CN112687410A - Diagnosis method for large-range damage accident of passive pressurized water reactor nuclear power plant - Google Patents
Diagnosis method for large-range damage accident of passive pressurized water reactor nuclear power plant Download PDFInfo
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- CN112687410A CN112687410A CN202110104593.6A CN202110104593A CN112687410A CN 112687410 A CN112687410 A CN 112687410A CN 202110104593 A CN202110104593 A CN 202110104593A CN 112687410 A CN112687410 A CN 112687410A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 28
- 238000000034 method Methods 0.000 title claims abstract description 19
- 238000003745 diagnosis Methods 0.000 title claims description 5
- 238000012806 monitoring device Methods 0.000 claims abstract description 97
- 230000002159 abnormal effect Effects 0.000 claims abstract description 69
- 238000012544 monitoring process Methods 0.000 claims abstract description 9
- 230000005855 radiation Effects 0.000 claims description 7
- 239000007788 liquid Substances 0.000 claims description 6
- 230000000116 mitigating effect Effects 0.000 claims description 4
- 238000012423 maintenance Methods 0.000 description 18
- 230000001960 triggered effect Effects 0.000 description 3
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 239000003381 stabilizer Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a method for diagnosing a large-range damage accident of a passive pressurized water reactor nuclear power plant, which comprises the following steps: be provided with first monitoring devices and second monitoring devices in the power plant, first monitoring devices monitors first data and/or second data, and second monitoring devices monitors first data and/or second data, and first data and second data all correspond to the first abnormal state of power plant, judge whether the state of power plant is in first abnormal state according to first data or second data. Set up first monitoring devices and second monitoring devices simultaneously in the power plant to place first monitoring devices and second monitoring devices respectively in the power plant different positions, take place to destroy after the power plant suffered a disaster, the probability that first monitoring devices and second monitoring devices took place to destroy simultaneously is very low, thereby helps being in the judgement of first abnormal state to the power plant, greatly reduces the power plant and lacks the probability that corresponding monitoring data can't be judged the power plant state after receiving the disaster.
Description
Technical Field
The invention relates to a diagnosis method for a large-range damage accident of a passive pressurized water reactor nuclear power plant, and belongs to the field of safety analysis of the nuclear power plant.
Background
Large area failures of nuclear power plant equipment may be caused under the action of extreme disasters (such as fire or terrorist attacks), especially if the monitoring and control capabilities of the power plant are damaged, which may make the existing power plant regulation system difficult to implement effectively. Although the ability of passive pressurized water reactor nuclear power plant reply accident is stronger than traditional nuclear power plant, nevertheless to damaging the operating mode on a large scale and not fully carrying out the scheme, there is corresponding risk, in case the control room takes place to destroy, can lead to the power plant to be in the data monitoring blind area equally.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provide a method for diagnosing a large-range damage accident of a passive pressurized water reactor nuclear power plant, so as to reduce the probability that the power plant is in a data monitoring blind area after the passive pressurized water reactor nuclear power plant suffers from a disaster.
The technical scheme adopted by the invention is as follows:
a diagnosis method for large-scale damage accidents of a passive pressurized water reactor nuclear power plant comprises the following steps: be provided with first monitoring devices and second monitoring devices in the power plant, first monitoring devices monitors first data and/or second data, and second monitoring devices monitors first data and/or second data, and first data and second data all correspond to the first abnormal state of power plant, judge whether the state of power plant is in first abnormal state according to first data or second data.
The invention has the beneficial effects that:
the first monitoring device and the second monitoring device are respectively used for monitoring first data, second data, third data, fourth data, wherein one of the first data and the second data is monitored at the same time, and the other one of the first data and the second data is monitored at the same time. If only set up first monitoring devices or second monitoring devices alone, then the power plant takes place the damage back, very probably the first monitoring devices or second monitoring devices also take place the damage together, and whether maintenance personal is in first abnormal state in the power plant just can't learn first data and second data with probably after getting into the power plant, so the nothing is followed and is judged the power plant. And set up first monitoring devices and second monitoring devices simultaneously in the power plant, and place first monitoring devices and second monitoring devices respectively in the power plant different positions, the power plant takes place the damage after suffering a disaster, the probability that first monitoring devices and second monitoring devices take place the damage simultaneously is very low, maintenance personal can learn one of them data in first data and the second data at least after getting into the power plant by the probability, thereby help being in the judgement of first abnormal state to the power plant, greatly reduce the power plant and lack the probability that corresponding monitoring data can't be judged the power plant state after suffering a disaster. The first data and the second data are used as a group of data, and as long as one of the first data and the second data is abnormal, the state of the power plant is indicated to be in a first abnormal state, so that maintenance personnel can perform corresponding relieving measures according to an instruction manual aiming at the first abnormal state.
The first monitoring device comprises a first instrument and a first control box, the first control box is electrically connected with the first instrument through cabinet disconnection, the second monitoring device comprises a second instrument and a second control box, and the second control box is electrically connected with the second instrument through cabinet disconnection.
The first monitoring device is a mobile monitoring device.
The first monitoring device and the second monitoring device are matched to monitor the first data and the second data, and when the first data or the second data trigger a corresponding warning value, the first abnormal state is relieved.
According to the invention, when the first data is pressure, temperature or radiation quantity, the alarm value of the first data is lower than a critical value, when the first data is liquid level, the alarm value of the first data is higher than the critical value, when the second data is pressure, temperature or radiation quantity, the alarm value of the second data is lower than the critical value, and when the second data is liquid level, the alarm value of the second data is higher than the critical value.
The power plant is also provided with a third monitoring device and a fourth monitoring device, the third monitoring device and the fourth monitoring device are matched to monitor third data and fourth data, the third data and the fourth data correspond to a second abnormal state of the power plant, and whether the power plant state is in the second abnormal state or not is judged according to the third data or the fourth data.
When the third data or the fourth data triggers the corresponding warning value, the relieving operation is carried out aiming at the second abnormal state.
When the plant is in the first abnormal state and the second abnormal state at the same time, the relieving operation for the first abnormal state is prior to or subsequent to the relieving operation for the second abnormal state.
According to the method, when the first data, the second data, the third data and the fourth data cannot be obtained, the power plant is treated in a disconnected mode.
According to the invention, the first abnormal state has a corresponding first setting time, and the first abnormal state is relieved within the first setting time after the first abnormal state starts.
Additional features and advantages of the invention will be set forth in the detailed description which follows.
Detailed Description
The technical solutions of the embodiments of the present invention are explained and illustrated below with reference to the embodiments of the present invention, but the following embodiments are only preferred embodiments of the present invention, and not all embodiments. Based on the embodiments in the implementation, other embodiments obtained by those skilled in the art without any creative effort belong to the protection scope of the present invention.
In the following description, the appearances of the indicating orientation or positional relationship such as the terms "inner", "outer", "upper", "lower", "left", "right", etc. are only for convenience in describing the embodiments and for simplicity in description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and are not to be construed as limiting the present invention.
Example 1:
the embodiment provides a method for diagnosing a large-scale damage accident of a passive pressurized water reactor nuclear power plant, which comprises the following steps: a first monitoring device, a second monitoring device, a third monitoring device and a fourth monitoring device are arranged in the power plant. The first monitoring device monitors the first data and the second data simultaneously, the second monitoring device also monitors the first data and the second data simultaneously, the third monitoring device monitors the third data and the fourth data simultaneously, and the fourth monitoring device also monitors the third data and the fourth data simultaneously. The first data and the second data correspond to a first abnormal state of the power plant, the third data and the fourth data correspond to a second abnormal state of the power plant, the power plant is indicated to be in the first abnormal state as long as one of the first data and the second data triggers an alarm value, and the power plant is indicated to be in the second abnormal state as long as one of the third data and the fourth data triggers the alarm value. And only under the condition that the first data, the second data, the third data and the fourth data simultaneously meet the normal numerical value, the power plant is probably in a more normal and controllable state.
More specifically, the first abnormal state is a loop water shortage, and the second abnormal state is a containment water shortage. Correspondingly, the first data is the pressure in the containment, the second data is the water level of the voltage stabilizer, the third data is the outlet temperature of the reactor core, and the fourth data is the radiation rate in the containment. In this embodiment, the alarm value of the first data is 34kpa, the alarm value of the second data is 10% of the initial liquid level, the alarm value of the third data is 650 ℃, and the alarm value of the fourth data is 1 Gy/h. Therefore, the judgment of the first abnormal state and the judgment of the second abnormal state are independent from each other, and mutual interference is avoided.
Once the power plant is in the first abnormal state and/or the second abnormal state, corresponding relieving measures need to be taken to reduce the influence of the first abnormal state and/or the second abnormal state on the operation of the power plant, for example, when the power plant is in the first abnormal state, water is injected into a loop to reduce the pressure in a containment vessel, and simultaneously, the water level of a voltage stabilizer is raised, and when the power plant is in the second abnormal state, water is injected into the containment vessel to reduce the outlet temperature of a reactor core and the radiation quantity in the containment vessel.
The first data, the second data, the third data and the fourth data have respective critical values. In this embodiment, the warning value is an abnormal data value corresponding to the alarm triggered to give an alarm, and the critical value is an abnormal data value corresponding to the power plant which is about to be out of maintenance. The alarm value of the first data is lower than the critical value, namely the critical value of the first data is greater than 34kpa, the alarm value of the second data is higher than the critical value, namely the critical value of the second data is less than 10% of the initial liquid level, the alarm value of the third data is lower than the critical value, namely the critical value of the third data is greater than 650 ℃, and the alarm value of the fourth data is lower than the critical value, namely the critical value of the fourth data is greater than 1 Gy/h.
Taking the first data as an example, if the pressure in the containment vessel gradually increases, the warning value is triggered before the critical value is triggered, and at the moment, the loop is filled with water in time, so that sufficient time for relieving measures can be provided for maintenance personnel, and the pressure in the containment vessel is prevented from increasing to the critical value. The second data, the third data, and the fourth data are the same, and are not described again in this embodiment.
The first monitoring device and the third monitoring device are located in a main control room, and the second monitoring device and the fourth monitoring device are located in an emergency command center in a power plant. After the power plant is in a disaster, the main control room and the emergency command center have low probability of damage at the same time, if the main control room is damaged, the first monitoring device cannot monitor the first data and the second data, the third monitoring device cannot monitor the third data and the fourth data, but the second monitoring device and the fourth monitoring device in the emergency command center still have high probability of being remained in the disaster, the second monitoring device continues to monitor the first data and the second data, the fourth monitoring device continues to monitor the third data and the fourth data, and maintenance personnel can go to the emergency command center to obtain the first data, the second data, the third data and the fourth data, thereby evaluating and diagnosing the post-disaster condition of the power plant, and greatly reducing data monitoring dead zones in the maintenance process. Even if the second monitoring device and the fourth monitoring device are partially damaged, maintenance personnel can also perform a brief judgment on the post-disaster condition of the power plant as long as the maintenance personnel can acquire a part of data in the first data, the second data, the third data and the fourth data, so that the probability of taking measures for the power plant to break is effectively reduced.
Preferably, a fifth monitoring device and a sixth monitoring device can be further arranged in the technical support center of the power plant, the fifth monitoring device monitors the first data and the second data, and the sixth monitoring device monitors the third data and the fourth data, so that the probability that maintenance personnel cannot monitor the first data, the second data, the third data and the fourth data after a disaster is further reduced.
The maintenance efficiency of maintenance personnel is limited, the water inflow of the power plant is limited, and if the post-disaster power plant is in a first abnormal state and a second abnormal state at the same time, the relieving operation of the first abnormal state is prior to or subsequent to the relieving operation of the second abnormal state according to the severity of the abnormal state. For example, under the condition that the pressure in the containment vessel is extremely high after a disaster and the temperature of the outlet of the reactor core is not serious, the first abnormal state is relieved. And under the condition that the radiation rate in the containment vessel exceeds the standard seriously and the pressure in the containment vessel does not exceed the standard seriously, the relieving operation is firstly carried out on the second abnormal state, and then the relieving operation is carried out on the first abnormal state.
Additionally, when the power plant is in a severe disaster situation, the first monitoring device, the second monitoring device, the third monitoring device and the fourth monitoring device are all damaged, and the corresponding first data, the corresponding second data, the corresponding third data and the corresponding fourth data cannot be acquired, the maintenance personnel still need to perform the emergency treatment on the power plant.
Example 2:
the difference between this embodiment and embodiment 1 is that the first monitoring device and the second monitoring device are respectively placed in the main control room and the remote shutdown station, and the third monitoring device and the fourth monitoring device are respectively placed in the technical support center and the emergency command center. The first abnormal state has a corresponding first setting time and the second abnormal state has a corresponding second setting time.
If the main control room and the remote shutdown station are damaged after the disaster, the first monitoring device and the second monitoring device cannot monitor the first data and the second data, but the technical support center and the emergency command center are intact, and the third monitoring device and the fourth monitoring device can still monitor the third data and the fourth data, so that the power plant is not required to be treated in a breaking way. However, since it cannot be determined whether the power plant is in the first abnormal state according to the first data and the second data, the power plant is determined to be in the first abnormal state, and therefore, a maintenance worker needs to complete the mitigation operation on the first abnormal state within the first setting time after starting maintenance.
Similarly, if the main control room and the remote shutdown station are intact after the disaster and the technical support center and the emergency command center are damaged, the first data and the second data can be monitored, the third data and the fourth data cannot be monitored, the power plant is in a second abnormal state by default, and the maintenance personnel need to complete the relieving operation of the second abnormal state within a second setting time after starting maintenance.
For example, water injection into the containment vessel within 160 minutes can ensure that the core outlet temperature is not higher than 650 ℃, and the corresponding second setting time is 160 minutes.
Example 3:
the difference between this embodiment and embodiment 1 lies in that first monitoring devices and second monitoring devices are located the master control room simultaneously, and first monitoring devices includes first instrument and first control box, and first control box and first instrument are through cabinet off-line electrical connection, and second monitoring devices includes second instrument and second control box, and second control box and second instrument are through cabinet off-line electrical connection. After a disaster, the main control chamber is partially damaged, and although the first instrument, the second control box and the second instrument are intact, the first control box is damaged. At the moment, the first instrument and the first control box can be disconnected, then the first instrument and the second control box are electrically connected through cabinet disconnection, and the first instrument and the second instrument are simultaneously controlled by the second control box to monitor the first data and the second data.
Example 4:
the difference between this embodiment and embodiment 1 is that the first monitoring device is a mobile monitoring device, and a maintenance person can drive the first monitoring device to move in the power plant to obtain the first data and the second data.
Example 5:
in this embodiment, the first monitoring device and the second monitoring device both monitor only the first data, and the third monitoring device and the fourth monitoring device monitor only the third data. If the first data is abnormal, the power plant is in a first abnormal state, and similarly, if the third data is abnormal, the power plant is in a second abnormal state. However, when the first data and the third data are normal, whether the power plant is in a normal state or not cannot be effectively judged, and the judgment precision is lower than that of monitoring the first data, the second data, the third data and the fourth data simultaneously in embodiment 1.
While the invention has been described with reference to specific embodiments thereof, it will be understood by those skilled in the art that the invention is not limited thereto but is intended to cover all modifications and equivalents as may be included within the spirit and scope of the invention. Any modification which does not depart from the functional and structural principles of the present invention is intended to be included within the scope of the claims.
Claims (10)
1. A diagnosis method for a large-range damage accident of a passive pressurized water reactor nuclear power plant is characterized by comprising the following steps: be provided with first monitoring devices and second monitoring devices in the power plant, first monitoring devices monitors first data and/or second data, and second monitoring devices monitors first data and/or second data, and first data and second data all correspond to the first abnormal state of power plant, judge whether the state of power plant is in first abnormal state according to first data or second data.
2. The method for diagnosing the large-scale damage accident of the passive pressurized water reactor nuclear power plant according to claim 1, wherein the first monitoring device comprises a first instrument and a first control box, the first control box is electrically connected with the first instrument through cabinet disconnection, the second monitoring device comprises a second instrument and a second control box, and the second control box is electrically connected with the second instrument through cabinet disconnection.
3. The method for diagnosing the wide-range damage accident of the passive pressurized water reactor nuclear power plant according to claim 1, wherein the first monitoring device is a mobile monitoring device.
4. The method for diagnosing the wide-range damage accident of the passive pressurized water reactor nuclear power plant according to claim 1, wherein the first monitoring device and the second monitoring device are used for monitoring the first data and the second data in a matched mode, and when the first data or the second data triggers a corresponding warning value, the first abnormal state is relieved.
5. The method for diagnosing the wide-range damage accident of the passive pressurized water reactor nuclear power plant according to claim 4, wherein when the first data is pressure, temperature or radiation amount, the alarm value of the first data is lower than a critical value, when the first data is liquid level, the alarm value of the first data is higher than the critical value, when the second data is pressure, temperature or radiation amount, the alarm value of the second data is lower than the critical value, and when the second data is liquid level, the alarm value of the second data is higher than the critical value.
6. The method for diagnosing the large-scale damage accident of the passive pressurized water reactor nuclear power plant as claimed in claim 4, wherein a third monitoring device and a fourth monitoring device are further arranged in the power plant, the third monitoring device and the fourth monitoring device are matched to monitor third data and fourth data, the third data and the fourth data correspond to a second abnormal state of the power plant, and whether the power plant state is in the second abnormal state is judged according to the third data or the fourth data.
7. The method for diagnosing the large-scale damage accident of the passive pressurized water reactor nuclear power plant according to claim 6, wherein when the third data or the fourth data triggers a corresponding warning value, a mitigation operation is performed for the second abnormal state.
8. The method for diagnosing the broad damage accident of the passive pressurized water reactor nuclear power plant according to claim 7, wherein when the plant is in the first abnormal state and the second abnormal state at the same time, the mitigation operation for the first abnormal state is performed before or after the mitigation operation for the second abnormal state.
9. The method for diagnosing the wide-range damage accident of the passive pressurized water reactor nuclear power plant according to claim 6, wherein when the first data, the second data, the third data and the fourth data are all unavailable, the power plant is treated in an outage mode.
10. The method for diagnosing the wide-range damage accident of the passive pressurized water reactor nuclear power plant according to claim 4, wherein the first abnormal state has a corresponding first setting time, and the first abnormal state is relieved after the first abnormal state is started within the first setting time.
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Application publication date: 20210420 |