JP2856158B2 - Reactor safety protection device - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor safety protection device, and more particularly to a reactor safety protection device having a means for transmitting a signal between a plant site and a central control room.

[0002]

2. Description of the Related Art A reactor safety protection device is a system for emergency stop of a reactor when an abnormal transient state may occur in order to ensure the safety of the reactor. For this purpose, a plurality of sensors for detecting the state of the plant are provided. For example, Japanese Patent Application Laid-Open No. 61-118801 discloses that signals from a plurality of sensors are taken into a multiplexed signal processor (signal processing device), and if the output signals of the sensors exceed a certain reference value, It has been discussed to output a trip signal from the signal processor to the site for emergency shutdown of the reactor.

Signal transmission from a plurality of sensors to one signal processing device can be performed by a multiplex transmission line using an optical fiber or the like as shown in FIG. 2 of JP-A-58-129699. Are known.

[0004]

In the above-described reactor safety protection device, the transmission of signals from a plurality of sensors to one signal processing device and the control of one controlled device from a plurality of signal processing devices are also performed. Signal transmission to the driving circuit
It is conceivable to use a multiplex transmission path as disclosed in Japanese Patent Application Laid-Open No. 58-129699. Thereby, the number of cables required for signal transmission can be significantly reduced. However,
The present inventors have found that in such a configuration, signal transmission takes time and the controlled device may not operate within a predetermined time.

In the above conventional example, signals between a plurality of sensors installed on the plant site side and a signal processor installed on the central control room side are transmitted individually. In addition, the trip signal output from the processor for the emergency shutdown of the reactor is also transmitted individually. As described above, in the conventional example, the transmission and reception of signals between the plant site side and the control room side are individual transmissions, so that there is a problem that the number of cables is large and the cable laying cost is high.

[0006] It is an object of the present invention to define a reactor scram.
Performs in time, reduces cable laying costs, and
Reactor safety and availability are easily and even more improved
It is an object of the present invention to provide a reactor safety protection device that can be operated.

[0007]

A feature of the present invention to achieve the above object is to detect an analog quantity indicating a state of a reactor.
A plurality of analog sensors to be output and the status of the reactor
Multiple digital sensors for on / off detection
Multiplex transmission of analog signals detected by the analog sensor.
Multiplex transmission means and an audio signal detected by the digital sensor.
First individual transmission means for individually transmitting an on-off signal;
The analog signal transmitted through the double transmission means
The judgment result of judging whether or not the
(1) The on-off signal transmitted via individual transmission means
Output a scrum signal based on the result of the logical decision
A plurality of signal processing means, and each of the plurality of signal processing means
A second individual transmission for individually transmitting the scrum signal
Transmission means and the second individual transmission means.
Of the scrum signal output from the plurality of signal processing means.
A driver who performs a majority decision operation and scrams the reactor
And a step provided between the signal processing means and the driving means.
A non-scrum signal in place of the output signal of the signal processing means.
And a bypass means for supplying a signal to the drive means .

[0008]

According to the present invention, an antenna detected by an analog sensor is used.
Multiplex transmission of analog signal and detection by digital sensor
Individually transmitted on / off signals and signal processing
By individually transmitting the scrum signal output from the stage
The reactor scram
It can be done within a fixed time. Furthermore, because it is possible that the sensor requires minimum number of transmission cable plant site side and a signal processing means which is disposed connecting the central control room side is installed, it is possible to reduce the cable installation cost . Also, a non-screen is used instead of the output signal of the signal processing means.
By providing a bypass means for providing a ram signal to the drive means, multiplexing means, during repair or maintenance when individual transmission means, the sensor or the signal processing unit has failed, Shin
Non-scrum signal in place of the scrum signal output from
A ram signal can be provided to the drive means to avoid reactor scram due to equipment repair or maintenance. Therefore, it is easy to improve the safety and operation rate of the reactor .
It can be further improved .

[0009]

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A preferred embodiment of the present invention will be described with reference to the drawings. In each of the drawings, configurations denoted by the same reference numerals indicate the same configurations. The reactor safety protection device has a plurality of signal processing systems as described in JP-A-61-118801. This embodiment also has a plurality of signal processing systems as in the above-mentioned known example.

FIG. 1 shows a reactor safety protection device according to a preferred embodiment of the present invention. The present embodiment has four signal processing systems A to D as the signal processing system, however, this is an example, and the signal processing system may include another plurality of signal processing devices.

[0011] In a nuclear reactor security device, a sensor installed in the plant site side, the reactor water level, the analog sensor (SA _1a for detecting an analog value, such as the reactor pressure ~S
A _ka, SD _1a ~SD _ka) and digital sensors such as limit switches for monitoring the status of the turbine stop valve (SA
_{1d to} SA _kd , SD _{1d to} SD _kd ). The reactor safety protection device stops the reactor immediately when the output signals of these sensors exceed a certain reference value, but the response time is specified as shown in Fig. 2 to ensure the safety of the reactor. Have been. FIG. 2 shows the signal processing system A of FIG. 1 as an example, but the same applies to other signal processing systems.

The output signals of the analog sensors (SA _{1a to} SA _ka ) are responded by a sensor installed on the object to be detected, and it is determined by a trip circuit 9A whether or not the output signal exceeds a certain reference value. The specified time until outputting the result is
Depends on the detection target. For example, as shown in FIG.
The specified time for the reactor water level is within 1S,
The specified time for reactor pressure is within 0.5S. Then, an output signal from the trip circuit 9A is output, a logical operation is performed by the logical circuit 10A, and a driving circuit 6 installed on the plant site side is output from the logical circuit.
The time required to activate the switching element in A is 50
ms.

On the other hand, as for the digital sensor, as shown in FIG. 2, the digital sensor SA _1d operates, a logical operation is performed by the logical circuit 10A, and the driving circuit 6
The time until the switching element in A operates is 50m
s. As described above, in the reactor safety protection device, the response time when the reactor is emergency stopped by the output signal of each sensor is different, but the response time to the output of the digital sensor is 50%.
It can be seen that ms is the most severe. Therefore, in the reactor safety protection device, multiplex transmission provided to minimize the signal transmission cable between the plant site side and the central control room side needs to be sufficiently studied. Therefore, the processing time of each element circuit and the processing time of the multiplex transmission means for the output signal of the digital sensor are evaluated to determine the optimum multiplex transmission configuration. In a nuclear reactor security device, the switching element driving circuit shown in FIG. 2 is a large-capacity relay for driving a plurality of scram solenoid valve V _A1 ~V _Ai, the response time is about 10~20ms . The logic circuit 10A is formed by a relay circuit, and its response time is about 5 to 10 ms. Therefore, the time from when a signal is applied to the input of the logic circuit 10A to when the switching element in the drive circuit 6A operates is about 30 ms at the maximum. In this state, if signals from sensors on the plant site side are multiplexed and output signals from the logic circuit on the central control room are also multiplexed, the transmission cycle of each multiplex transmission device depends on the number of signal points handled. Although it is different, if there are several tens of signal points like a reactor safety protection device, it may be evaluated as about 10 ms. However, there is a transmission module of several Mbps to several tens of Mbps, but when input data is taken in, transferred to the transmission module and transmitted, the current device is 10 m
s (some of which are faster, but more expensive). Therefore, when all the transmission signals between the plant site and the main control room are multiplex-transmitted, the transmission cycle becomes about 20 ms, and the digital sensor SA _1d
The time from when the output signal is output from the switch to when the switching element in the drive circuit 6A operates is about 50 ms. In other words, the response time is the same as the specified time of 50 ms.
There is also a possibility that the time does not fall within 0 ms. Therefore, in the reactor safety protection device, there is a problem in multiplex transmission of all signals in the signal transmission between the plant site side and the central control room side.

By the way, when the number of signals between the plant site and the central control room is evaluated, the number of signals transmitted from the plant site to the central control room is the same as the number of analog sensors and digital sensors. Ten points. On the other hand, signals transmitted from the main control room to the plant site are only signals output from the logic circuit 10A shown in FIG. Therefore, if the multiplex transmission of the signal output from the logic circuit 10A is realized by individual transmission, the response time to the output signal of the above-described digital sensor can be reduced to about 40 ms. Because, in the case of individual transmission,
It is not necessary to take in the data and transfer it to the transmission module, and since the output of the logic circuit 10A directly drives the switching element in the drive circuit, the response time is negligibly short.

By the way, as shown in FIG. 1, the output signal from the logic circuit 10A is output to the drive circuits of other systems (systems B and C... Not shown, and system D). Has four points. That is, even if this is transmitted by an individual transmission cable, the number of cables is only four, and there is no problem in terms of the number. Also,
If the four cables and the cable for multiplexing transmission of the signal output from the sensor are constituted by one multi-core cable, the transmission cable between the plant site side and the main control room side is one, and this cable is laid. Cost can be lower than conventional methods. Further, if the multi-core cable is formed of an optical multi-core cable or a composite cable in which an optical cable and a metal cable are combined, the cable becomes lighter and the cable is easily laid. When signals between the plant site and the main control room are transmitted by a composite cable, signals to be multiplexed are transmitted by an optical cable, and signals to be individually transmitted are transmitted by a metal cable. This is because, when performing multiplex transmission, it is necessary to use a transmission cable having a wide transmission band.

For the reasons described above, the transmission of signals between the plant site and the central control room is performed by the analog sensors SA _{1a to} SA _ka and the digital sensors SA _{1d to} SA _jd as shown in FIG. The output signal is multiplexed and the trip signal a output from the signal processing device 4A, specifically, the logic circuit 10A in the signal processing device 4A, is individually transmitted. As a result, the digital sensors SA _1d to
The response time from when SA _jd outputs the output signal to when the drive circuit 6A operates can be about 40 ms, which satisfies the specified time of 50 ms. That is, when the reactor is in a state where the control rods are to be fully inserted, the response time until the sensor outputs a signal and the drive circuit 6A, which is the controlled device, operates is within a predetermined time (50 ms). , Specifically 40
ms. Therefore, the control rod can be urgently inserted into the core in a short time. That is, it is possible to minimize the number of transmission cables between the plant site side and the main control room side in the reactor safety protection device while ensuring the safety of the reactor. Transmission circuit 1A of multiplex transmission apparatus of FIG.
Are analog sensors SA _{1a to} S installed at the plant site
It receives the output signal from the A _ka and digital sensor SA _1d -SA _jd, transmits these signals are multiplexed to the reception circuit 3A multiplex transmission apparatus installed in a central control room side by multiplex transmission cable 2A. Receiving circuit 3A, the signal from the analog sensor SA _1a -SA _ka outputs a signal to the trip circuit 9A, the digital sensor SA
The signals from _{1d to} SA _jd are output to the logic circuit 10A. The trip circuit 9A determines, for each input signal, whether the value exceeds a reference value, and if so, outputs a signal for urgently stopping the reactor to the logic circuit 10A. If any of the input signals is a signal to scrum the reactor,
The trip signal a for operating the drive circuit is output. The trip signal a is output from the logic circuit 10A to the drive circuits of the respective signal processing systems (systems A to D) as individual transmission means as described above. The drive circuit 6A excites the scram solenoid valves D _{A1 to} D _Ai by taking a majority decision of the trip signals a to d from the signal processing devices 4A to 4B of each system, specifically, the logic circuits 10A to 10D in the signal processing devices. Drive the coil. 7A and 8A are voltage power supplies. Although the scram solenoid valve having two independent excitation coils is shown as an example in the example of FIG. 1, this may be a scram solenoid valve having one excitation coil. In the current boiling water reactor, the drive circuit 6A has a one-out-of-two-wise configuration as shown in FIG. 9, but is not necessarily limited thereto. ,
It goes without saying that various majority circuits described in Table 9.6 of P264 of the first edition and the first printing can be applied.

Further, the logic circuit 10 of the signal processing device 4A
A has a logic based on a relay circuit in a current boiling water reactor, but this logic circuit itself or a signal processing device is constituted by a microprocessor as disclosed in JP-A-61-118801. The present invention can be applied as it is even in the case where This is because, for example, when the signal processing device 4 is configured by a microprocessor, signal processing is performed at regular intervals as a characteristic thereof. Therefore, when the receiving circuit 3A outputs a received signal to the signal processing device 4A including a microprocessor, there is no guarantee that the signal processing device 4A takes in the signal with good timing. For example, if the signal processing device 4A completes taking in the output signal from the receiving circuit 3A before the receiving circuit 3A outputs a new signal (for example, a signal for urgently stopping the reactor), the signal processing device 4A 4A takes in this new signal during the next signal processing cycle,
After that, a processing time is required until the result of this signal being taken in and subjected to the arithmetic processing (trip signal a) is output. In other words, it takes a maximum of twice as long as the signal processing cycle. In general, the signal processing cycle of the microprocessor depends on the content of the signal processing, but is considered to be about several ms if the trip circuit and the logic circuit function. Assuming that the signal processing cycle is 5 ms, the processing time in the above case is 10 ms. As described above, the processing time of the multiplex transmission device composed of 1A, 2A, and 3A is one time.
In this case, the digital sensor S
The time from the output of A _{1d to} SA _jd until the output of the trip signal a is 20 ms. Since the operation time of the drive circuit is about 20 ms, it is about 40 ms in total, which satisfies the specified time of 50 ms. As described above, the present invention can be effectively applied even when the signal processing device 4A is configured by a microprocessor. Note that each element circuit of the system D is the same as the system A.

FIG. 3 is a diagram showing the implementation of a portion different from the signal object shown in FIG. 1 for the purpose of minimizing the number of transmission cables between the plant site side and the central control room side in the reactor safety protection system. It is an example. The reactor safety protection device has a function to not only perform an emergency shutdown of the reactor when the output level of the sensor at the plant site exceeds a certain reference value, but also a function to scram the reactor by manual operation by the operator. And a function for urgently inserting control rods one by one.
The function to scram the reactor by manual operation is shown in Fig. 1.
(Or FIG. 3) is incorporated in the signal processing devices 4A to 4D. However, the function of urgently inserting control rods one by one is not incorporated in this signal processing device. This functionality can be achieved by selecting the appropriate switches of the switch group 14A in FIG. 3 (centrally located control chamber side), conventionally, scram solenoid valve V _A1 of the signal of the switch group 14A is a plant site side ~V Each was transmitted individually to _Ai . Regarding the emergency insertion of the individual control rod, there is no provision that the response time must operate in a short time as described above. Therefore, regarding the emergency insertion of the individual control rod, multiplex transmission is performed between the main control room side and the plant site side as shown in FIG. The signal of the switch group 14A installed in the central control room is taken in by the transmission circuit 12A, and these signals are multiplexed and transmitted to the reception circuit 11A on the plant site side. The output signal of the receiver circuit 11A is supplied to the switching circuit 13A ₁₁ ~13A _i1, 13A _i2 provided Scrum solenoid valve V _A1 ~V _Ai to operate respectively. That is, from among the receiving circuit 11A transmission signal received, to detect the instruction to spill emergency inserts certain control rods, the corresponding switching circuit 13A _11, 13A ₁₂ to 13
A _i1 and 13A _i2 are driven.

It is well known that when information is multiplexed and transmitted, a transmission code error occurs. However, in the above-described case, the signal received by the receiving circuit 11A is identified by the occurrence of the transmission code error. It may be an emergency insertion command for the control rod. As a result, the receiving circuit 11A switch circuit 13A ₁₁ to an emergency insert the appropriate control rods, 13A ₁₂ ~
A signal is given to a specific switch circuit of 13A _i1 and 13A _i2 to operate the scrum solenoid valve. An emergency insertion of a control rod during normal operation of the reactor can result in partial peaking of the reactor output, which can cause the reactor to scram. That is, there is a possibility that the reactor may be scrummed by the transmission code error and the operation rate may be reduced. In order to prevent such a problem from occurring, the above-described multiplex transmission means needs a measure against transmission code errors. As specific means,
The receiving circuit 11A is provided with a code error check function (for example, a parity check). When the receiving circuit 11A detects that a code error has occurred, the receiving circuit 11A transmits a retransmission request signal to the transmitting circuit 12A. Means for multiplexing and transmitting the signal again to 12A will be provided. As another example, a transmission code error correction function is provided in the multiplex transmission means. This is because the transmission circuit 12A
The signal from A is taken in, a redundant code is added to these signals, and the signal is transmitted to the receiving circuit 11A. The receiving circuit 11A
By correcting the information transmission code error has occurred by the bit pattern of the redundancy code, it is possible to output the proper signals to the switch circuit _{13A 11, 13A 12 ~13A i1,} 13A i2.

As another method, as shown in FIG. 4, the multiplex transmission means is made redundant, and the majority decision of the output of each receiving circuit (logical product in the case of a dual system) is taken to obtain the individual control rods. There is a means to prevent erroneous insertion. FIG. 4 shows a case of a dual system, in which the output signals of the receiving circuits 11A ₁ and 11A ₂ are ANDed.
ANDs the gate 15 ₁ to 15 _i, and controls the switching circuit _{13A 11, 13A 12, 13A i1} , 13A i2 at this output.

As described above, according to the present embodiment, the transmission cable between the central control room side and the plant site side can be used for the single control rod emergency insertion system without the individual control rods being erroneously inserted. It can be minimized by the multiplex transmission means.

FIG. 3 shows the system A as an example, but the same applies to the other systems BD.

FIG. 5 shows an example in which the respective embodiments of FIGS. 1 and 3 are implemented together. In this example,
In addition to the features of FIG. 1 and the features of FIG. 3, the transmission cable between the plant site side and the central control room side is a single multi-core cable or a composite cable, so that the entire reactor safety protection device can be used. There is an effect that transmission cable laying cost can be reduced.

FIG. 6 shows another embodiment of the present invention. As described above, regarding the response time of the system in applying the multiplex transmission to the reactor protection system, the response time for a digital signal from a reed switch or the like is the severest. Therefore, FIG. 6 shows another means that can satisfy the response time of the entire system by focusing on the transmission of the digital signal. The points of the digital sensors SA _{1d to} SA _jd installed on the plant site side are smaller than the number of other sensors. Therefore, even if the output signal of this sensor is transmitted individually as in the idea described with reference to FIG. 1, if these cables are multi-core cables or composite cables, the cable installation cost does not increase. Moreover, by transmitting these signals individually, there is an effect that the response time can be further shortened as compared with the embodiment of FIG.

FIG. 7 is a block diagram of the signal processing device 4A shown in FIG.
Output signal from a single control rod emergency switch group 14
In this embodiment, the signal is multiplexed and transmitted together with the output signal from A. In this case, the trip signal is not output from the signal processing device 4A to the other system, but is transmitted from the receiving circuit 11A at the plant site to the other system. It is appropriate to output a trip signal. Because, in FIG. 6, if the signal transmitted from the main control room side to the plant site side is to be multiplex-transmitted as it is, the multiplex transmission in the system A and the trip signal from the system A to the systems B, C and D are transmitted. Multiplex transmission is performed in each of the sections. However, only one trip signal is output from the system A to the systems B, C, and D.
Using multiplex transmission means for these signals would be too expensive. Therefore, the transmission circuit 12
A, together with the output signal of the switch group 14A, is transmitted to the receiving circuit 11A on the plant site side.
Thus, the trip signal is distributed to the drive circuit of another system. This can minimize the number of multiplex transmission means for transmitting signals from the main control room to the plant site. Also, as for the response time in this case, as in FIG. 1, the processing time of the logic circuit 10A in the signal processing device 4A is about 10 ms.
Considering the case where the multiplex transmission means is about 5 ms and the timing of data transfer between the two is the worst,
The transmission time is about 10 ms, which is twice the above-mentioned 5 ms. Further, the response time of the drive circuit is about 20 ms, and a total of 3
It is about 5 ms, which is shorter than the current fixed time of 50 ms. That is, when the transmission time by the multiplex transmission means is shorter than the processing time of the logic circuit, providing the multiplex transmission means at the subsequent stage of the logic circuit has the effect of shortening the response time of the system. Conversely, if the transmission time of the multiplex transmission means is longer than the processing time of the logic circuit, the provision of the multiplex transmission means before the logic circuit has the effect of shortening the response time of the system. In this case, the embodiment of FIG. 1 can be applied.

In FIG. 6, the multiplex transmission means between the central control room and the plant site provided for emergency insertion of a single control rod may be realized by individual transmission means.

Although the multiplex transmission means and the individual transmission means have high reliability like other apparatuses, they may still fail. Therefore, maintenance or repair at the time of failure occurs. At the time of maintenance or repair, if the system is operated by a signal from the equipment being maintained or repaired, there is a problem in terms of safety or operation rate of the reactor. Therefore, in such a case, as shown in FIG. 8, a means for forcibly outputting a specific logical signal to the output side of the multiplex transmission means and the individual transmission means by the bypass switches 16A _{1 to} 16A _Aj and 18A is provided. The above problem can be solved. If the reactor safety protection device, since that is the safe side designed to operate at signal loss (logically "0"), the logic signal of the above, the power supply 17A ₁ to 1 as shown in FIG. 8
_7Aj , a signal of logic "1" by 19A is preferable. FIG. 8 shows the multiplex transmission means (1
A, 2A, 3A) and individual transmission means (output stage of 4A, 5
A) is shown as an example, but the same applies to other embodiments.

By the way, the switching element in the drive circuit is a large-capacity relay in the examples up to now, but if this is a semiconductor element such as a large-capacity bidirectional thyristor, the whole reactor safety protection device can be used. Can be further shortened.

[0029]

As described above, according to the present invention, the atomic
The furnace scram can be performed within a specified time, and the cable laying cost can be reduced. Further, the safety and operation rate of the nuclear reactor can be easily further improved .

[Brief description of the drawings]

FIG. 1 is a configuration diagram of a preferred embodiment of the present invention.

FIG. 2 is an explanatory diagram showing a response time required for a reactor safety protection device.

FIG. 3 is a configuration diagram of another embodiment of the present invention.

FIG. 4 is a configuration diagram of another embodiment of the present invention.

FIG. 5 is a configuration diagram of another embodiment of the present invention.

FIG. 6 is a configuration diagram of another embodiment of the present invention.

FIG. 7 is a configuration diagram of another embodiment of the present invention.

FIG. 8 is a configuration diagram of another embodiment of the present invention.

FIG. 9 is an explanatory diagram illustrating a configuration example of a drive circuit.

[Explanation of symbols]

_{SA 1a ~SA ka, SD 1a ~SD} ka ... analog sensor,
SA _{1d to} SA _jd , SD _{1d to} SD _jd ... digital sensors,
1A to 1D, 11A: receiving circuit, 2A to 2D: multiplex transmission cable, 3A to 3D, 12A: transmitting circuit, 4A to 4
D: Signal processing device, 5A to 5D: Individual transmission cable, 6
A to 6D: drive circuits.

──────────────────────────────────────────────────続 き Continuation of the front page (56) References JP-A-62-280697 (JP, A) JP-A-62-280690 (JP, A) JP-A-58-221403 (JP, A) JP-A-61-20697 204591 (JP, A) JP-A-62-127695 (JP, A) (58) Fields investigated (Int. Cl. ⁶ , DB name) G21D 3/04 G21C 17/00

Claims (2)

(57) [Claims] An analog quantity indicating a state of a nuclear reactor is detected.
Turn on multiple analog sensors and the status of the reactor
A plurality of digital sensors for detecting when the
Multiplexing for multiplex transmission of analog signals detected by log sensors
Transmission means and on / off detected by the digital sensor
First individual transmission means for individually transmitting a signal, and the multiplex transmission
The analog signal transmitted through the means is a reference value
And the first individual
With the on / off signal transmitted through the transmission means.
Multiple units that output a scrum signal based on the logical decision result
Signal processing means, and for each of the plurality of signal processing means,
Second individual transmission means for individually transmitting scrum signals
And the data transmitted via the second individual transmission means.
Majority of scrum signals output by multiple signal processing means
A driving means for performing calculations and scramming the reactor,
Provided between the signal processing means and the driving means,
A non-scrum signal in place of the output signal of the signal processing means.
A reactor safety protection device comprising: a bypass unit provided to the driving unit . 2. A sensor for detecting the same state quantity of a nuclear reactor.
Four analog sensor groups each having the atom
Sensors that detect the same state of the furnace on and off
The four digital sensor groups included therein and the four
The analog signal detected by the analog sensor group is
Four multiplex transmission means for multiplex transmission for each gensor group
And the on / off state detected by the four digital sensor groups.
A first individual transmission means for individually transmitting a signal,
The analog signal transmitted through the transmitting means is used as a reference.
The result of the determination as to whether or not the value
The on / off signal transmitted via another transmission means;
4 units that output scrum signals based on the logical judgment result of
Signal processing means and the switch for each of the four signal processing means.
Four second individual transmissions for individually transmitting clam signals
Means and transmitted via the second individual transmission means
Many scrum signals output by the four signal processing means
Drive means for performing a calculation and scramming the reactor
Provided between the signal processing means and the driving means.
A non-scrum signal in place of the output signal of the signal processing means.
And a bypass means for giving a signal to the driving means .