CN202083945U - LOCA (loss of coolant accident) supervising system for refrigerant of reactor - Google Patents
LOCA (loss of coolant accident) supervising system for refrigerant of reactor Download PDFInfo
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- CN202083945U CN202083945U CN201120157137XU CN201120157137U CN202083945U CN 202083945 U CN202083945 U CN 202083945U CN 201120157137X U CN201120157137X U CN 201120157137XU CN 201120157137 U CN201120157137 U CN 201120157137U CN 202083945 U CN202083945 U CN 202083945U
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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
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Abstract
The utility model provides an LOCA (loss of coolant accident) supervising system for a refrigerant of a reactor, comprising an LSS (light spot scanner) communication station (2), an LSS computation station (3) and an LSS parameter modifying computer (4). The LSS computation station (3) is used for the LOCA special computation and the logic alarm computation, and the LSS parameter modifying computer (4) is used for providing an user interface to be convenient for an user to update the parameters of the RIC (reciprocating internal combustion) and a manual keyboard. When the system works, the LSS communication station (2) collects data from an unsafe level DCS (data communication system) (1) and transmits the data to the LSS computation station (3), the LSS computation station (3) computes a result, and the data is sent back to the unsafe level DCS (1) through the LSS communication station (2) to realize the bidirectional data conversion between the LSS system and the unsafe level DCS (1). The system also can be taken as an independent special system for controlling a nuclear power instrument, namely the data is uniaxially transmitted between the unsafe level DCS (1) and the LSS communication station (2) and a computing result is displayed on a KVM (k virtual machine) display (5) to be suitable for the different design requirements of an improved pressurized water reactor type nuclear power station, reduce the cost of the hardware, realize the full-automatic monitoring, and save the labor cost.
Description
Technical field
The utility model relates to a kind of nuclear power station instrument control system, particularly a kind of reactor coolant loss of-coolant accident (LOCA) monitor system that can realize data interaction with non-safe level DCS.
Background technology
Current in nuclear power station instrument control system, reactor loss of-coolant accident (LOCA) LOCA (loss of coolant accident) is one of serious accident of pressurized-water reactor nuclear power plant, current a lot of LSS (LOCA Surveillance System---loss of-coolant accident (LOCA) detection system) is mainly used in monitoring pressurized-water reactor nuclear power plant reactor operation situation, cycle is gathered 56 even more on-site signal by the hardwire mode, carries out the special-purpose computing of LOCA and does monitoring image demonstration and the data storage that logic is reported to the police and finished this locality; With the result of low computational effort, send partial data to give KIT (power station computer system) or DCS simultaneously by the mode of serial ports link communication.If result of calculation is operating point when exceeding operational limit, system will send C21 and report to the police (often opening in the contact switch amount), cause that unit is with power.The reactor loss of-coolant accident (LOCA) monitor system of seeing at present mostly can only be used as autonomous system, and acquisition function is realized by polylith Hardware I/O integrated circuit board, brings difficulty for the maintenance in later stage and the buying of spare part; Monitoring range is confined in the master-control room, and is convenient inadequately; Do not have network interface, can not realize sharing of total data, become information island, just belong to this type of situation as Daya Bay nuclear power plant and mountain range Australia first phase power station LOCA monitor system with non-safe level DCS or KIT/KPS system.
LOCA (loss of coolant accident)---reactor loss of-coolant accident (LOCA)
LSS (LOCA Surveillance System)---loss of-coolant accident (LOCA) detection system
The utility model content
The technical problems to be solved in the utility model is to overcome the deficiencies in the prior art, a kind of reactor coolant loss of-coolant accident (LOCA) monitor system that can really realize data interaction with the non-safe level DCS of nuclear power station instrument control system is provided, and native system also can be according to field requirement, become the independently special-purpose instrument control of a nuclear power system, be applied to the Fortschrittlicher Druckwasser Reaktor nuclear power station.
For solving the problems of the technologies described above, the utility model adopts the basic design of technical scheme to be:
A kind of reactor coolant loss of-coolant accident (LOCA) monitor system comprises:
LSS parameter modification computing machine 4, mainly as the user interface of LOCA monitoring system renewal RIC (reactor core measurement) parameter, maintenance parameters, realize that with LSS computer installation 3 communications are connected, show the data that LOCA is relevant, comprise LOCA result calculated and intermediate value, for the user provides monitoring interface; Carry out data storage simultaneously;
Preferably, adopt netting twine to be connected between LSS operating office 2 and the LSS computer installation 3.
Preferably, adopt netting twine to be connected between LSS parameter modification computing machine 4 and the LSS computer installation 3.
Preferably, LSS operating office 2 and LSS parameter modification computing machine 4 are industrial control computer.
Preferably, also comprise a KVM switching display 5, it is connected with LSS parameter modification computing machine 4 with LSS operating office 2 respectively, and the display screen that is used between LSS operating office 2 and the LSS parameter modification computing machine 4 switches.
After adopting technique scheme, the utility model compared with prior art has following beneficial effect: 1) mode with netting twine has replaced hardwire realization data acquisition, has reduced the quantity of Hardware I integrated circuit board, brings convenience for site operation and later maintenance; 2) this system and non-safe level DCS seamless link, power plant operation person can use among the DCS any operator station to check the reactor operation situation, enlarged the scope of checking of LSS operating point monitoring image, and other data of the markers of all data and power station are used same benchmark, be suitable for Fortschrittlicher Druckwasser Reaktor nuclear power station instrument control system, reduce hardware cost.
Below in conjunction with accompanying drawing embodiment of the present utility model is described in further detail.
Description of drawings
Fig. 1 is the groundwork schematic diagram of existing LOCA (reactor accident monitor system).
Fig. 2 is the structured flowchart of first kind of embodiment of the utility model.
Fig. 3 is the structured flowchart of second kind of embodiment of the utility model.
Embodiment
Fig. 1 is the groundwork schematic diagram of a cover LOCA (reactor accident monitor system) of existing nuclear power station employing, and as seen, 1 ' is the LSS picture display unit among the figure; 2 ' is the LSS computing unit; 3 ' for gathering the I/O integrated circuit board, and this device is used for gathering and processing on-site signal data.
What this cover system adopted is the hardwire acquisition mode, LOCA passes through Hardware I/O integrated circuit board 3 ' collection site signal in system, after the 2 ' processing of LSS computing unit, send LSS picture display unit 1 ', KIT (power station computer system respectively, do not mark among the figure, its effect is equivalent to DCS, but uses with LOCA is respectively independent) and indicator, registering instrument and the warning disc system of master-control room.LSS picture display unit 1 ' is graphically located the result of calculation of LOCA existing, and this display unit is placed on master-control room, and electric power supply plant the operator check.
As time goes on the raising that supervision requires with nuclear power station, it also exposes a lot of deficiencies, such as:
(1) the aging and maintenance issues of I/O plate kind equipment: the LOCA monitor system that this kind mode realizes, use the direct collection site signal of I/O integrated circuit board owing to not being connected with non-safe level DCS, through operation for many years, there are problems such as ageing equipment, analog quantity plate precise decreasing, brought difficulty for maintenance and use;
(2) picture is checked and is limited in scope: owing to just in master-control room, place display unit (display screen), so indication range has only the master-control room operator to see; Other places of power plant can't telemonitoring to LOCA operating point monitoring image;
(3) the history data store time is short: this kind LOCA monitor system adopts autonomous device, can not be by the mode of network communication, realize that with DCS or KIT/KPS system total data is shared, and LOCA system self capacity of memory device is limited, causes the history data store time very short;
Reactor coolant loss of-coolant accident (LOCA) monitor system as shown in Figures 2 and 3 comprises three parts: LSS operating office 2, LSS computer installation 3, parameter modification computing machine 4.Also has KVM switching display 5 in addition.Native system is connected with non-safe level DCS 1.
LSS operating office 2 is mainly as the communication apparatus of the data interaction of reactor loss of-coolant accident (LOCA) monitor system and non-safe level DCS 1, gathers the data that non-safe level DCS 1 key-course transmits and offers LSS computer installation 3 by netting twine; The related data that LSS computer installation 3 is calculated is uploaded to the administration and supervision authorities of non-safe level DCS 1 simultaneously.LSS operating office 2 is a general-purpose industrial control computer, its with non-safe level DCS 1 between adopt netting twine to be connected, also can use Ethernet protocol, the while has also reduced the use of I/O equipment.
LSS computer installation 3 calculates behind the signal data that reception LSS operating office 2 transmits, and then result of calculation is returned to LSS operating office 2 mainly as the equipment of the calculating and the output of C21 signal alarm of LOCA monitoring system; According to circumstances control simultaneously the C21 signal that DO output is used to control reactor capability.As long as the hardware platform of LSS computer installation 3 satisfies above-mentioned signal data transmission, processing and control function, such as the special-purpose instrument control of the nuclear power that can adopt Beijing Guangli Nuclear Power Co., Ltd. system hardware platform SpeedyHold.LSS computer installation 3 and LSS operating office 2 are connected by netting twine.
LSS parameter modification computing machine 4 is mainly as the user interface of LOCA monitoring system renewal RIC (reactor core measurement) parameter, maintenance parameters, for user's undated parameter, configuration device provide means; Carry out data storage simultaneously, and on connected KVM switching display 5, carry out the picture demonstration, such as, show the data that LOCA is relevant, comprise LOCA result calculated and intermediate value, for the user provides monitoring interface.LSS parameter modification computing machine 4 is a general-purpose industrial control computer.LSS parameter modification computing machine 4 and LSS computer installation 3 are connected by netting twine.
Picture shows and actually to be one and to operate on non-safe level DCS 1 active station and the picture software of LSS parameter modification computing machine 4, shows the data that LOCA is relevant on KVM screen 5, comprises LOCA result calculated and intermediate value, for the user provides monitoring interface.The picture that operates on non-safe level DCS 1 active station is shown as a software package, can adopt the LOCA monitor system monitoring software V1.0 of Beijing Guangli Nuclear Power Co., Ltd.'s exploitation.
During operate as normal, this monitor system workflow is as follows: LSS operating office 2 is given LSS computer installation 3 from the field data that non-safe level DCS 1 gathers, and LSS computer installation 3 is given non-safe level DCS 1 and 4 demonstrations of LSS parameter modification computing machine by LSS operating office 2 respectively with data after calculating the result.Connect by netting twine between non-safe level DCS 1 and the LSS operating office 2, can between LSS operating office 2 and non-safe level DCS 1, carry out data communication, realize that data double-way is mutual.
Embodiment one:
As shown in Figure 2, when this reactor coolant loss of-coolant accident (LOCA) monitor system is connected with non-safe level DCS 1, and when picture is presented in non-safe level DCS 1 operator station, can be implemented in seamless fusion with non-safe level DCS 1, the result that can calculate LSS computer installation 3 just by LSS operating office 2, parameter, all important data such as running status all are presented on non-safe level DCS 1 system operator station, the operator of whole like this nuclear power station can use any one active station to check the reactor correlation circumstance, has enlarged the scope of checking of LSS operating point monitoring image.Again because among the non-safe level DCS 1 special-purpose history data store equipment has been installed, storage space will be far longer than common computing machine, so utilize non-safe level DCS 1 historical storage equipment and memory mechanism, storage time is longer, checks historical data mode more (supporting the sharp numerical value trend of curvilinear trend mode to check).In the case, KVM switching display 5 have or not all can because all significant datas can be presented in non-safe level DCS 1 operator station or on the KVM switching display 5.
Embodiment two:
These scheme characteristics are according to field condition, need between non-safe level DCS 1 and LSS operating office 2, realize in the data unidirectional delivery, then information such as historical data, parameter can be presented at respectively with LSS operating office 2 and KVM switching display 5 that LSS parameter modification computing machine 4 is connected on, then can not show above-mentioned data this moment in non-safe level DCS 1 operator station.
As shown in Figure 3, when this reactor coolant loss of-coolant accident (LOCA) monitor system according to the field condition requirement, do not need picture is presented among the non-safe level DCS 1, this system can become the independently special-purpose instrument control of nuclear power station system, 2 need of this scheme LSS operating office are given LSS computer installation 3 by non-safe level DCS 1 data that will collect and are got final product, do not need result of calculation is returned to non-safe level DCS 1, at this moment, select to switch the button on the display screen, just can be by checking the service chart picture on the LSS parameter modification computing machine 4, data such as Parameter File and test dictation, historical data are also stored by LSS parameter modification computing machine 4.LSS parameter modification computing machine 4 is industrial control computers.
This reactor loss of-coolant accident (LOCA) monitor system is except realizing that data sharing is with mutual with non-safe level DCS, or become outside individual independently this system of dedicated system, all right continuous monitoring reactor operation state, by continuous calculating, and result of calculation is shown in modes such as numerical value, figure and curves, simultaneously by the misoperation situation being given the alarm and the mode of control signal, help the operation conditions of the effective monitor reactor reactor core of operating personnel, improve the security of nuclear power station operation, crucial meaning is arranged.
The above only is a preferred implementation of the present utility model; should be pointed out that for those skilled in the art, under the prerequisite that does not break away from the utility model principle; can also make some improvements and modifications, these improvements and modifications also should be considered as protection domain of the present utility model.
Claims (5)
1. reactor coolant loss of-coolant accident (LOCA) monitor system is characterized in that: comprising:
LSS operating office (2) is connected with non-safe level DCS (1) mainly as reactor loss of-coolant accident (LOCA) monitor system, receives the data of non-safe level DCS (1) key-course and offers LSS computer installation (3); The related data that LSS computer installation (3) is calculated is uploaded to non-safe level DCS (1) administration and supervision authorities simultaneously;
LSS computer installation (3), the equipment mainly as the calculating and the C21 signal alarm of LOCA monitoring system are exported is connected with LSS operating office (2), calculates behind the signal data of reception LSS operating office transmission, and then result of calculation is returned to LSS operating office (2); According to result of calculation, judging whether needs to give the DO integrated circuit board to send output order, controls and whether sends the C21 signal that power falls in reactor simultaneously;
LSS parameter modification computing machine (4), mainly as the user interface of LOCA monitoring system renewal RIC parameter, maintenance parameters, realize that with LSS computer installation (3) communication is connected, show the data that LOCA is relevant, comprise LOCA result calculated and intermediate value, for the user provides monitoring interface; Also can be used for data storage.
2. a kind of reactor coolant loss of-coolant accident (LOCA) monitor system according to claim 1 is characterized in that, adopts netting twine to be connected between LSS operating office (2) and the LSS computer installation (3).
3. a kind of reactor coolant loss of-coolant accident (LOCA) monitor system according to claim 1 is characterized in that, adopts netting twine to be connected between LSS parameter modification computing machine (4) and the LSS computer installation (3).
4. a kind of reactor coolant loss of-coolant accident (LOCA) monitor system according to claim 1 is characterized in that LSS operating office (2) and LSS parameter modification computing machine (4) are industrial control computer.
5. according to the described a kind of reactor coolant loss of-coolant accident (LOCA) monitor system of arbitrary claim in the claim 1 to 4, it is characterized in that, also comprise a KVM switching display (5), it is connected with LSS parameter modification computing machine (4) with LSS operating office (2) respectively, and the display screen that is used between LSS operating office (2) and the LSS parameter modification computing machine (4) switches.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201120157137XU CN202083945U (en) | 2011-05-17 | 2011-05-17 | LOCA (loss of coolant accident) supervising system for refrigerant of reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201120157137XU CN202083945U (en) | 2011-05-17 | 2011-05-17 | LOCA (loss of coolant accident) supervising system for refrigerant of reactor |
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| Publication Number | Publication Date |
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| CN202083945U true CN202083945U (en) | 2011-12-21 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201120157137XU Expired - Lifetime CN202083945U (en) | 2011-05-17 | 2011-05-17 | LOCA (loss of coolant accident) supervising system for refrigerant of reactor |
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| Country | Link |
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| CN (1) | CN202083945U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104950854A (en) * | 2015-06-17 | 2015-09-30 | 中国核动力研究设计院 | LOCA (Loss of Coolant Accident) monitoring system of nuclear power plant |
| WO2020103857A1 (en) * | 2018-11-21 | 2020-05-28 | 深圳中广核工程设计有限公司 | Multiple sequence safety display and control touch screen system of nuclear power plant and control method |
-
2011
- 2011-05-17 CN CN201120157137XU patent/CN202083945U/en not_active Expired - Lifetime
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104950854A (en) * | 2015-06-17 | 2015-09-30 | 中国核动力研究设计院 | LOCA (Loss of Coolant Accident) monitoring system of nuclear power plant |
| WO2020103857A1 (en) * | 2018-11-21 | 2020-05-28 | 深圳中广核工程设计有限公司 | Multiple sequence safety display and control touch screen system of nuclear power plant and control method |
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Granted publication date: 20111221 |
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