JPS61286794A - Training device for operating tool of nuclear power plant - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to nuclear reactors, and more particularly to a training device for training operators of nuclear power generation equipment.

[Prior art and problems]

Nuclear reactors, especially power reactors, have become widely known over the past few years. Although nuclear reactor reactions and their reaction control systems are well known to scientists in the field, heat flow within nuclear reactors is less well known and therefore misunderstood by those who operate nuclear reactors. There are many points. The simulated nuclear reactors that have been used so far are both large and small.
It consists only of electrical components and is designed and installed to operate like an electronic computer operating according to a prescribed program, and is used as a training device for reactor operation to change the flow of hot water or steam in nuclear equipment. It cannot be displayed visually or visually. Scenes presented by such conventional training devices lack the sense of realism of an actual nuclear reactor. All you need for a training device is a pump,
Valves, temperature measuring devices, flow rate measuring devices, etc. must be installed so that they can be operated, operate in a manner that corresponds to various situations, and must be made of transparent material so that they can be operated. The objective is to make it easier for personnel to observe the operation of the simulated nuclear reactor and its various parts during training.

[Object of the Invention] An object of the present invention is to provide a nuclear reactor operation training device that is improved so that power reactor operators can be trained to operate all the reactors in a nuclear power generation facility. Another object of the present invention is to provide an apparatus for studying safety devices for power reactors. Still another object of the present invention is to provide a device that visually indicates the normal situation when an abnormal operation occurs in a nuclear power generating device.

[Key points and effects of the invention]

The second purpose is to use real materials for all the building components (but instead of using nuclear fuel, a heater imitating nuclear fuel is used), and to circulate water and steam in the same way as in an actual nuclear power plant. This is achieved by a nuclear power plant operator training device that allows operations similar to those of an actual nuclear power plant. This training device is even compared to conventional training simulators, which are made of electrical components and operate only according to the program designed by the designer, and which simulates only a portion of the entire nuclear power generation M stage. Even when compared to incomplete simulators, it can simulate the operation of an actual nuclear power plant to a much greater extent.

The above-mentioned simulated nuclear power generation device, ie, nuclear power generation device operator training device based on the present invention, includes (a) a liquid, a heating member that is immersed in the liquid and can heat the liquid to its boiling point, and a heating member that is immersed in the liquid to heat the liquid to its boiling point; (b) A container containing water, which is immersed in this water, and A heat exchange heat radiation pipe through which high-temperature hot water from the simulated nuclear reactor flows through in order to heat the water to the boiling point, and a pipe and pump device that sends the steam from the steam generation heather to the steam turbine; a steam turbine that receives energy steam and discharges low-energy steam, and a pipe and pump device that sends this low-energy steam to a condenser; (d) is coupled to the steam turbine and generates electricity when the steam turbine rotates; a generator, and (e) receiving low-energy steam from the steam turbine,
A condenser that condenses water into water, a reservoir pipe and a pump device for returning the condensed water to the steam generator, and (g) a device for monitoring the temperature and pressure of the heating member; A device that displays a visible display so that the physical state can be identified; and manual and electrical controls capable of taking appropriate corrective action against the simulated nuclear reactor operating in the abnormal operating mode.

In embodiment 1f11 of the present invention, a simulated nuclear reactor produces pressurized water or steam heated above its boiling point at atmospheric pressure. In another embodiment of the present invention, the simulated nuclear reactor is set to operate in any one of many types of abnormal operation modes, and the simulated nuclear reactor thus set is set to return to a normal operating state. You can do it manually.

〔Example〕

Embodiments of the present invention will be described below with reference to the drawings.

FIG. 1 is a flow diagram of a nuclear reactor operator training system according to the present invention.

FIG. 2 is a diagram of the control device of the training device.

FIG. 3 is a pictorial diagram of the control valves of each component of the training device.

FIG. 4 is a cross-sectional view of the training device of FIG. 1 taken along line 4--4.

FIG. 5 is a diagram of an electric circuit for controlling the output of the nuclear reactor.

FIG. 6 is a diagram of the temperature control device for the nuclear reactor and pressurization device.

FIG. 7 is a pictorial diagram of the electric circuit of the output control device for the pressurized water system and the boiling water system of the reactor.

FIG. 8 is a diagram of the cooling water system, drainage system, and water supply system of the reactor.

FIG. 1 is a diagram showing the entirety of a nuclear reactor operator training system based on the present invention. The simulated nuclear reactor 11 generates a large amount of heat,
This simulates a type of nuclear reactor that absorbs this heat with a fluid and guides this fluid to another location to recover the absorbed heat. In this embodiment, the simulated nuclear reactor 11 is made of a glass tube, and this simulated nuclear reactor 11 has a heater 12 that generates heat using a plurality of electrical resistances.
2 is immersed in water inside the simulated nuclear reactor 11. The heater 12 keeps the water in the simulated nuclear reactor at a predetermined temperature, preferably about 23.9 to 148.9 degrees Celsius (about 75 to 300 degrees Celsius).
°F). The temperature of this heater 12 is continuously recorded on a recording device. This recording device may be any recording device currently available on the market. Seven heaters 12 are connected to the recording device of the training device, and of these seven heaters, one heater is placed in the center and the other six heaters are arranged at equal intervals around the center. is preferable.

The training device monitors by recording the temperature of a thermocouple 16 suitably placed along the surface of the central heater. The thermocouples 16 are, for example, spaced apart on one surface of the central heater in different radial directions and along the axis of the central heater. The above recording device has 1 thermocouple for each
Preferably, a temperature output signal of 6 is recorded.

The simulated nuclear reactor 11 discharges high-temperature fluid.

The discharge fluid may be pressurized water or steam. In the case of pressurized water, this discharge fluid passes through the circulation path 68.68A and steam power generation B! The heat is transferred to the water by the pipes 19° and 19A in the pipes 122 and 22Δ, and the heat generates steam, which enters the two turbines through the steam pipes 20° and 2OA. The steam generator 22 is U-shaped, and the steam generator 22
Δ is a straight pipe type, and both steam generators 22 and 22A have the ability to generate steam necessary for the turbine 29.

When the discharge fluid of the simulated nuclear reactor 11 is steam, the valve 7
8 is a leap. The steam generator 22.22A is preferably constructed with glass walls so that its internal operating conditions are visible. Similarly, turbine 29 preferably has a transparent housing so that the steam driving the turbine can be observed.

As the steam passes through the two turbines, it converts thermal energy into kinetic energy, rotating the shaft 30, for example. A preferred method of utilizing the kinetic energy of the shaft 30 is to drive the heat generator 28 to generate electric power, extract this electric power from an appropriate terminal, and guide it to a desired power-using device. The ammeter 86 indicates the output current of the generator 28, and the amount of power generation is determined from this current. When the steam passes through the turbine 29, it releases thermal energy, passes through the circulation path 32, enters the condenser 27, and enters the condenser 27.
7, it returns to water, flows through the condenser 33 and pump 34 to the control panel 10, and returns to the steam generator 22, 22A through the circulation path 69° 69A.

The condenser 27 is cooled with cooling water. This cooling water is pipe 35
The steam enters the condenser, absorbs the heat of the steam as it flows through the pipe 32, and exits the condenser through the outlet 36. The water exiting the outlet 36 may be used for other purposes in the training outfit or may be discharged to a drainage system. The casing of the condenser 27 is preferably made of glass so that its operating state can be observed from the outside.

The above thermal fluid passes through the circulation path 68.68A to the steam generator 2.
2.22A, and releases thermal energy while passing through this steam generator 22.22A, circulating path 38.38A,
It circulates through a path that enters the simulated nuclear reactor 11 via a pump 37.37A and a circulation path 39.39A. When using the above training device as a pressurized water generation type, a pressurizer 24 is used,
Water is contained in this pressurizer 24, and this water is poured into a snake pipe 4.
0 (this corrugated tube may be an electric heating type or one heated by another heat source), and this heating is performed so as to generate an upper pressure higher than the vapor pressure of the water in the pressurizer 27.

Of course, this steam pressure is sent to the training device, and this steam pressure is maintained appropriately to prevent the water in the simulated nuclear reactor 11 from evaporating.

When steam is generated in the simulated nuclear reactor 11, a pressurizer 24 is used.
is not used, and valve 70 is closed. The water storage 4f121 is a tank for storing water to maintain an appropriate amount of water in the entire training device when the training device malfunctions and leaks water. Appropriate pressure gauges 41 are placed at various locations so that the pressure state at that location can be read. Thermometers 42 are also placed at various locations to monitor the temperature at that location. Simulated nuclear reactor 1
1. Steam generator 22.22A, pressurizer 24, water storage tank 2
1, and the pumps, valves, and pipes attached to each of these devices are all installed in a protective container 65, and even if the training device leaks or ruptures, this protective container 65 will not allow the training device to be operated. The shape is such that it does not cause any harm to those using the device or those who are near the training device.

The control panel 10 is installed in one place for easy viewing and has an illuminated display 5Jt15, and this display panel 15 is equipped with appropriate valves, instruments, etc. for controlling the flow of fluid in the training device in each section of the training device. Displays temperature display, control switch, and tube operating status. The display panel 15 has a plurality of display sections that display the status of the training device at any given time, and each display section individually displays the status of each part of the training device that is in operation by lighting. For example, when the training device is operating at maximum output, the "maximum ratio" display is lit so that it can be seen from the front of the control panel. Similarly, a "low output" display indicates that the training device is operating at low output. Display portions of the display panel 15 other than the above indicate abnormal operation. The "Water Leakage Accident" display indicates that the coolant has decreased due to an accident, and this means that the water leakage has occurred in the training equipment, so the liquid level of the coolant (water in this training equipment) in the reactor should be adjusted to the normal level. This means that coolant must be added manually or automatically to maintain the temperature. The "High Pressure Water Injection" display is related to the high pressure water injection system, and this display indicates that water is being injected into the training equipment at high pressure due to a coolant leak in the training equipment. "Pressurized water type J" indicates that the training device is operating as a pressurized water type. "Boiling water type"
The display indicates that it is operating as a boiling water type. ``An indication of ``Cooling down'' indicates that the training device is at zero output, but is still generating heat because it is cooling down.

The display of "cooling stop" and "high temperature stop" indicates that the training device is stopped in a cooling state or a high temperature state. Each display on the display panel displays various operating modes of the training device.
It can be used to explain how to operate the core normally and how to prevent damage to the core in the event of water leakage or other abnormal operations.

The operation panel 14 includes switches and timing adjustment devices for operating various electromagnetic valves disposed in various parts of the training device. The operation panel 14 and the display panel 15 are used to indicate whether the operator should change the operation of the power reactor from an abnormal state to normal. Good for learning how things can be restored.

FIG. 2 is an enlarged view of the control panel 10, which includes a display panel 15 and an operation panel 14. As shown in FIG. Part 17 of the control panel is lined with instruments, and these instruments are the heater and fuel (heater in this training equipment) of the simulated nuclear reactor that is immersed in the water inside the reactor body.
Displays the temperature and output in terms of voltage and current. The control panel section 18 is lined with switches, including switches for selecting the type of simulated nuclear reactor (boiling water type or pressurized water type), various drain valves in the reactor body, steam generator, and pressurization switch. This is the operating switch for the pressure vessel. Part 25 of the υIall panel includes valves, pumps, turbines, condensers, pressurizers,
There are various switches and gauges to operate the high-pressure water injection device and the main output device. The control panel section 26 is lined with switches for various lights of the AAIO control and power switches for the illumination lights of each part of the training station.

FIG. 3 is a drawing showing individually the various valves for operating the devices inside the protective container 65. The valves in the row below the reference numeral 31 are solenoid valves. However, this does not include manually operated safety valves. The valves listed below the reference numeral 43 are manual valves.

The part indicated by line 44 is a manifold connected to the above-mentioned various valves and a water tank 45 explained in FIG. 8.

FIG. 4 is a cross-sectional view of the furnace body 11 taken along line 4--4 in FIG. FIG. 4 shows an arrangement of seven heaters 12, of which the central heater 12 is fitted with thermocouples 16 (in different radial and longitudinal directions) for 1ltI. The inlet annular portion 46 guides the supplied cooling water downward as shown in diagram gR1.

FIG. 5 is a diagram showing the main power supply control circuit for the furnace body 11. 647.49 connects the power supply control device 48 (located in section 25 in FIG. 2) to the appropriate section of the display panel 15. A voltmeter 49 and an ammeter 50 (located on the operation panel 14 in FIG. 2) display the power supplied to the heater 12 of the furnace body 11. This supplied power is controlled by a potentiometer attached to the operation panel 14, and this potentiometer is operated by a control knob 51 on the operation panel. The supplied power is preferably 220 volts alternating current, and the potentiometer serves only to remove the sinusoidal portion of the supplied power, thus controlling the supplied power. The line 52 is for activating the temperature relay and stopping the power supply when the temperature of the thermocouple indicated by the line 53 rises above a specified value. l! 1154 acts to stop the operation of the furnace body when the temperature of the thermocouple indicated through line 53 falls below a specified value. The line 55, circuit breaker 54, and switches 57 are a circuit for supplying the above-mentioned power to the control panel 10 and related equipment for controlling this power supply.

FIG. 6 is a diagram showing an electric circuit for controlling the furnace 11 and the pressurizer 24. The instrument 58 (disposed on the operation panel 14) is connected to the furnace 11.
It also detects whether the water in the pressurizer 24 is sufficient and indicates whether the operating conditions of the furnace and pressurizer are safe. When water is insufficient, thermocouple 59 or 60 is exposed,
Since the needle of the meter 58 points to the dangerous range 61, it can be seen that the operating state has become dangerous.

Gauge 62 (also located at operation 5J114) selects thermocouple 16 of heater 12 of furnace 11 to monitor its temperature. This thermocouple 16 imitates a device for monitoring the temperature of nuclear fuel in a nuclear reactor. The meter 62 is a connecting rod 6 that is manually adjusted.
It has 3. When the needle 64 is moving in a higher value range than the connecting rod 63, an activation signal is sent to the high-pressure water injection device via line 66, and this activation signal is displayed via line 67! 3
Turn on the high pressure water injection indicator 15. Next, the high-pressure water injection device injects water into the furnace 11 or the pressurizer 24 to bring the liquid level to a specified level.

FIG. 7 shows a control device for selecting the operating mode of the furnace 11. In this FIG. 7, the steam generator 22 (U
The figure shows the state in which the (shape) is connected to the furnace 11. Steam generator 2
2A (straight pipe type) is not shown in FIG. 7, but the connection procedure to the furnace 11 is the same as the steam generator 22 described above. Furnace 1
1 water inlet, water outlet, connection pipe of furnace 11, steam generator 2
2 and pump 37 are given the same reference numerals as in FIG. Solenoid valve A
. . . C are operated by operating mode selection switches on the operation panel 14, that is, pressurized water furnace mode and boiling water mode. Switches A to C on the operation panel 14 are connected to valves A to C, respectively. When operating the furnace 11 in pressurized water type mode, open valve A and then switch valve B.

Open C. Conversely, to operate the furnace 11 in boiling water mode, valve A is opened and valves B and C are opened. The pressurized water furnace mode or boiling water furnace mode display on the furnace operation mode display section of the display panel 15 lights up.

FIG. 8 is a diagram showing a cooling water system, a drainage system, and a water supply system. The protective container 65 is connected to the furnace 11 and the pump, 37.37
Shown with A. Equipment other than the above described in FIG. 1 of the protective container 65 is not shown in FIG. 8 to simplify the drawing. The pumps 37° and 37A must be cooled in order to operate efficiently, so connect the water supply pipe 70, fill with normal tap water, circulate this tap water through the pump, and then send it to the air conditioner 71. . This air space X1t171 maintains the air condition in the protective container 65 appropriately. Air conditioner 71
The water from the main water supply tank 45 enters the main water supply WJ45 through the pipe 72, and after exchanging heat with the water in this main water tank 45, it flows through the corrugated pipe 35 for cooling to condense the steam coming out of the turbine. Acts like water. This water exits the condenser and flows through tube 36.

This water may be recirculated for cooling or discharged as waste water. The main water supply tank 45 is kept almost full so that water can be supplied to the high-pressure water injection device.

Two pumps 73, 74 are connected in series to deliver the high pressure water required by the high pressure water injection system, and this high pressure water is passed through pipes 75 to each piece of equipment selected by the operator of the training system.

An ion exchange device 76 is shown in FIG. 8, and this ion exchange device 76 processes the water in the main water tank 45 to make it soft water when soft water is required. All water discharged from the equipment in the protective container 65 is collected in the manifold 44 (FIG. 3) and sent to the main water tank. A power supply line 77 connects the switches on the operating panel 14 to the pumps 73, 74 and the ion exchange device 76.

A particularly important point in the present invention is that abnormal operation of a nuclear reactor can be displayed and shown.

For example, a water supply system 3 that normally circulates water into the furnace 11
8, it is possible to easily show the state in which water flow failure has occurred. By appropriately operating the valves and controlling the training device, it is possible to change the flow of the water supply pipe 39 and lead water from the reactor 11 to the main water tank 45, but this may cause a break in the reactor's primary cooling system. This corresponds to the case where this occurs. After the specified time has passed,
The drainage system is closed, the high-pressure water injection device starts water injection, and cooling water is injected into the furnace 11 at a flow rate set by the manual control valve.

The predetermined time can be arbitrarily set in advance within a range of up to about 60 seconds by operating a switch on the operation panel 14. Another example of abnormal operation is that a "core flat" device can be activated independently, and this device
Using switch 4, it is possible to cause the core to begin flattening after an arbitrarily preset time within a range of up to 40 seconds. Additionally, one of each manual valve can be manually operated to vary the displacement (9), thereby simulating varying the blowdown rate to match the extent of cooling water loss. It is also possible to incorporate a high-pressure or low-pressure water injection device into various protective containers and operate the training device as described above.

Other malfunctions relate to failures of the steam generator 22 in the pressurized water reactor mode, or of tubes 19 or 19Δ of 22Δ. If a pipe fails, hot pressurized water flows into the steam generator to generate steam. Therefore, the tube 20
Alternatively, the pressure of the 2OA steam increases rapidly, and the pressure in the furnace 11 and the pressure in the tube 68 or 68A decreases. Accidents of this type occur in real nuclear power facilities, and operators need to know how to respond to them and what to do to avoid them. In the training device according to the present invention, the valve 81 operated by a solenoid valve is opened, and high temperature pressurized water is supplied to the pipe 68 (the seventh
By guiding the steam from the steam generator 22 through the pipe 80 into the steam generation space 82 of the steam generator 22, a failure of the pipe can be simulated. Such a structure can also be used in a steam generator if necessary. Normally, valve 81
is closed, but can be opened by operating a switch on the operation panel 14.

Furthermore, other abnormal operations that can be simulated using this training device include:
For example, this is the case when the pressurizer 24 comes off for some reason.

Such an accident can be simulated by closing valve 70 (FIG. 1). The corrective action when the pressurizer 24 comes off in this training device is to open the high-pressure water injection and water injection valves (Fig. 3) and operate the high-pressure water injection pumps 73 and 74. The pumps 73 and 74 are centrifugal pumps, and the maximum head thereof is the furnace 1.
For example, 2, I Kgl ci (30
psia).

The pumps 73 and 74 have a discharge pressure of, for example, 2.1 Ky/
A pressure of 30 psia or more is applied to the furnace 11.

When this pressure is reached and no water comes to the pump, the pump will maintain the pressure but will not discharge water.

When simulating a water leakage accident caused by a pressure drop using this training device, the water discharge pressure of the pump should be set to approximately 2, I
Return to K9/cri (30 psia). For some reason, the pressure of this training device was reduced to 2.1Kg/ci (30
psia) or higher, pump the water to 73°7
4, the pressure in the main water tank 45 is 2.1/(g/d(30DS
Reflux until reduced to ia).

The safety management that this training device can simulate is a measure against large-scale leakage accidents. This measure is useful, for example, when a power generation facility needs to be operated at low pressure in order to reduce the leakage, when the building would be destroyed or equipment damaged if left unchecked. This training device detects leaks and injects sufficient water into the training device equipment using a high-pressure water injection device.

An electrical switch 83 is used to control this high pressure water injection device.
(Fig. 7) is provided, and this switch 83 senses the pressure,
Starts or stops water injection from the high-pressure water injection device at a predetermined pressure. This switch 83 is turned on at any pressure,
Can be adjusted to turn off. For example, it can be set to turn on at 50% of the training device's normal pressure and turn off at 75%. Therefore, the high-pressure water injection device periodically interrupts water injection to maintain the pressure between the two valves.
□ Maintain the operating pressure of this training device and compensate for water leaks. The switch 83 is connected to the operation panel 14 by a line 84.
is connected to a keyed control switch 85. The switch 85 can be set when the key is inserted, but if the key is removed, the setting conditions cannot be changed unless the key is inserted again. By doing this, if the instructor has the key, it is possible to prevent the operator from changing the switch 85 without the instructor's permission. Switch 85 can also automatically operate switch 83 so that it is turned off when the furnace begins to operate at normal pressure, and turned on when the pressure saw drops due to a leak.

[Brief explanation of drawings]

Fig. 1 is a functional diagram of the nuclear power plant operator training device based on the present invention, Fig. M2 is an external diagram of the control panel of the training device shown in Fig. 1, and Fig. 3 is a valve diagram of each part of the training device shown in Fig. 1. wiring diagram, 4th
The figure is a cross-sectional view of the above-mentioned training device taken along line 4-4 in Figure 1, Figure 5 is a schematic circuit diagram of the output control device of the simulated nuclear reactor, and Figure 6 is a schematic diagram of the temperature control device of the simulated nuclear reactor and pressurizer. FIG. 7 is a schematic wiring diagram of the power control II device for the pressurized water system and boiling water system, and FIG. 8 is a schematic diagram of the cooling water system, drainage system, and water tank. 10... Control panel, 11... Simulated nuclear reactor, 12...
Heater, 14...Operation panel, 15...Display panel, 16
, 59゜60...Thermocouple, 19.19Δ, 35...
Pipe, 20°2OA...Steam pipe, 21...Water tank, 2
2.22A... Steam generator, 24.27... Pressurizer, 27... Condenser, 28... One engine, 29...
Steam turbine, 30...shaft, 32.33.38
．． 38Δ, 69° 69A...Circulation path, 34...Pump, 36...Outlet, to 37.37, 73.74...
Pump, 40...Serial pipe, 41...Pressure gauge, 42...
・Thermometer, 45... Main water tank, 51... Knob, 58
．． 62... Instrument, 61... Hazardous area, 65... Protective container, 7o... Water supply pipe, 71... Air conditioner, 76...
...Ion exchange equipment. Applicant's agent Kiyoshi Inomata FIG, 2 Procedural amendment opening ceremony) July 1, 7, 1985 Michibe Uga, Commissioner of the Patent Office 1, Indication of the case 1985 Patent application No. 20782 2, Title of the invention Nuclear Power Plant Operator Training Device 3, Relationship with the Amendment Person Case Patent Applicant Glenn, Jie, Shellasot 4, Agent June 4, 1986 (Shipping Date June 24, 1986) 6. Amendment Target of

Claims (1)

[Claims] 1. A liquid, a heater immersed in the liquid and capable of heating the liquid to its boiling point, and a closed circuit for returning the liquid from the simulated nuclear reactor to the simulated reactor via a steam generator. a simulated nuclear reactor comprising pipes and pumping equipment for moving the water inside, a container containing water, and a container immersed in the water, through which a hot liquid exiting the simulated reactor flows to bring the water to boiling point; a steam generator including a heat exchanger having a heating tube, a pump device and a tube that sends steam from the steam generator to the turbine; a steam turbine that receives high-energy steam and discharges low-energy steam; a pipe and pump device for sending low-energy steam to a condenser; a generator connected to the steam turbine to generate electricity when the steam turbine rotates; and a generator for receiving and generating low-energy steam from the steam turbine. a condenser for condensing steam to water, and pipes and pumping equipment for returning this condensed water to the steam generator, the temperature and pressure of the liquid in the furnace and the temperature and pressure of the liquid immersed in the water; In a nuclear power plant operator training system including a device for monitoring the temperature and pressure of a heating element, the nuclear power plant operator training system is operated in a simulated nuclear reactor by selecting one of several operating modes. a device for displaying normal or abnormal operation of the reactor to enable observation of the physical state of the simulated nuclear reactor; A nuclear power plant operator characterized in that the above-mentioned training device has been improved to include a manual control device and an electric control device provided in the center so that corrective measures can be taken sufficiently in response to abnormal operation of the nuclear power plant operator. training equipment. 2. The nuclear power plant operator training device according to claim 1, wherein the liquid is water. 3. A patent claim characterized in that the liquid is water that is sufficiently pressurized so as not to evaporate at any point between being sent from the simulated nuclear reactor to the steam generator and returning to the simulated nuclear reactor. A nuclear power generating equipment operator training device according to item 1. 4. The nuclear power plant operator training device according to claim 1, further comprising an instrument that indicates that not all of the heating elements are immersed in the liquid in the simulated nuclear reactor. 5. The observable display device has a display panel that can be lit, and each of the display panels has a display section that can identify the physical state of the reactor, and the display panel has a display panel that can identify the physical state of the simulated nuclear reactor. 2. The nuclear power plant operator training device according to claim 1, wherein the corresponding display section is lit in response. 6. Nuclear power plant operation according to claim 4, including a device for indicating that the simulated nuclear reactor is flat when liquid is added to submerge all of the heating elements. personnel training equipment. 7. A suitable part of the nuclear power plant operator training device has a water supply device separated from the water portion, and the water supply device is connected to the nuclear power plant by means of suitable pipes, valves, and pump devices. Claim 1, characterized in that the simulated nuclear reactor is connected to an operator training device and flattens when the valves, pumps and other control devices are activated.
Nuclear power generation equipment operator training device as described in paragraph. 8. The steam generator, turbine, generator, and condenser are made of transparent materials in whole or in part, and the internal workings, parts, and water and steam paths are controlled by the nuclear power plant operator training device. 2. The nuclear power plant operator training device according to claim 1, wherein the training device is designed to be able to be observed by personnel. 9. A device capable of manually setting the above-mentioned furnace to any one of several types of abnormal operation modes, and changing this abnormal operation mode to a normal operation mode by manual operation of an appropriate control valve or other control device. A nuclear power plant operator training device according to claim 1, characterized in that the training device includes: 10. The simulated nuclear reactor, steam generator, and other potentially dangerous equipment are enclosed and isolated from the operator of the nuclear power plant operator training system, and the equipment can be observed by the operator. The nuclear power plant operator training device according to claim 1, characterized in that it has a protective wall. 11. Nuclear power plant operation according to claim 1, characterized in that the simulated nuclear reactor has a device for detecting the concentration at different depths of the liquid in the simulated nuclear reactor. personnel training equipment. 12. A patent characterized by including a device for selectively introducing pressurized hot water at a pressure higher than atmospheric pressure into the steam generator, and converting the introduced pressurized hot water into steam in the steam generator. A nuclear power plant operator training device according to claim 1. 13. A patent claim characterized by comprising a sealed container containing water and a device for sufficiently heating the water in the sealed container to a pressure higher than atmospheric pressure in the nuclear power plant operator training device. A nuclear power plant operator training device according to scope 3. 14. A device that closes the connection between the container and other parts of the nuclear power plant operator training device, and is connected to the training device and a separate water supply device to substantially maintain the operating pressure of the training device. 14. The nuclear power plant operator training device according to claim 13, further comprising a pump device. 15. A pressure selection switch is provided at the inlet of the simulated nuclear reactor, and this pressure selection switch selectively sets high pressure and low pressure, so that the pressure at the inlet of the simulated reactor is set to the high pressure and low pressure set above. The pump sends water from the water supply source device when the water supply source device is in Nuclear power plant operator training device according to scope 7. 16. The nuclear power plant operator training device according to claim 15, wherein the pressure selection switch is controlled by a power supply switch, and the power supply switch is operated by a removable key. 17. Simulated nuclear reactor, one or more steam generators, pressurizers,
and a protective enclosure surrounding the pumps, lines and remotely operated valves associated with such equipment, including water and an electric heating element immersed in the water, the electric heating element being provided with a suitable temperature monitor for temperature monitoring of said water. The above-mentioned simulated nuclear reactor is a container having a thermocouple, and the thermocouple is disposed in a portion of the electric heating element immersed in water; The above-mentioned steam generator has a structure in which there is water on the outside and hot water or steam pumped from the above-mentioned simulated nuclear reactor is passed through the pipes, and the above-mentioned simulated nuclear reactor is connected to the above-mentioned steam generator. suitable pumps, valves, and conduits for delivering water to the reactor and said generator, for directing steam exiting said simulated reactor or steam generator out of said protective enclosure, and for receiving steam exiting said simulated reactor; , and a steam turbine that is connected to a generator and rotates to cause the generator to generate electricity; and a steam turbine that receives discharged steam from the steam turbine, condenses it and converts it into water, and converts the water into the steam generator. a water tank for receiving water discharged from any or all of the above equipment and discharging the water to any other part of the training system; and a device for pumping water from the water tank to the simulated nuclear reactor to cause flattening of equipment in the training equipment, and a device for causing the equipment in the training equipment or any of the equipment to operate in a plurality of normal operating modes or abnormal operating modes. A monitoring instrument that indicates the temperature and steam of water and steam in various parts of the training equipment, and indicates the power consumption of equipment in the simulated nuclear reactor or the amount of power generated from the generator. The monitoring instruments, the electrical switches that regulate the timing of operation of selected pumps and valves, and the training device or any of its components are operating in one of a plurality of normal and abnormal operating modes. A nuclear power plant operator training device improved to include a control panel provided at the center of the training device and equipped with an illumination device, including a display panel that indicates by blinking. 18. There is a pressurizer inside the protective container, water is poured into the pressurizer so that it does not become full, and when this water leaves the simulated nuclear reactor, it is heated to a temperature higher than the boiling point of the water, and this temperature is 18. The nuclear power plant operator training device of claim 17, wherein the nuclear power plant operator training device is heated to maintain the nuclear power plant operator training device. 19. Nuclear power plant four operator training equipment 20 according to claim 17, characterized in that it includes a device that simulates leakage in the coolant system of the training equipment, which includes a plurality of thermocouples, each of which A patent claim characterized in that the thermocouple is mounted at a distance so as to firmly contact the heating element, and the mounting position is such that it can detect temperatures at different depths of the water in the simulated nuclear reactor. The nuclear power plant operator training device according to item 17. 21. Claim 17, characterized in that the steam generator includes a device that selectively guides water pressurized to a pressure higher than atmospheric pressure to the outside of the heat receiving tube of the heat exchanger. The nuclear power generating equipment operator training device described. 22. A device capable of pumping water from the water supply tank to the simulated nuclear reactor to substantially maintain the operating pressure of the water in the training device when the pressurizer is not operably coupled to the training device. A nuclear power plant operator training device according to claim 17, characterized in that it has the following. 23. A device for detecting the pressure of water in the simulated nuclear reactor;
a device for sending water from the water supply tank to the simulated nuclear reactor using a pump, and the water feeding device starts operating when the pressure detected by the pressure detection device decreases to at least a preset low pressure value; 18. The nuclear power plant operator training device according to claim 17, wherein the device stops operating when the pressure increases to a preset high pressure level. 24. The nuclear power plant operator training device according to claim 23, wherein the pressure detection device is configured to be activated or deactivated by a switch controlled by a removable key. .