a is connected with electrical components in a first loop and a second loop, and the electrical components may be a waste heat discharge pump, a safety injection pump, an electric auxiliary water feed pump, and the like; the input end of the emergency bus B is also connected with an off-plant power supply or a generator, the output end of the emergency bus B is also connected with electrical elements in the first loop and the second loop, and the electrical elements can be a waste heat discharge pump, a safety injection pump, an electric auxiliary water feeding pump and the like;
when the time that the voltage signal of the emergency bus is smaller than the threshold value is judged to exceed the preset time, whether the time that the voltage signal of the emergency bus A is smaller than the threshold value is judged to exceed the preset time, and whether the time that the voltage signal of the emergency bus B is smaller than the threshold value is judged to exceed the preset time, and the power loss of the whole plant can be confirmed only when the time that the voltage signals of the emergency bus A and the emergency bus B are smaller than the threshold values exceeds the preset time.
Further, in the step 120, it is determined whether the time when the emergency bus voltage signal is less than the threshold exceeds a preset time, for example, the following example may be referred to: the voltage of an emergency bus of a typical nuclear power plant is 6.6KV, if the bus voltage monitoring detects that the voltage signal of the emergency bus is lower than 0.8 multiplied by 6.6KV and continuously exceeds 20s, the fact that power supply cannot be carried out on the emergency bus by an off-plant power source and an emergency diesel engine means that power is lost for the emergency bus, and the emergency bus is judged.
In some embodiments, after power loss of the whole plant is confirmed, in order to conveniently judge whether the coolant in the primary loop is lost, the method and the system need to immediately acquire the core outlet coolant supercooling degree signal and the pressure vessel water level signal in the primary loop, and confirm that the coolant loss accident occurs in the primary loop by judging whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold value or not and judging whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold value or not.
Specifically, the pressure vessel water level signal threshold is the top of the pressure vessel, since the pressure vessel water level can reflect the loss degree of the coolant in the pressure vessel, when the pressure vessel water level is lower than the top of the pressure vessel, it means that the pressure vessel is no longer in a full water state, and there is a threat to the cooling of the nuclear fuel in the pressure vessel, thereby confirming that the coolant loss occurs in the primary circuit.
In some embodiments, prior to step 150, i.e., prior to controlling the opening of the atmospheric relief valve, the method further comprises:
and adjusting the discharge pressure on the atmospheric relief valve to be a preset pressure value, so that the cooling temperature on the primary loop is not lower than the steam temperature required by the steam-driven auxiliary water feeding pump on the secondary loop.
Specifically, in order to implement automatic quick cooling to a primary circuit under the condition of shaft seal breach, and can ensure that primary circuit coolant temperature is high enough so that steam generator secondary side produces sufficient steam simultaneously, guarantee the availability of steam-driven auxiliary water feed pump, this application is the discharge pressure on the atmosphere relief valve for preset pressure value (like 2.0MPa), this preset pressure value can ensure that primary circuit refrigerated target temperature can not be too low and lead to steam generator secondary side steam to produce inadequately, and then lead to steam-driven auxiliary water feed pump to lose efficacy (like ordinary steam-driven auxiliary water feed pump requires steam temperature to keep its normal operating above 190 ℃, the saturation temperature that target pressure 2.0MPa corresponds is about 210 ℃, can guarantee steam-driven auxiliary water feed pump's continuous operation).
In some embodiments, still be connected with the safety injection case through connecting line on the trunk line in a return circuit in this application, and be provided with isolation valve and check valve on the connecting line, because the isolation valve of safety injection case will be unable to close because of losing the control power supply under the power failure operating mode of whole factory, in order to avoid the safety injection incasement pressurized nitrogen gas to pour into a return circuit and influence the natural circulation of a return circuit, the aforesaid pressure value that corresponds when the boron-containing water in the safety injection incasement empties is predetermine to the aforesaid.
For example, a typical PWR nuclear power plant has one ampereThe volume of the injection box is about 50m3The inside of the water tank is stored with boron-containing water with a certain concentration (the water volume is about 30-35 m)3) The headspace is covered with nitrogen (nitrogen volume about 15-20 m)3) And pressurizing to about 4.5-4.9 MPa. The safety injection tank starts to inject boron-containing water into the primary circuit when the pressure of the primary circuit is lower than the pressurizing pressure of the primary circuit, and the safety injection tank can be emptied when the pressure of the primary circuit is reduced to be lower than 2.0 MPa. The selected preset pressure value (such as 2.0MPa) can avoid nitrogen injection of the safety injection box.
In some embodiments, controlling the opening of the atmospheric relief valve in step 150 of the present application comprises: the opening degree of the atmospheric relief valve is controlled.
Further, the controlling the opening of the atmospheric relief valve includes automatically adjusting the opening of the atmospheric relief valve according to a difference between a steam pressure value of a secondary side of the steam generator on the two loops and a preset pressure value.
In particular, the atmospheric relief valve is prior art and will not be described in detail herein. At present, the existing atmospheric relief valve mainly has two kinds of opening modes, one kind is the manual control mode, and under this mode, the opening of atmospheric relief valve is by staff manual control, but because staff can't come in the quick response when a return circuit takes place to break the accident for the opening time of atmospheric relief valve is comparatively lagged behind, can't satisfy in time to open the requirement that atmospheric relief valve in time reduced a return circuit pressure. The other mode is a pressure control mode, namely the opening degree of the atmospheric release valve is automatically adjusted according to the difference value between the steam pressure value of the steam generator on the two circuits and a preset pressure value, and the pressure in the two circuits is controlled to be kept at a pressure level corresponding to an internal set value or an external set value by controlling the opening degree of the atmospheric release valve.
When judging that a primary circuit takes place the breach accident, the direct control atmosphere relief valve is opened for steam in the two return circuits can be discharged to the atmosphere fast, takes away the heat in a primary circuit, makes the coolant rapid cooling in a primary circuit, and then a circuit pressure also descends fast, and steam generator secondary side produces sufficient steam simultaneously, guarantees the availability of steam-driven supplementary feed water pump, compensates the loss of a circuit coolant, and then reduces the naked risk of reactor core.
As shown in fig. 2, the present invention further provides a primary circuit cooling device 200 under a power loss condition of a whole plant, the device comprising:
a first obtaining module 210, configured to obtain an emergency bus voltage signal;
the first judging module 220 is configured to judge whether the time that the emergency bus voltage signal is less than the threshold exceeds a preset time, and if the time exceeds the preset time, determine that the power loss of the whole plant occurs;
a second obtaining module 230, configured to obtain a core outlet coolant supercooling degree signal and a pressure vessel water level signal in the primary loop;
a second judging module 240, configured to judge whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than a threshold value; if the supercooling degree signal of the coolant at the reactor core outlet and the water level signal of the pressure vessel are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit;
and a processing module 250 for controlling the opening of the atmospheric release valve.
Specifically, when the emergency bus voltage signal acquired by the first acquiring module 210 is judged by the first judging module 220 whether the time that the emergency bus voltage signal is less than the threshold value exceeds the preset time, and if the time exceeds the preset time, the power loss of the whole plant is confirmed, at this time, the core outlet coolant supercooling degree signal and the pressure vessel water level signal in the primary loop need to be acquired by the second acquiring module 230, and whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold value is judged by the second judging module 240; if the supercooling degree signal of the coolant at the reactor core outlet and the water level signal of the pressure vessel are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit;
when judging that a primary circuit takes place the breach accident, processing module 250 direct control atmosphere relief valve opens for steam in the two return circuits can be discharged to the atmosphere fast, takes away the heat in the primary circuit, makes the coolant rapid cooling in the primary circuit, and then the primary circuit pressure also descends fast, and steam generator secondary side produces sufficient steam this moment, guarantees the availability of steam-driven supplementary water-feeding pump, compensates the loss of a primary circuit coolant, and then reduces the naked risk of reactor core.
The technical features of the embodiments described above may be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the embodiments described above are not described, but should be considered as being within the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A primary circuit cooling method under the power-loss working condition of a whole plant is characterized by comprising the following steps:
acquiring an emergency bus voltage signal, judging whether the time that the emergency bus voltage signal is less than a threshold value exceeds preset time, if so, confirming power loss of the whole plant, and meanwhile, confirming power loss of the whole plant
Obtaining a core outlet coolant supercooling degree signal and a pressure vessel water level signal in a primary circuit, and judging whether the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than a threshold value;
and if the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit and controlling an atmospheric release valve to open.
2. The primary circuit cooling method under the power loss condition of the whole plant as claimed in claim 1, wherein the input end of the emergency bus is connected with an external power supply or a generator, and the output end of the emergency bus is connected with electrical elements in the primary circuit and the secondary circuit.
3. The primary circuit cooling method under the power-loss working condition of the whole plant according to claim 1 or 2, wherein the step of obtaining the emergency bus voltage signal and judging whether the time that the emergency bus voltage signal is smaller than the threshold value exceeds a preset time comprises the following steps:
the method comprises the steps of obtaining two voltage signals corresponding to at least two emergency buses arranged in parallel, judging whether the time that the two voltage signals are smaller than a threshold value exceeds preset time, and if the time that the two voltage signals are smaller than the threshold value exceeds the preset time, confirming that the whole plant loses power.
4. The primary loop cooling method under the plant power loss condition of claim 1, wherein the pressure vessel water level signal threshold is a pressure vessel top.
5. The primary loop cooling method under a plant loss of power condition of claim 1, wherein before the opening of the atmospheric release valve, the method further comprises:
and adjusting the discharge pressure on the atmospheric release valve to be a preset pressure value so that the cooling temperature on the primary loop is not lower than the steam temperature required by the steam-driven auxiliary water feeding pump on the secondary loop.
6. The primary circuit cooling method under the power-loss working condition of the whole plant according to claim 5, further comprising a safety injection tank, wherein the safety injection tank is connected with a main pipeline on the primary circuit through a connecting pipeline, and the preset pressure value is larger than a corresponding pressure value when boron-containing water in the safety injection tank is exhausted.
7. The primary loop cooling method under the power loss condition of the whole plant as claimed in claim 6, wherein an isolation valve and a check valve are arranged on the connecting pipeline.
8. The primary loop cooling method under the plant power loss condition of claim 5, wherein the controlling the opening of the atmospheric relief valve comprises:
and controlling the opening degree of the atmospheric relief valve.
9. The primary loop cooling method under the power loss condition of the whole plant as claimed in claim 8, wherein the controlling of the opening degree of the atmospheric release valve comprises:
and automatically adjusting the opening of the atmospheric release valve according to the difference value between the steam pressure value of the secondary side of the steam generator on the two loops and the preset pressure value.
10. A primary circuit cooling apparatus for a plant under power loss conditions, said apparatus comprising:
the first acquisition module is used for acquiring an emergency bus voltage signal;
the first judgment module is used for judging whether the time that the emergency bus voltage signal is smaller than the threshold value exceeds the preset time or not, and if the time exceeds the preset time, determining that the whole plant loses power;
the second acquisition module is used for acquiring a core outlet coolant supercooling degree signal and a pressure vessel water level signal in the primary circuit;
the second judgment module is used for judging whether the supercooling degree signal of the coolant at the reactor core outlet and the water level signal of the pressure vessel are lower than the threshold value or not; if the core outlet coolant supercooling degree signal and the pressure vessel water level signal are lower than the threshold values, confirming that a coolant loss accident occurs in a primary circuit;
and the processing module is used for controlling the opening of the atmospheric release valve.
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| CN113421662A (en) * | 2021-06-18 | 2021-09-21 | 中国核动力研究设计院 | Natural circulation cooling method under failure of liquid level indication of pressure vessel of nuclear power plant |
| CN113593739A (en) * | 2021-07-22 | 2021-11-02 | 中国核动力研究设计院 | Control method for dealing with water supply flow loss accident of nuclear power plant |
| CN113746196A (en) * | 2021-09-02 | 2021-12-03 | 苏州热工研究院有限公司 | Nuclear power plant emergency power supply control system and method |
| CN113963822A (en) * | 2021-09-29 | 2022-01-21 | 深圳中广核工程设计有限公司 | Loop radioactive anomaly monitoring method and device, storage medium and electronic equipment |
| CN113972016A (en) * | 2021-10-26 | 2022-01-25 | 中国核动力研究设计院 | Method, device, equipment and medium for coping loss of coolant accident outside containment of nuclear power plant |
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