CN102496393A - System for monitoring pressure vessel of reactor of nuclear power station and method thereof - Google Patents
System for monitoring pressure vessel of reactor of nuclear power station and method thereof Download PDFInfo
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- CN102496393A CN102496393A CN201110367565XA CN201110367565A CN102496393A CN 102496393 A CN102496393 A CN 102496393A CN 201110367565X A CN201110367565X A CN 201110367565XA CN 201110367565 A CN201110367565 A CN 201110367565A CN 102496393 A CN102496393 A CN 102496393A
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Abstract
The invention relates to the technical field of nuclear power and discloses a system for monitoring a pressure vessel of a reactor of a nuclear power station and a method thereof. The monitoring system contains a monitoring terminal which is disposed at the monitoring point of the monitored pressure vessel of the reactor and is used to acquire and send temperature information of the pressure vessel of the reactor; and a monitoring device which is electrically connected with the monitoring terminal and is used to receive the temperature information sent from the monitoring terminal and monitor the state of the pressure vessel of the reactor according to the temperature information. According to the invention, as there is no need to contact high temperature melts, the cost of the monitoring terminal can be reduced, its installation position is easy to determine and the acquired temperature information is effective and reliable. Based on the temperature information, the state of the pressure vessel of the reactor can be effectively monitored. The system for monitoring the pressure vessel of the reactor of the nuclear power station has a simple structure and requires low cost. The monitoring method provided by the invention is convenient to carry out and has high accuracy.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a monitoring system and a monitoring method for a reactor pressure vessel of a nuclear power station.
Background
A Reactor Pressure Vessel (RPV) is a cylindrical vessel in a pressurized water nuclear reactor that includes the core of the nuclear reactor and is vertically disposed in a reactor cavity. The pressurized water normally cools the core, and the temperature of the core and thus the reactor pressure vessel fluctuates to a small extent. However, after a severe accident (e.g., an unexpected cessation of core cooling) the reactor core may melt and further cause the reactor pressure vessel to melt through with serious consequences.
Due to the lack of a corresponding means for monitoring a reactor pressure vessel in a nuclear power station accident of the Japanese Fudao, the effectiveness of external water injection after the accident happens cannot be accurately evaluated, and the state monitoring and control after the accident are influenced. At present, stricter requirements are provided for monitoring after serious accidents of nuclear power stations and monitoring operation states. The monitoring of the state (temperature monitoring) and the determination of the integrity of a reactor pressure vessel, which is one of the important devices in a nuclear reactor circuit, are of great importance. In the prior art, a domestic nuclear power unit basically has no means for monitoring the state and integrity of a reactor pressure vessel; foreign nuclear power plants detect the melt by arranging a thermocouple at the bottom of the reactor cavity (fig. 1), and judge whether the reactor pressure vessel is melted through by judging whether the melt falls into the reactor cavity. The disadvantages of this solution are: (1) the temperature of the melt is very high, so a thermocouple for detecting the melt needs to be capable of bearing extremely high temperature and has higher cost; (2) the position where the melt falls into the reactor cavity is difficult to determine, and therefore the installation position of the thermocouple is difficult to determine; (3) the extremely high temperature melt can cause structural damage to the thermocouple; (4) the high-temperature signal detected by the thermocouple is an instantaneous signal, and the validity of the measurement signal is difficult to judge.
Disclosure of Invention
The invention aims to solve the technical problems that in the prior art, the thermocouple cost is high, the installation position is difficult to determine, the risk of structural damage exists, and the validity of a measurement signal is difficult to judge when a reactor is melted through by the thermocouple at the bottom of a reactor cavity, and provides a monitoring system and a monitoring method for a nuclear power station reactor pressure vessel, which have low requirement on the thermocouple, easy determination of the installation position and high validity of the measurement signal.
The technical problem to be solved by the invention is realized by the following technical scheme: there is provided a monitoring system for a nuclear power plant reactor pressure vessel, wherein the monitoring system comprises:
the monitoring terminal is arranged at a monitoring point of the monitored reactor pressure vessel and is used for acquiring and transmitting the temperature information of the reactor pressure vessel;
and the monitoring device is electrically connected with the monitoring terminal and is used for receiving the temperature information sent by the monitoring terminal and monitoring the state of the reactor pressure vessel according to the temperature information.
In the monitoring system of the reactor pressure vessel of the nuclear power station, the distance between the monitoring terminal and the reactor pressure vessel is 1-3 cm.
In the monitoring system for the reactor pressure vessel of the nuclear power station, the monitoring system is provided with a plurality of monitoring terminals, and before the monitoring device monitors the state of the reactor pressure vessel, the monitoring device also corrects the received temperature information:
calculating average temperature information according to the received temperature information;
calculating a relative deviation of the received temperature information from the average temperature information;
judging whether the relative deviation exceeds a preset deviation threshold value in the monitoring device or not; wherein:
if the relative deviation exceeds the deviation threshold, correcting the received temperature information and generating corrected temperature information; otherwise, monitoring the state of the reactor pressure vessel according to the received temperature information.
In the monitoring system for the reactor pressure vessel of the nuclear power station, the plurality of monitoring terminals are arranged around the reactor pressure vessel at the same height and at equal intervals.
In the monitoring system for a reactor pressure vessel of a nuclear power plant, the monitoring device for monitoring the state of the reactor pressure vessel includes:
the received temperature information or corrected temperature information is displayed, and from this historical operating conditions for analyzing the state development trend of the reactor pressure vessel are generated and output.
In the monitoring system for a reactor pressure vessel of a nuclear power plant, the monitoring device for monitoring the state of the reactor pressure vessel includes:
judging whether the temperature information of the reactor pressure vessel exceeds a preset temperature threshold value in the monitoring device or not according to the received temperature or corrected temperature information; wherein,
if the received temperature information or the corrected temperature information exceeds the temperature threshold, judging that the reactor pressure vessel is melted through; otherwise, the reactor pressure vessel is not melted through.
In the monitoring system of the reactor pressure vessel of the nuclear power station, when the reactor pressure vessel is judged to be melted through, the monitoring device gives out a high-temperature alarm.
According to another aspect of the present invention, there is provided a method of monitoring a nuclear power plant reactor pressure vessel, wherein the method comprises the steps of:
s1: the monitoring terminal arranged at the monitoring point of the reactor pressure vessel acquires the temperature information of the monitored reactor pressure vessel and sends the acquired temperature information to the monitoring device;
s2: the monitoring device receives the temperature information sent by the monitoring terminal and monitors the state of the reactor pressure vessel according to the temperature information. In the monitoring method for the reactor pressure vessel of the nuclear power station, in the step S1, the distance between the monitoring terminal and the reactor pressure vessel is 1-3 cm.
In the method for monitoring a reactor pressure vessel of a nuclear power plant, the monitoring system is provided with a plurality of monitoring terminals, and in step S2, before the monitoring device monitors the state of the reactor pressure vessel, the monitoring device further corrects the received temperature information:
calculating average temperature information according to the received temperature information;
calculating a relative deviation of the received temperature information from the average temperature information;
judging whether the relative deviation exceeds a preset deviation threshold value in the monitoring device or not; wherein:
if the relative deviation exceeds the deviation threshold, correcting the received temperature information and generating corrected temperature information; otherwise, monitoring the state of the reactor pressure vessel according to the received temperature information.
In the monitoring method for the reactor pressure vessel of the nuclear power station, the plurality of monitoring terminals are equidistantly arranged around the reactor pressure vessel at the same height.
In the method for monitoring a reactor pressure vessel of a nuclear power plant, in step S2, the monitoring device for monitoring a state of the reactor pressure vessel includes:
the received temperature information or corrected temperature information is displayed, and from this historical operating conditions for analyzing the state development trend of the reactor pressure vessel are generated and output.
In the method for monitoring a reactor pressure vessel of a nuclear power plant, in step S2, the monitoring device for monitoring a state of the reactor pressure vessel includes:
judging whether the temperature information of the reactor pressure vessel exceeds a preset temperature threshold value in the monitoring device or not according to the received temperature or corrected temperature information; wherein,
if the received temperature information or the corrected temperature information exceeds the temperature threshold value, judging that the reactor pressure vessel is melted through; otherwise, the reactor pressure vessel is not melted through.
In the method for monitoring the reactor pressure vessel of the nuclear power plant, in step S2, when it is determined that the reactor pressure vessel is melted through, the monitoring device issues a high temperature alarm.
The monitoring system and the method for the reactor pressure vessel of the nuclear power station can obtain the following beneficial effects: (1) the monitoring terminal indirectly acquires the temperature information of the reactor pressure vessel and does not need to directly contact the extremely high-temperature melt, so that the requirement on the high temperature resistance of the monitoring terminal is obviously reduced; meanwhile, the monitoring terminal continuously acquires temperature information, and does not need to complete acquisition and data processing in a very short time, so that the requirement on the response time of the monitoring terminal is reduced; the cost control is facilitated after the overall requirement on the monitoring terminal is reduced; (2) the installation position of the monitoring terminal is easy to determine, and accurate temperature measurement can be realized only by arranging the monitoring terminal at a monitoring point; (3) the collected temperature information is a continuous signal, and the signal effectiveness is improved; (4) the monitoring device is used for monitoring the state of the reactor pressure vessel according to the temperature information with high effectiveness, and has important significance for safety control of the nuclear power station. The monitoring system for the nuclear power station reactor pressure vessel has the advantages of simple structure and low cost, and the monitoring method is convenient to implement and high in accuracy.
Drawings
The invention will be described in further detail below with reference to the accompanying drawings and specific embodiments. In the drawings:
FIG. 1 is a schematic diagram of a monitoring terminal installed in a reactor pressure vessel for collecting temperature information in the prior art;
FIG. 2 is a schematic illustration of the installation of a monitoring terminal in collecting temperature information of a reactor pressure vessel according to the present invention;
FIG. 3 is a schematic diagram of a monitoring system for a nuclear power plant reactor pressure vessel according to the present invention;
FIG. 4 is a schematic view of another monitoring system for a nuclear power plant reactor pressure vessel according to the present invention;
fig. 5 is a schematic diagram of a method of monitoring a nuclear power plant reactor pressure vessel in accordance with the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
The invention provides a monitoring system of a reactor pressure vessel of a nuclear power station, which can be used for acquiring temperature information of the reactor pressure vessel at any time by a monitoring terminal arranged at a monitoring point of the reactor pressure vessel and monitoring the state of the reactor pressure vessel by a monitoring device.
Fig. 3 is a schematic diagram of a monitoring system 100 for a nuclear power plant reactor pressure vessel according to the present invention. As shown in fig. 2 and 3, a monitoring system 100 for a nuclear power plant reactor pressure vessel includes a monitoring device 110 and a monitoring terminal(s) 120. The monitoring terminal 120 is disposed in a containment in the reactor cavity and electrically connected to the monitoring device 110 outside the containment, and the monitoring terminal 120 is installed near an outer wall of the reactor pressure vessel.
The monitoring terminal 120 is used for collecting temperature information of the reactor pressure vessel and sending the temperature information to the monitoring device 110. Because the requirement on the thermocouple is high after a serious accident of the nuclear power station, the K-type armored thermocouple is selected as the monitoring terminal 120 to collect corresponding temperature information. As known to those skilled in the art, the thermocouple may generate an electromotive force signal according to a temperature difference between the working end and the free end, and the monitoring device 110 may receive the electromotive force signal and convert the electromotive force signal into corresponding temperature information.
Referring to fig. 2, fig. 2 is a schematic diagram illustrating an installation of the monitoring terminal 120 (using a thermocouple in the present invention) for collecting temperature information of the reactor pressure vessel in the present invention. Specifically, the collected temperature information of the reactor pressure vessel is reflected by the temperature information of the outer wall thereof. In order to enable the acquired temperature information to truly reflect the temperature information of the reactor pressure vessel, the thermocouple is arranged close to the reactor pressure vessel. In other words, the monitoring points are placed near the reactor pressure vessel to ensure good implementation. It should be understood that the term "monitoring point" as used herein refers to a spatial location at a distance from the reactor pressure vessel from which temperature information of the outer wall of the reactor pressure vessel can be collected; the thermocouple can effectively acquire the temperature information of the reactor pressure vessel when being arranged at the position. In the invention, the distance between the monitoring point and the reactor pressure vessel, particularly the distance between the monitoring point and the outer wall of the reactor pressure vessel is preferably 1-3 cm. In the specific implementation process, the thermocouple is fixedly installed on the containment close to the reactor pressure vessel, and the working end of the thermocouple is located at the monitoring point, so that the thermocouple can accurately acquire the temperature information of the reactor pressure vessel. In addition, as understood by those skilled in the art, since the reactor pressure vessel is a cylindrical structure (a containment vessel is arranged outside the reactor pressure vessel) which is generally vertically installed in the reactor cavity, and the lower head of the reactor pressure vessel is a circular arc structure as shown in the figure, high-temperature melt inside the reactor pressure vessel is generally gathered at the bottom of the reactor pressure vessel, namely the lower head of the reactor pressure vessel. To this end, the present invention preferably places monitoring points near the lower head of the reactor pressure vessel to enable more accurate temperature information acquisition.
When the monitoring system provided by the invention is provided with a plurality of monitoring terminals, the plurality of monitoring terminals are correspondingly arranged at a plurality of monitoring points. In connection with the above description, it is particularly proposed that the monitoring points in this case have to be set at the same height around the reactor pressure vessel, so that thermocouples arranged at the monitoring points can collect equal temperature information. The setting is specifically expressed as follows: when the monitoring points are arranged on the circumference of the same height with the axis point of the reactor pressure vessel as the circle center, the thermocouples arranged at the monitoring points are arranged at equal intervals on the outer wall of the reactor pressure vessel, and the theoretical temperature information collected by each thermocouple is the same.
As is clear from the above description, the position of the monitoring point, that is, the mounting position of the thermocouple in the stack cavity is easily determined. The installation of the monitoring terminal (thermocouple) 120 shown in fig. 2 is one of the core contents of the present invention. The installation mode is convenient for collecting temperature information, and structural damage of high-temperature melt to the thermocouple in the prior art is avoided; further, the mounting arrangement in which the thermocouple does not directly contact the reactor pressure vessel may also avoid impacting the normal operation and design of the reactor pressure vessel.
Further, in order to ensure the authenticity and reliability of the temperature information, when the present invention employs a plurality of monitoring terminals 120, the temperature information collected by the plurality of monitoring terminals may be mutually corrected, and the temperature information with obvious errors may be removed before the monitoring device monitors the state of the reactor pressure vessel.
Furthermore, the temperature information collected by the thermocouple is a continuous signal, and further reflects the continuous change state of the temperature of the reactor pressure vessel. Compared with the instantaneous high-temperature signal in the prior art, the temperature information acquired by the invention is real and reliable and has higher effectiveness.
The monitoring device 110 is configured to receive temperature information sent by the monitoring terminal 120, and monitor a state of the reactor pressure vessel according to the received temperature information. As shown in fig. 3, the monitoring device 110 of the present invention may include a trend analysis module 111, a determination module 112, and an alarm module 113. The trend analysis module 111 is configured to analyze the monitored operation status of the reactor pressure vessel according to the received temperature information, the determination module 112 is configured to determine whether the reactor pressure vessel is melted through according to the received temperature information, and the alarm module 113 is configured to send a high-temperature alarm when the reactor pressure vessel is melted through.
In the present invention, the monitoring device 110 for monitoring the state of the reactor pressure vessel includes two aspects: (1) monitoring historical operating conditions of a reactor pressure vessel; and (2) judging whether the reactor pressure vessel is melted through or not.
In a specific implementation, the trend analysis module 111 may display the received temperature information, and generate and output a temperature-time correlation curve that may be used to analyze a state development trend of the reactor pressure vessel, i.e., generate and output a historical operating condition of the reactor pressure vessel, according to the continuously received temperature information. It should be appreciated that the temperature of the reactor pressure vessel fluctuates only to a small extent under normal operating conditions. However, when a core cooling failure or other severe accident occurs, the temperature of the core may continue to rise, causing the temperature of the reactor pressure vessel to continue to rise, and to exhibit a continuously increasing profile over historical operating conditions. The historical operating conditions generated by the trend analysis module 111 are intuitive and facilitate the determination of the condition of the reactor pressure vessel based on the results. The beneficial effects of judging the temperature of the reactor pressure vessel are as follows: there is a certain correlation between its temperature and its wall thickness; the thinner the wall at higher temperatures, the greater the likelihood of fusion and other serious hazards occurring at that time; on the premise of mastering the temperature information, the equipment state of the reactor pressure vessel can be predicted, and effective measures are taken to prevent the fusion-through phenomenon. In fact, the trend analysis module 111 may generate one or more temperature-time correlation curves according to the temperature information collected by one or more thermocouples, or generate one temperature-time correlation curve according to the average value of the temperature information collected by a plurality of thermocouples. Both of the above implementations may be used to trend the state of the reactor pressure vessel.
In an implementation, the determining module 112 may determine whether the reactor pressure vessel is melted through according to the received temperature information. Specifically, the determining module 112 determines whether the temperature information of the reactor pressure vessel exceeds a temperature threshold preset in the determining module 112 according to the received temperature information. If the temperature of the reactor pressure vessel reflected by the temperature information exceeds a preset temperature threshold, the reactor pressure vessel is considered to be melted through (or the possibility of melting through is extremely high) (relevant to the setting of the temperature threshold); at this time, corresponding measures should be taken to solve the problem caused by the fusion penetration as much as possible (or avoid the fusion penetration phenomenon).
In a specific implementation process, when the determining module 112 determines that the reactor pressure vessel is melted through (or the possibility of melting through is very high), the alarm module 113 sends out a high-temperature alarm, so as to attract the attention of relevant personnel. The high temperature alarm described herein includes, but is not limited to, illuminating an alarm indicator light and/or sounding an alarm sound. In addition, although the alarm module 113 of the present invention is integrated in the monitoring device 110, an external independent alarm may be used. When the judging module 112 judges that the reactor pressure vessel is melted through, an alarm signal is sent to an external independent alarm to control the alarm to execute related high-temperature alarm.
Fig. 4 is another schematic view of a monitoring system for a reactor pressure vessel of a nuclear power plant provided with a plurality of monitoring terminals, as shown in fig. 4. At this time, the monitoring device 110 may further include a correction module 114 for correcting the received temperature information and generating corrected temperature information. The trend analysis module 111 and the determination module 112 may then receive the calibrated temperature information and monitor the state of the reactor pressure vessel accordingly.
In a specific implementation, the calibration module 114 receives and calibrates the temperature information transmitted from the monitoring terminal 120. Specifically, the correction of the temperature information by the correction module 114 mainly includes the following steps: (1) calculating an average value of the temperature information collected by the plurality of monitoring terminals 120 to obtain average temperature information; (2) calculating the relative deviation of each temperature information and the average temperature information; (3) comparing the calculated relative deviation with a deviation threshold value stored in the correction module 114, if the calculated relative deviation exceeds the deviation threshold value, considering that the monitoring terminal 120 to which the relative deviation belongs may have an abnormal operation condition, and discarding the temperature information corresponding to the relative deviation; and if the deviation threshold value is not exceeded, the temperature information corresponding to the relative deviation is considered to be valid, and the corresponding received temperature information is used for monitoring the state of the reactor pressure vessel subsequently. In the present invention, the deviation threshold is set to 10%; that is, when the relative deviation between the certain temperature information and the average temperature information exceeds 10%, it is determined that the temperature information is abnormal and should be discarded. The temperature information corrected by the correction module 114 is generally referred to as corrected temperature information in the present invention and is applied to the following analysis process.
When the monitoring device 120 includes the correction module 114, the trend analysis module 111 and the determination module 112 preferably perform relevant condition monitoring based on the corrected temperature information. The specific principle and implementation thereof are the same as those when the received temperature information is adopted, and the detailed description thereof is omitted here.
In conclusion, the monitoring system can master the state (mainly temperature) of the reactor pressure vessel from time to time, and the collected temperature information is effective and reliable; the monitoring device can well analyze the state development trend of the reactor pressure vessel according to effective and reliable temperature information, judge whether the fusion penetration occurs and send a high-temperature alarm to remind related personnel of paying attention.
The invention also provides a monitoring method of the reactor pressure vessel of the nuclear power station. As shown in fig. 5, the method begins at step 200.
In step 202, the monitoring terminal collects temperature information of the monitored reactor pressure vessel. In the specific implementation process, the monitoring terminal is a thermocouple, and the acquired temperature information is represented as an electromotive force signal. The monitoring terminal is arranged at a certain height close to the outer wall of the lower end enclosure of the reactor pressure vessel, namely, the thermocouple is arranged on the circumference of the same height with the axis point of the reactor pressure vessel as the circle center. In a next step 204, each monitoring terminal sends the collected temperature information to an electrically connected monitoring device.
In a next step 206, the monitoring device corrects the received temperature information and generates corrected temperature information. As described above, this step determines whether to use the temperature information by mainly calculating the relative deviation of each temperature information from the average temperature information.
In a next step 208, the monitoring device generates a historical operating condition (i.e., a temperature-time correlation curve) of the reactor pressure vessel based on the corrected temperature information and presents it to the relevant personnel. As mentioned above, the temperature information collected by the monitoring terminal has the self-correcting function. Before the historical operating conditions are generated by using the temperature information, the correctness and the validity of the temperature information are firstly judged, and the temperature information with overlarge deviation is removed. In addition, the monitoring device is provided with a signal conversion module which can convert the electromotive force signal of the thermocouple into a corresponding temperature signal. In step 208, the monitoring device determines whether the reactor pressure vessel is melted through according to the corrected temperature information; the determination includes, but is not limited to, comparing the collected temperature information to a preset temperature threshold.
Subsequently, in the next step 210, if the monitoring device determines that the reactor pressure vessel has been melted through, the alarm module of the monitoring device sends out a high temperature alarm. Or if the monitoring device judges that the reactor pressure vessel is melted through, the monitoring device sends out an alarm signal, and an external alarm sends out a high-temperature alarm.
The method 200 described above is a method process when a calibration module is included in the monitoring device. In contrast, when the monitoring system is not provided with a monitoring device including a calibration module, in step 208, the monitoring device may directly determine the state of the reactor pressure vessel according to the temperature information collected by the monitoring terminal, that is, the monitoring device does not include the calibration module to correct the received temperature information in step 206. Other operations and principles are the same as the method 200, and are not repeated here.
The invention provides a monitoring system and a method for a reactor pressure vessel of a nuclear power station, which comprises the following steps: the monitoring terminal can continuously acquire temperature information, the acquired information is effective and reliable, and the monitoring device can reliably judge the state of the reactor pressure vessel according to the temperature information, so that the equipment state of the monitoring device can be predicted, and a reliable basis is provided for understanding the accident process and guiding accident rescue after a serious accident. The monitoring terminal of the invention does not need to be in direct contact with a reactor pressure vessel or an extremely high-temperature melt, so the requirement on high temperature resistance is low, and extremely high response speed is not needed, so the requirement on the overall performance of the monitoring terminal is reduced, and the cost is favorably controlled. The monitoring terminal is arranged close to the reactor pressure vessel (for example, arranged at the same height and at the same distance with the outer wall of the reactor pressure vessel), and the installation position is easy to determine and implement, thereby facilitating the implementation of the monitoring method. When a plurality of monitoring terminals are adopted, the temperature information collected by each monitoring terminal can be corrected before the state of the reactor pressure vessel is judged, so that the reliability of the temperature information is further improved. The invention adopts the computer technology to carry out subsequent processing on the acquired temperature information, and the analysis and judgment are objective and efficient. The monitoring system for the nuclear power station reactor pressure vessel has the advantages of simple structure and low cost, and the monitoring method is convenient to implement and high in accuracy.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents and improvements made within the spirit and principle of the present invention are intended to be included within the scope of the present invention.
Claims (14)
1. A monitoring system for a nuclear power plant reactor pressure vessel, the monitoring system comprising:
the monitoring terminal is arranged at a monitoring point of the monitored reactor pressure vessel and is used for acquiring and transmitting the temperature information of the reactor pressure vessel;
and the monitoring device is electrically connected with the monitoring terminal and is used for receiving the temperature information sent by the monitoring terminal and monitoring the state of the reactor pressure vessel according to the temperature information.
2. The monitoring system of the nuclear power plant reactor pressure vessel as recited in claim 1, wherein the distance between the monitoring terminal and the reactor pressure vessel is 1-3 cm.
3. The system as claimed in claim 1, wherein the monitoring system is provided with a plurality of monitoring terminals, and the monitoring device further corrects the received temperature information before the monitoring device monitors the state of the reactor pressure vessel:
calculating average temperature information according to the received temperature information;
calculating a relative deviation of the received temperature information from the average temperature information;
judging whether the relative deviation exceeds a preset deviation threshold value in the monitoring device or not; wherein:
if the relative deviation exceeds the deviation threshold, correcting the received temperature information and generating corrected temperature information; otherwise, monitoring the state of the reactor pressure vessel according to the received temperature information.
4. The nuclear power plant reactor pressure vessel monitoring system of claim 3, wherein the plurality of monitoring terminals are disposed equidistantly around the reactor pressure vessel at the same elevation.
5. The nuclear power plant reactor pressure vessel monitoring system of claim 1 or 3, wherein the monitoring device monitoring the state of the reactor pressure vessel comprises:
the received temperature information or corrected temperature information is displayed, and from this historical operating conditions for analyzing the state development trend of the reactor pressure vessel are generated and output.
6. The nuclear power plant reactor pressure vessel monitoring system of claim 1 or 3, wherein the monitoring device monitoring the state of the reactor pressure vessel comprises:
judging whether the temperature information of the reactor pressure vessel exceeds a preset temperature threshold value in the monitoring device or not according to the received temperature or corrected temperature information; wherein,
if the received temperature information or the corrected temperature information exceeds the temperature threshold, judging that the reactor pressure vessel is melted through; otherwise, the reactor pressure vessel is not melted through.
7. The nuclear power plant reactor pressure vessel monitoring system of claim 6, wherein the monitoring device issues a high temperature alarm when it is determined that the reactor pressure vessel is melted through.
8. A method for monitoring a reactor pressure vessel of a nuclear power plant, the method comprising the steps of:
s1: the monitoring terminal arranged at the monitoring point of the reactor pressure vessel acquires the temperature information of the monitored reactor pressure vessel and sends the acquired temperature information to the monitoring device;
s2: the monitoring device receives the temperature information sent by the monitoring terminal and monitors the state of the reactor pressure vessel according to the temperature information.
9. The method for monitoring the nuclear power plant reactor pressure vessel as recited in claim 8, wherein in the step S1, the distance between the monitoring terminal and the reactor pressure vessel is 1-3 cm.
10. The method for monitoring the reactor pressure vessel of the nuclear power plant as recited in claim 8, wherein the monitoring system is provided with a plurality of monitoring terminals, and in the step S2, before the monitoring device monitors the state of the reactor pressure vessel, the monitoring device further corrects the received temperature information:
calculating average temperature information according to the received temperature information;
calculating a relative deviation of the received temperature information from the average temperature information;
judging whether the relative deviation exceeds a preset deviation threshold value in the monitoring device or not; wherein:
if the relative deviation exceeds the deviation threshold, correcting the received temperature information and generating corrected temperature information; otherwise, monitoring the state of the reactor pressure vessel according to the received temperature information.
11. The method of monitoring a nuclear power plant reactor pressure vessel as recited in claim 10, wherein the plurality of monitoring terminals are positioned equidistantly around the reactor pressure vessel at the same elevation.
12. The method for monitoring the reactor pressure vessel of the nuclear power plant as recited in claim 8, wherein the step S2, the monitoring device monitoring the state of the reactor pressure vessel includes:
the received temperature information or corrected temperature information is displayed, and from this historical operating conditions for analyzing the state development trend of the reactor pressure vessel are generated and output.
13. The method for monitoring the reactor pressure vessel of the nuclear power plant as recited in claim 8, wherein the step S2, the monitoring device monitoring the state of the reactor pressure vessel includes:
judging whether the temperature information of the reactor pressure vessel exceeds a preset temperature threshold value in the monitoring device or not according to the received temperature or corrected temperature information; wherein,
if the received temperature information or the corrected temperature information exceeds the temperature threshold value, judging that the reactor pressure vessel is melted through; otherwise, the reactor pressure vessel is not melted through.
14. The method for monitoring the nuclear power plant reactor pressure vessel as recited in claim 13, wherein in step S2, the monitoring device issues a high temperature alarm when it is determined that the reactor pressure vessel is melted through.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN201110367565.XA CN102496393B (en) | 2011-11-18 | 2011-11-18 | System for monitoring pressure vessel of reactor of nuclear power station and method thereof |
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| CN201110367565.XA CN102496393B (en) | 2011-11-18 | 2011-11-18 | System for monitoring pressure vessel of reactor of nuclear power station and method thereof |
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| CN102496393A true CN102496393A (en) | 2012-06-13 |
| CN102496393B CN102496393B (en) | 2014-12-10 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103065433A (en) * | 2012-12-26 | 2013-04-24 | 中山大学 | Monitoring and alarming device for departure from nucleate boiling ratio (DNBR) of reactor core of pressurized water reactor |
| CN105489259A (en) * | 2014-09-18 | 2016-04-13 | 中国核动力研究设计院 | Long-life irradiation monitoring method for reactor pressure vessel |
| CN109243652A (en) * | 2018-09-18 | 2019-01-18 | 中广核工程有限公司 | A kind of nuclear power plant system compressed air require data validity judges system and method |
| CN110265165A (en) * | 2019-06-18 | 2019-09-20 | 中广核核电运营有限公司 | Nuclear power vessel temp adjusting method, device, computer equipment and storage medium |
| CN113984243A (en) * | 2021-10-22 | 2022-01-28 | 中国原子能科学研究院 | Temperature detection device |
| CN114068052A (en) * | 2021-11-30 | 2022-02-18 | 中国核动力研究设计院 | A pressurized water reactor chamber temperature monitoring system |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002207095A (en) * | 2001-01-11 | 2002-07-26 | Toshiba Corp | Pressure leakage testing device of reactor pressure vessel |
| JP2007232503A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Reactor system and reactor control method |
| CN201600931U (en) * | 2010-02-20 | 2010-10-06 | 华北电力大学 | Temperature Sensitive Safety Injection Device for Nuclear Power Plant |
| CN102176274A (en) * | 2011-02-14 | 2011-09-07 | 国家粮食局科学研究院 | Grain condition alarm system, grain condition control system and grain bulk safety state discrimination method |
-
2011
- 2011-11-18 CN CN201110367565.XA patent/CN102496393B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002207095A (en) * | 2001-01-11 | 2002-07-26 | Toshiba Corp | Pressure leakage testing device of reactor pressure vessel |
| JP2007232503A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Reactor system and reactor control method |
| CN201600931U (en) * | 2010-02-20 | 2010-10-06 | 华北电力大学 | Temperature Sensitive Safety Injection Device for Nuclear Power Plant |
| CN102176274A (en) * | 2011-02-14 | 2011-09-07 | 国家粮食局科学研究院 | Grain condition alarm system, grain condition control system and grain bulk safety state discrimination method |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103065433A (en) * | 2012-12-26 | 2013-04-24 | 中山大学 | Monitoring and alarming device for departure from nucleate boiling ratio (DNBR) of reactor core of pressurized water reactor |
| CN103065433B (en) * | 2012-12-26 | 2014-12-24 | 中山大学 | Monitoring and alarming device for departure from nucleate boiling ratio (DNBR) of reactor core of pressurized water reactor |
| CN105489259A (en) * | 2014-09-18 | 2016-04-13 | 中国核动力研究设计院 | Long-life irradiation monitoring method for reactor pressure vessel |
| CN105489259B (en) * | 2014-09-18 | 2017-06-16 | 中国核动力研究设计院 | Reactor pressure vessel longevity phase irradiation method |
| CN109243652A (en) * | 2018-09-18 | 2019-01-18 | 中广核工程有限公司 | A kind of nuclear power plant system compressed air require data validity judges system and method |
| CN109243652B (en) * | 2018-09-18 | 2020-05-15 | 中广核工程有限公司 | System and method for judging validity of compressed air flow data of nuclear power station system |
| CN110265165A (en) * | 2019-06-18 | 2019-09-20 | 中广核核电运营有限公司 | Nuclear power vessel temp adjusting method, device, computer equipment and storage medium |
| CN113984243A (en) * | 2021-10-22 | 2022-01-28 | 中国原子能科学研究院 | Temperature detection device |
| CN113984243B (en) * | 2021-10-22 | 2023-11-10 | 中国原子能科学研究院 | Temperature detecting device |
| CN114068052A (en) * | 2021-11-30 | 2022-02-18 | 中国核动力研究设计院 | A pressurized water reactor chamber temperature monitoring system |
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Address after: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee after: CHINA GENERAL NUCLEAR POWER Corp. Patentee after: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. Address before: 518023 No. 69 Shennan Middle Road, Shenzhen, Guangdong, Futian District Co-patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. Patentee before: CHINA NUCLEAR POWER ENGINEERING Co.,Ltd. |
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