CN1265220A - Digital engineered safety features actuation system - Google Patents

Abstract

An interface between a Plant Protection System and Engineered Safety Features in a nuclear power plant is disclosed for continuously monitoring the plant protection system initiation circuit for each remotely actuated Engineered Safety Feature system to effect remedial action in the event that the Plant Protection System generates a 'trip' signal. By using actuation inputs from the Plant Protection System and manual, operator implemented inputs, controls are provided for remote equipment components, such as solenoid valves, motor operated valves, pumps, fans and dampers.

Description

Digital engineered safety features actuation system

The application's theme is disclosed in the interim U.S. Patent application No.60/048 of determining jointly of applicant, and 922 and No.60/048,923, all in application on June 6th, 1997, the application requires to enjoy the right of priority of these two parts of applications for they.

The theme of this provisional application generally relates to unsettled U. S. application No.08/848, the theme in 556, and the latter is filed on April 29th, 1997, and it is based on a provisional application that on June 20th, 1996 submitted to, and disclosure is incorporated herein to be used for full disclosure.In addition, the application's theme relates to the present inventor (procurator's numbering: the content ABB-144), it is incorporated herein with for referencial use for " digital plant protection system " at the exercise question of submitting on the same day.

In nuclear power station, employing independently shuts down and safe operation system is monitored the operation of nuclear power station and assessed multiple security parameter.There is under the situation of unsafe condition said shut down and/or safe operation system can automatically be implemented the corrective operation that is fit in the indication of one or more measurement parameters.These safety control systems that are called as the nuclear power station protection system must be able to be worked reliably, thereby require the parameter of all measurements and detection effectively necessary.

In the work of nuclear power station protection system is provided with, generally all need to measure and the relevant multiple parameter values of nuclear power station operation.These parameters comprise for example temperature, pressure, flow rate, power density, neutron flux, liquid level etc.Other function of nuclear power station protection system comprises for each environment division, comprises valve, pump, motor, control device and monitor generator.

In addition, under some qualifications, the nuclear power station protection system can start a reactor self-stopping gear (RT), promptly by starting various fielded systems and remotely initiated devices is rapid, controlled and off-response heap safely.Under the situation of pressurization light-water reactor,, make reactor be in subcritical state and realize shutdown usually by the slowing down control rod is dropped in the reactor core.

In the U.S. Patent application No.08/848556 of unexamined, a kind of invention that is used for nuclear industry is disclosed, this invention provides a kind of automatic self-check system of remote sensor that adopts multisensor, the redundant monitoring of multichannel and control circuit.This system by many independently, sensor-specific handles path detection or measurement parameter, wherein said each bar is handled the path and all is equipped with many parallel redundant sub-paths, they can be distinguished and sequentially insert in the said processing path to realize normal handling, perhaps break to detect from said processing path.The digital value that each sensor will record directly or indirectly is sent to a comparer, this comparer compares measured value and a predetermined value, then the result is sent in the consistance decision logic circuit, output and other input of handling the comparer in path of its comparer are compared assessment, thereby provide an output signal of indicating normal/malfunction.This invention very preferably provides a kind of can check signal path processing capacity and parameter detecting system simultaneously, particularly uses a kind of automatic self-check system of the various logic state validity of many redundant parameter detecting systems of handling paths.

In the U.S. Provisional Patent Application No.60/048922 of unexamined; a kind of invention that is used for nuclear industry is disclosed; this invention provides a kind of nuclear plant digital protection system (DPPS), and this system utilizes digital signal, and has the longer mean time between failures.This nuclear plant digital protection system is characterised in that to have many cross-coupled detected parameters processing channel; these channels transmit the digital value of adjusting through suitably to digital comparator, are compared to determine whether measured parameter has exceeded normal range through digital value and predetermined value of adjusting said by this comparer.Comparer links to each other with each bar in many channels, and receives the independent measurement value of every Channel Detection parameter.If based on 4/2 condition, judge that the detected parameters that is provided surpasses set quota, just produce " automatic stop " signal, operate with enforcing remedies.

An object of the present invention is to provide a digital interface that is arranged between said nuclear power station numerical protection system and the nuclear power station engineered safety features (ESF).

Another object of the present invention provides a kind of digital engineered safety features actuation system (DESFAS) that is used for pressurized water reactor.

As mentioned above, developed with ' 556 unexamined patented claims in a kind of digitizing nuclear power station protection system (DPPS) of being used of institute's discussing system.Said digitizing nuclear power station protection system and above-mentioned automatic self-check system and a kind of nuclear power plant reactor protection system of the common formation of digital engineered safety features actuation system of the present invention.Said DESFAS detects the DPPS start-up circuit of each ESF incessantly.Therefore, the invention provides a kind of interface that is arranged between said DPPS and the remote starter gear, enforcing remedies operation when the latter produces " automatic stop " signal at said DPPS.According to the present invention, utilize from the startup input signal of said DPPS generation and the signal of manually importing by the operator, remote equipment parts such as solenoid valve, motor control valve, pump, fan and stack damper are controlled.

U.S. Pat-5267277 (on November 30th, 1993 authorized, and had transferred assignee of the present invention) describes a kind of control system of prior art in detail, and the trade mark of this system is " NUPLEX 80+ ".Another general purpose of the present invention is improvement or engages this nuclear power station control assembly control system, is included in the system described in ' 277 patents.So disclosed content with the way of reference combination in this application in ' 277 patents.

Therefore, a basic purpose of the present invention provides a kind of interface that engages with Component Control System existing or exploitation recently.

Can understand other purpose of the present invention and feature from the detailed description of present specification and the accompanying drawing of performance summary of the invention.

In said accompanying drawing:

The schematic functional block that the DPPS system that Fig. 1 is connected with DESFAS of the present invention system for expression is connected with a plurality of ESF Component Control Systems.

Fig. 2 is for being used for a kind of digitizing ESFAS of system of the present invention auxiliary relay case.

Fig. 3 is the block schematic diagram of a kind of digitizing ESFAS electrical relaybox control system of the present invention, the row canonical system in the biserial system that expression constitutes according to the present invention.

Fig. 4 is the schematic functional block of a kind of typical DESFAS auxiliary relay case logic diagram of the present invention.

Fig. 5 is than the more detailed single-row block schematic diagram of DESFAS of Fig. 3.

Fig. 5 A is the synoptic diagram of an optical modulation detuner.

Fig. 5 B is the schematic block diagram by the continuous input and output optical cable of fiber coupler.

Fig. 6 is the floor map that a printed circuit board (PCB) of relay and dropping resistor is installed.

Fig. 6 A is shown in Figure 6 and replaces the floor map of the printed circuit board (PCB) of resistor with bonding line.

Fig. 6 B is the circuit diagram that dropping resistor is connected with relay coil.

Fig. 6 C is the circuit diagram that replaces dropping resistor with bonding line.

Fig. 7 is a kind of simplification schematic functional block of typical DESFAS auxiliary relay case test logic circuit.

Fig. 8 is the circuit diagram that is used to implement a photo-coupler of light isolated operation.

Fig. 9 is used for more circuit diagram of a kind of pair of light isolating coupler that has the feedback indication of conventional system of system of the present invention and other.

But Figure 10 is the block schematic diagram that a kind of general light is isolated selective system, wherein Figure 10 A is but that light of the present invention is isolated selective system, Figure 10 B uses the selected A of system shown in Figure 10 A or the circuit diagram of Type B contact for expression, and wherein each type can both be used for other system.

Figure 11 is that a kind of lose-lose light inlet that is used for the present invention and other system is isolated the schematic functional block that can select the output relay module.

Figure 12 is used for the simple functional circuit schematic diagram that having of the present invention or other system isolated a kind of lose-lose light inlet isolation output driver of output state for choosing wantonly.

Fig. 1 represents the schematic functional block with a kind of digital engineered safety features actuation system (DESFAS) of above-mentioned digitizing nuclear power station protection system (DPPS) interface, refers to this system with reference label 20 systems among the figure.As mentioned above, said DPPS is characterised in that first number, and preferably four, cross-coupled detected parameters processing channel A to D is designated as channel 21 to 24 (not expressing cross connection in Fig. 1) respectively among the figure.Every digital value (not shown) that channel provides a process suitably to adjust to a digital comparator, this comparer compares to judge institute's whether overshoot scope of detected parameters through digital value and predetermined value of adjusting said.If judging, two detected parameters overshoot indexs that provided are provided in four channels, just produce " automatic stop " signal and operate with enforcing remedies.

In Fig. 1, every DPPS channel 21 to 24 produces the driving of second number or starts output signal to be transferred in same a plurality of DESFAS row.In a preferred configuration, as shown in Figure 1, express two row A and B, be designated as row 25 and 26 respectively.Therefore, in said preferred disposition, channel 21 produces two and drives or startup output 27a and 27b, and one of them is transferred to row 25, and another is transferred to row 26.Similarly, channel 22 to 24 produces same number of driving or starts output.

Every channel 21 to 24 is that one of a plurality of engineered safety features (ESF) system produces redundant driving or starts output.Utilize the various ESF system of DPPS channel monitoring independently to comprise: (1) Entry-level System, it comprises safety and injects enabling signal (SIAS), vessel isolation enabling signal (CIAS) and recycle enabling signal (RAS); (2) subsystem comprises container and sprays enabling signal (CSAS), main flow isolation signals (MSIS) and auxiliary feedwater enabling signal AFAS1 and AFAS2.These signals are also exported from the nuclear power station protection system of routine.

As mentioned above, drive or start output is transferred to invention as described in the application as 27a and 27b a pair of row A of system and B.Should be appreciated that row A and row B need DESFAS auxiliary relay case discussed below, the content of this respect only describes in detail at row.

Said row 25 and 26 output 28 and 29 be sent to four Component Control Systems 30 to 33 with according to the State Control of enabling signal such as parts such as pump and valves.Introduce startup in more detail below by each ESF system of Component Control System 30 to 33 controls.

Before introduction comprised the parts of DESFAS of the present invention in detail, the general utility functions of at first introducing this system were there to be the understanding of summary to its operation.It is worthy of note that DESFAS auxiliary relay case is as the ESFAS part (as shown in Figure 1) of said DPPS and the interface between the remote starter gear (not shown).Said DESFAS auxiliary relay case comprises the circuit that is connected with control systems of nuclear power plant (PCS), these circuit parts are receiving the DESFAS signal that produces from DPPS according to the standard of being set up, promptly drive or start the ESF system during enabling signal, said ESF system comprises that solenoid valve, motor handle valve, pump, fan and stack damper.Shown in Fig. 3 and 4, said ESF system is started independently by one 4/2 logical circuit, hereinafter will further introduce related content.In addition, handle two hand push buttons simultaneously, in Fig. 4, be expressed as the MANUAL ACTUATE signal of a specific ESF system, also can start this system.DESFAS of the present invention also comprises maintenance and test board (MTP) interface that is used to detect DPPS initial input interface and DESFAS automatic stop logical circuit function.

Once you begin drive, said automatic stop logical circuit will lock, and can not automatically reset when removing the DPPS/DESFAS enabling signal.Said automatic stop logical circuit must hand-reset after removing the DPPS/DESFAS enabling signal.Said DESFAS structure comprise with control main board (MCB) on remote control start the terminal box that restoring board is connected.Said locking and reset feature can be applied to all ESF systems, and except following periodic duty circuit: selection circuit and main flow shielding system in the auxiliary feedwater drive system 1 and 2 can not lock, and do not need to reset yet.

Said DESFAS equipment is used to control two groups of parts that its driving circuit mechanically is separated from each other.Wherein one group comprises all fans and pump, and second group comprise other valve and stack damper, as shown in Figure 3.

In each group, be divided into a plurality of less child groups, thereby can test several assemblies simultaneously, and can not influence the normal operation of nuclear power station, as shown in Figure 6, and described in ' the 556 unexamined patented claims of being quoted hereinbefore.

Utilize be arranged on as shown in Figure 3 safeguard and check-out console 55 on one detect selector switch or the required child group of keypad selection.Be provided with manual control and be used for manual automatic stop of driven element group and lock-up relay.Also can under the situation that does not drive any assembly (water pump or valve), detect DPPS initial input interface.

Before getting back to the accompanying drawing of detailed description, should be understood that said DESFAS auxiliary relay case monitors the output of the DPPS start-up circuit of each ESF system incessantly, as shown in Figure 1.Implement driving for start-up circuit and be provided with the notifying device (not shown).Said DESFAS auxiliary relay case starts the protection operation automatically when 4/2 of the DPPS that receives each ESF system starts input signal, described in the provisional application of submitting to when above quoting.

Should be appreciated that between DPPS channel A to D, DESFAS row A and B, CCS channel A to D and utilize the lead of optical fiber communication or separation such as copper conductor to transmit multiple signal, with transmission signal separated from one another between each assembly.Isolation and detection feedback signal are sent to DPPS channel 21 to 24 by maintenance and check-out console 55 (Fig. 3) from row A and B, and between row 25 and 26.

Describe all features of DESFAS of the present invention now in detail.

Fig. 2 represents a digitizing ESFAS auxiliary relay case, and its Qianmen has been laid down to show the function distribution of this system.As mentioned above, said DESFAS is designed to independently electrical relaybox of two safety, one of installs in each case among row A and the B (label 25 and 26 among Fig. 1).An electrical relaybox is used again with reference to label 34 in Fig. 2 and is represented, be used to drive A row assembly, and another electrical relaybox (not shown) is used to drive B row assembly.The structure of these two electrical relayboxs is basic identical, and difference is casing nameplate and terminal box color coding.The set-up mode of these electrical relayboxs meets the conventional design standard in this area.

Electrical relaybox 34 shown in Fig. 2 is expressed three unit 35 to 37 that open signal and hold the represented interconnection line of this accompanying drawing that drive that are used for receiving from DPPS channel A to D output shown in Figure 1.

Fig. 3 represents briefly that with the schematic functional block form DESFAS auxiliary relay case in the DESFAS case drives logic and circuit, uses among the figure with reference to label 40 indications.The fundamental purpose of structure shown in Figure 3 is to drive the DESFAS assembly when receiving a DESFAS channel signal from the representative channel of said DPPS 42.

In said DESFAS case 40, the logical circuit of DESFAS and I/O interface are divided into two groups.These two groups are pointed to pump I/O 44, pump I/O 46, valve I/O 48 and valve I/O 50, and each group all is connected with the DPPS output circuit of one of said DPPS channel A to D, as shown in Figure 3.Therefore, each group has its oneself programmable logic controller (PLC) (PLC) and I/O.The function of said PLC is divided as follows: pump and fan SIAS, CIAS, RAS, CSAS, AFAS-4 and AFAS-2 in two PLC51 and the 52 control safety feature systems, and as shown in Figure 3 with as described in the reference accompanying drawing 1.Valve and stack damper in two PLC53 and the above-mentioned safety feature of the 54 controls system.Described these assemblies all are contained in the said DESFAS case 40.

When said DESFAS auxiliary relay case received enabling signal from DPPS 42, a DESFAS PLC 51,52,53,54 started the sub-group relay of DESFAS on 4/2 basis.Said sub-group relay is operated necessary parts again to finish system start-up.Between said elementary and subsystem, be provided with a maintenance and check-out console (MTP) 55 and be connected and monitor each system being used to, and the detection that starts logical circuit in each system.

The output of logical circuit and I/ O group 44,46,48 and 50 is sent to the PDAS56 of system, PCS57 and PAS58 selectively, and wherein said pcs system 57 is according to operation nuclear power station pump and valve shown in the functional block 59.Should be pointed out that the solid line representative with the hard-wired interface between the DPPS of two-way mode work, and the dotted line that links to each other with MPT is represented the data link between pump and the valve system.

In Fig. 4, represented to be used for the typical logic that all ESF except that AFAS-1 and AFAS-2 and MSIS start, wherein the ESFAS enabling signal that produces from DPPS is sent to OR door 60 and 61, and output in the combinational circuit of NOT door, AND door, time delay circuit and latch circuit, at last from AND door 62 and 63 output logic signals.

According to logic shown in Figure 4, start said ESF system independently according to 4/2 logic.In addition, two hand push buttons operating a specific ESF system simultaneously also can start this system.In Fig. 4, with manually booting (MANUAL ACTUATE) input signal 64 and two hand push buttons of 65 expressions.In a kind of preferred logical organization, start-up operation Once you begin, the automatic stop logic will lock, and when removing the DPPS/DESFAS enabling signal, it can not automatically reset.But, comprise in the said DESFAS project organization with nuclear power station master control board (not shown) on remote control startup and the terminal box that engages of restoring board (not shown).After removing the startup channel number, operating two hand-resets (MANUAL RESETS) 66 and 67 simultaneously can hand-reset automatic stop logic.Preferably described calm and reset feature is applied to above-mentioned all ESF systems, but except AFAS1,2 and MSIS in the selection circuit, they do not lock, thereby do not need to reset.

Fig. 5 is the detailed block schematic diagram of single-row A, uses among the figure with reference to label 70 systems to refer to, it comprises that hurdle B1, B2, B3, B4 and row R01, R02, R03, R04 are to constitute redundancy communication and processor.Logic and the I/O group of in four son groups shown in Figure 5 each in can representative graph 3, wherein each group can also comprise more redundance as required.Preferably, these redundancy communications and processor can interconnect by Connectorized fiber optic cabling 71.Thereby utilize DESFAS of the present invention can significantly reduce the consumption of relay, fuse and plain conductor.Driving or enabling signal are transferred to each sub-group relay by Connectorized fiber optic cabling 72, and this Connectorized fiber optic cabling also is used for transmitting ESF system drive information from DESFAS row A to on-the-spot assembly (not shown).All information also are sent to maintenance and the check-out console 73 of DESFAS row A, and it is carried out above with reference to the described function of Fig. 3.Row A and B also interconnect by Connectorized fiber optic cabling 74.

As expression more in detail among Fig. 5 A and Fig. 5 B, DESFAS of the present invention utilizes optical fiber to connect each height group, and is used for carrying out data communication between each system's row.As the part of fibre system, in fiber optic circuit, be provided with the modulator-demodular unit of a plurality of use electric energy.Shown in Fig. 5 A, modulator-demodular unit M has input cable IN and output cable OUT, and two cables all pass through conventional connector ST and are connected with modulator-demodular unit.In addition, modulator-demodular unit M has power supply PWR.According to the present invention, a conventional fiber connector FOC removably fixes or otherwise installs or be connected on the modulator-demodular unit M.For example, said joints of optical fibre FOC can utilize a support (not shown) to be installed on the modulator-demodular unit M, perhaps utilizes a flexible guy rope to be connected with modulator-demodular unit.Take place at modulator-demodular unit M under the situation of internal fault or loss of power, can be by with said input cable IN with output cable OUT disconnects and utilize fiber coupler that these cables are linked together shown in Fig. 5 B and with said modem bypass, thus the integrality of fiber path kept.

Each ESF system also utilizes the part of electromagnetic relay as its operating system.In general, commercial programmable logic controller (PLC) (PLC) produces 24 volts direct current output or 12 volts direct current output according to the difference of its manufacturer, thinks the coil power supply or the outage of power switch relay.Usually, the relay that is suitable for the most for the particular power source switching function is with the relay of 12 volt DC power supplys power supply and the relay that must mate with 24 volt DC PLC.In order under the situation that can drive with 12 volt DC power supplys or 24 volt DC power supplys 12 volt DC relays to be installed neatly at relay, the present invention utilizes a kind of relay construction that is installed on the printed circuit board (PCB), this relay or be used for 24 volt DC systems perhaps is used for 12 volt DC systems.As shown in Figure 6, two relay K 1 and K2 and two dropping resistor R1 and R2 are installed on printing board PCB.Said relay K 1 and K2 have 12 volt DC coils, can buy from for example KiloVac company.(for relay K 1) said dropping resistor R1 connects with the coil of said relay K 1 shown in Fig. 6 B.Select the resistance value of said dropping resistor R1, make said resistor R 1 and coil K1 constitute a voltage divider, when supply voltage was 24 volts (direct current), this voltage divider provided 12 volts DC voltage to coil K1.Like this, the relay of one 12 volt DC voltage just can use one 24 volts direct supply.Be used in relay K 1 under the situation of one 12 volt DC power supply, remove said dropping resistor R1, be connected or utilize alternate manner to insert in the said circuit bonding line JP1 to substitute dropping resistor R1.Similarly, a bonding line JP2 is connected or utilize alternate manner insert in the said circuit to substitute dropping resistor R2.Expression substitutes dropping resistor with bonding line among Fig. 6 A.Shown in Fig. 6 C, bonding line JP1 allows said 12 volt DC coil K1 directly to link to each other with one 12 volt DC voltage source.In Fig. 6 B, represented one second resistor (not numbering) with dashed line form; This second resistor can constitute an accurate voltage divider jointly with said resistor R 1, and the operating voltage of relay K 1 coil obtains from the middle connecting line of two resistors.

Fig. 7 represents the detection flogic system of a simplification with the block schematic diagram form, and said flogic system is used for said system.The ESFAS enabling signal that is produced by DPPS is sent to input OR door, and logical circuit shown in passing through, and detects and the output of cleared condition indicator to provide the 1st group, shown in label 80.In a preferred embodiment, by the MTP73 of the row of the A shown in Fig. 5, DESFAS driving and the enable logic detection signal that produces from said DPPS can be input to 4/2 logic, as Fig. 4 and shown in Figure 7.In addition, can detect separately each sub-group relay in part shown in Figure 7 81.At last, can also detection validation there be false the connection in detection flogic system shown in Figure 7 between relay.

In the design of nuclear power station protection system, importantly be isolated from each other between the circuit, thereby a circuit produces the work that overvoltage condition can not influence other circuit.In general, disclosed in this application this digitizing nuclear power station protection system is used programmable logic circuit (PLC) array, and it has one 24 volt DC output terminal, and under the control of said logic array, this output terminal can open or close.Because these PLC are very crucial for system works, so they and overvoltage condition are isolated.According to the present invention, by on other voltage switch parts of the output terminal of PLC and all, adopting fiber coupler can guarantee the integrality of system.As shown in Figure 8, said fiber coupler OC comprises a pair of PN light emitting diode D1 and D2, and their parallel connections (opposite with conducting direction) are between input end IN1 and IN2.The DC voltage that is applied on input end IN1 and the IN2 will make one of two diodes (polarity that depends on input voltage) luminous.The emitter of a phototransistor and base stage are connected between output terminal OUT1 and the OUT2, and its mutual conductance is as being changed by the function of the led lighting that is driven conducting.As a result, be applied to the mutual conductance generation respective change that voltage level on input end IN1 and the IN2 will make phototransistor PT.Input that is formed by the photo-coupler of routine and the electricity between the output are isolated the scope that can reach the 3-5 kilovolt; Therefore, the isolation that is produced by photo-coupler can be guaranteed system integrity.In the facility environment of digitizing nuclear power station protection system, require all devices all to satisfy the 1E grade standard requirement of IEEE, in this facility environment, use photo-coupler can improve system reliability.

Under the situation of DESFAS of the present invention, wherein a plurality of output signals that produce from DPPS are input to the said DESFAS, require to provide protection with other input end of the feedback influence that prevents to produce from the input end of DESFAS.Fig. 9 represents to be used for the dual smooth isolating coupler with feedback indication of the present invention or other invention.Specifically, need to use a photo-coupler to be protected, and can not feed back to another input end from an input end with the output of control from input end 1 or input end 2.Direct-flow input signal 91 and 92 is applied to control diode 93 respectively and 94 collectors with the phototransistor in optoisolator 95 apply an input voltage.Represent a negative input voltage source with 96 among the figure, and represent a positive output voltage with 97, this output voltage is applied to the emitter in the optoisolator 95.A feedback indicator 98 is connected so that the feedback indication to be provided with the transistor of coupling.

Figure 10 A and Figure 10 B represent to be used for a kind of general light of the present invention or other invention and isolate the relay output that can select A, Type B, use among the figure with reference to label 100 systems to refer to.Apply an input voltage from the PLC output terminal of circuit shown in Figure 3 to the input end 101 and 102 that is connected with optoisolator 103 circuit, said optoisolator and the coupling of a pair of phototransistor, to control a pair of relay, system refers to be reference label 105 in the drawings.Said A of selection or Type B contact structure more specifically are illustrated among Figure 10 B, and wherein terminal 106 is a common terminal, the output that terminal 107 produces NC state or NO state.

Figure 11 isolates for another kind of dual light can select the output relay module, uses among the figure with reference to label 110 systems to refer to the C type contact that it has selectable A type or Type B contact and has an additive wire.The input voltage that produces from PLC output terminal shown in Figure 3 is applied to and controls the input end 111 and 112 that diode 113 is connected with 114 circuit, and input state light emitting diode 115 links to each other to represent existing of signal with said input end with 116.Said controlled input signal is applied to a photo-coupler 117, drives a relay in the A/B selector switch 119, to provide as 9 and output shown in Figure 10.

Figure 12 represents this and input light is isolated, had the dual output driver of isolating output state, uses among the figure with reference to label 120 systems to refer to.By making the relay 122 and the output optically-coupled of optical connector 123 can constitute an independently optically-coupled output 121.

Above-mentioned DESFAS and subassembly thereof constitute a kind of digital interface between DPPS in the nuclear power station and any ESF system.DESFAS of the present invention monitors the DPPS start-up circuit that is used to control each ESF system incessantly.Therefore, the invention provides and be arranged on DPPS and be used for a kind of interface between the romote-controlled driving device of enforcing remedies operation when DPPS produces " automatic stop " signal.According to the present invention,, can the remote equipment parts be controlled such as solenoid valve, motor control valve, pump, fan and stack damper by using from the drive input signal of DPPS generation and the manual ringing that applies by the operator.Said DESFAS can be at an easy rate with above-mentioned automatic self-check system and digitizing nuclear power station protection system in various systems cooperating, in the unexamined application that these systems all are documented in above to be quoted.Said DPPS, automatic self-check system and DESFAS of the present invention constitute a complete nuclear power plant reactor protection system.In addition, DESFAS of the present invention system can be at an easy rate and other nuclear power station Control Component control system interface.

In order between DPPS and ESF system, to constitute interface, provide high energy starting relay interface to relate to safe 1E level circuit to utilize any signal that produces by DESFAS of the present invention to start as requested.In addition, in order to produce disadvantageous feedback between the output signal of the input signal that prevents DPPS and DESFAS, various smooth isolation coupling modes have been introduced.A kind of like this optically-coupled also can be used to isolate the 1E level and relate to safe device power supply (DPS).

Between each parts of said system, adopt optical fiber to connect.Use these optical fiber to connect, can import and detect and the logic fault detection,, and can not destroy the integrality that DESFAS monitors with the serviceability of checking DESFAS.Also introduced independent detection for each sub-group relay.At last, can detection validation there be false the connection in a kind of detection flogic system between the relay group.

The preferred embodiments of the present invention are above disclosed.But those of ordinary skills will be appreciated that, can make some improvement and replacement under instruction of the present invention.So scope of the present invention and content should be determined by claim.

Claims (55)

1, a kind of digital engineered safety features actuation system, it comprises:

Enabling signal input from first number of a nuclear power station protection system;

Said input is received by the logical row of second number;

Said logical row converts said input to predetermined driving output; With

Said output is applied to the Component Control System of the 4th number in order to control designed safety feature system unit.

2, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that said nuclear power station protection system produces digital enabling signal input.

3, a kind of digital engineered safety features actuation system as claimed in claim 2 is characterized in that adjusting said digitizing enabling signal input.

4, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that receiving said enabling signal input from the nuclear power station protection system channel of first number.

5, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that said second number is 2.

6, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that utilizing primary and secondary logic processor and I/O device to receive said input.

7, a kind of digital engineered safety features actuation system as claimed in claim 6 is characterized in that said primary and secondary logic processor and I/O device are sent to said Component Control System with said driving output.

8, a kind of digital engineered safety features actuation system as claimed in claim 7 is characterized in that said primary and secondary logic processor also links to each other to monitor said primary and secondary logic processor with check-out console with a row maintenance with the I/O device.

9, a kind of digital engineered safety features actuation system as claimed in claim 8 is characterized in that said maintenance and check-out console can start the detection for said logic in said primary and secondary flogic system.

10, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that said logical row is made of the logic and the I/O group of the 5th number.

11, a kind of digital engineered safety features actuation system as claimed in claim 10 is characterized in that said logical row is made of four logics and I/O group.

12, a kind of digital engineered safety features actuation system as claimed in claim 11 is characterized in that said four groups of steering logics and I/O device control elementary valve and stack damper, backing pump, second valve and stack damper and secondary pumps respectively.

13, a kind of digital engineered safety features actuation system as claimed in claim 12 is characterized in that said every group of logic and I/O device also comprise independently I/O module and one Programmable Logic Device independently.

14, a kind of digital engineered safety features actuation system as claimed in claim 13 is characterized in that said Programmable Logic Device starts designed safety feature relay on 4/2 basis.

15, a kind of digital engineered safety features actuation system as claimed in claim 14 is characterized in that said every group of Programmable Logic Device also links to each other to monitor said Programmable Logic Device and I/O module with check-out console with a row maintenance with the I/O module.

16, a kind of digital engineered safety features actuation system as claimed in claim 15 is characterized in that said maintenance and check-out console can also start the detection for said logic in said Programmable Logic Device and I/O module.

17, a kind of digital engineered safety features actuation system as claimed in claim 16 is characterized in that said every group of Programmable Logic Device also links to each other with check-out console with a row maintenance by the fiber data line with the I/O module.

18, a kind of digital engineered safety features actuation system as claimed in claim 17 is characterized in that said logical row comprises that also one manually boots input to start designed safety feature selectively.

19, a kind of digital engineered safety features actuation system as claimed in claim 18 is characterized in that said logical row comprises that also a hand-reset input is to reset said logical row after said input zero clearing.

20, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that said logical row starts designed safety feature relay on 4/2 basis.

21, a kind of digital engineered safety features actuation system as claimed in claim 20 is characterized in that said logical row comprises that also one manually boots input to start designed safety feature selectively.

22, a kind of digital engineered safety features actuation system as claimed in claim 21 is characterized in that said logical row comprises that also a hand-reset input is to reset said logical row after said input zero clearing.

23, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that between the said input it being feeding back to prevent to import of light isolation.

24, a kind of digital engineered safety features actuation system as claimed in claim 23 is characterized in that said feedback protection is that the output driver that utilizes dual input light to isolate is realized.

25, a kind of digital engineered safety features actuation system as claimed in claim 24 is characterized in that said light isolation output driver comprises that also can be selected an output relay module.

26, a kind of digital engineered safety features actuation system as claimed in claim 25 is characterized in that the output driver that said light is isolated also comprises an independently optically-coupled output.

27, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that using driving high energy relay that output cooperates with 12 volt DC or 24 volt DC and driving said engineered safety features system.

28, a kind of digital engineered safety features actuation system as claimed in claim 1 is characterized in that said row utilize the fiber data line to communicate by letter with said nuclear power station protection system.

29, a kind of digital engineered safety features actuation system, it comprises:

Be used for importing the device of enabling signal from the numeral that the process of nuclear power station protection system reception first number is adjusted;

Be used for said input signal is converted to the device of the numeral output enabling signal of second number;

Be used for said output enabling signal is converted to the device of designed safety feature system start-up signal.

30, a kind of digital engineered safety features actuation system as claimed in claim 29 is characterized in that the said device through the digital input signals adjusted that is used to receive first number also comprises and is used for manually producing said device through the numeral input enabling signal adjusted.

31, a kind of digital engineered safety features actuation system as claimed in claim 30 is characterized in that it also comprises the device that is used for eliminating said output drive signal when said input enabling signal is removed.

32, a kind of digital engineered safety features actuation system as claimed in claim 31 is characterized in that the said device that is used to eliminate said output drive signal comprises a manual reseting device.

33, in a kind of nuclear power plant reactor protection system, be arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features, it comprises:

The cross-coupled processing channel of first number,

Said channel produces the enabling signal input of second number respectively, and by the logical row reception of second number, each said logical row also comprises:

The Component Control System of the 3rd number is used for controlling at least one the startup of said engineered safety features.

34, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 33, it is characterized in that said second number is 2.

35,, it is characterized in that said logical row starts said engineered safety features when receiving said enabling signal input on 4/2 basis as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 34.

36, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 35, it is characterized in that said logical row comprises that also one manually boots input to start said engineered safety features selectively.

37,, it is characterized in that said logical row comprises that also a hand-reset input is to reset said logical row after said input zero clearing as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 36.

38,, it is characterized in that said logical row is also safeguarded with row respectively to link to each other to monitor said Component Control System with check-out console as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 37.

39, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 38, it is characterized in that said maintenance and check-out console can start the detection for said logic in said Component Control System.

40, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 39, it is characterized in that said the 3rd number is 4.

41,, it is characterized in that said four Component Control Systems control elementary valve and stack damper, backing pump, second valve and stack damper and secondary pumps respectively as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 40.

42,, it is characterized in that each Component Control System also comprises independently I/O module and one Programmable Logic Device independently as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 41.

43, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 42, it is characterized in that said logical row utilizes the fiber data line to communicate by letter with said cross-coupled processing channel.

44,, it is characterized in that said logical row uses the fiber data line to communicate by letter with check-out console with said maintenance as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 42.

45, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 44, it is characterized in that said enabling signal input be each other light isolate to prevent the input feedback.

46, as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 45, it is characterized in that said prevent to feed back utilize dual input light to isolate output driver to realize.

47,, it is characterized in that said light isolates output driver and comprise that also can be selected an output relay module as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 46.

48,, it is characterized in that said light isolates output driver and also comprise an independently optically-coupled output as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 47.

49,, it is characterized in that the high energy relay that uses adaptive 12 volt DC voltages or 24 volt DC voltages to start output starts said engineered safety features system as being arranged on a kind of interface between a nuclear power station protection system and the nuclear power station engineered safety features as described in the claim 48.

50, a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features, and this method comprises:

Receive the numeral input enabling signal through adjusting of first number from a nuclear power station protection system;

Said input signal is converted to the numeral output enabling signal of second number;

Said output enabling signal is converted to engineered safety features system start-up signal.

51, as a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features as described in the claim 50, this method also comprises the step of eliminating said output enabling signal when said input enabling signal zero clearing.

52, as a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features as described in the claim 51; it is characterized in that said output enabling signal starts said engineered safety features when receiving the input of said enabling signal on 4/2 basis.

53, as a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features as described in the claim 52, it also comprises the step of monitoring said input enabling signal and said output enabling signal by a maintenance and check-out console.

54, as a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features as described in the claim 53, it also comprises the step that detects said input enabling signal and said output enabling signal by said maintenance and check-out console.

55, as a kind of method of an interface is set between a nuclear power station protection system and nuclear power station engineered safety features as described in the claim 54, it also comprises the step of utilizing the fiber data line that said maintenance and check-out console and said input enabling signal are linked to each other with said output enabling signal.

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