JPH0469356B2 - - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a test device for performing performance tests on components of a tank-type nuclear reactor, such as a primary circulation pump, an intermediate heat exchanger, and other components.

[Technical background of the invention and its problems]

In a tank-type nuclear reactor, the primary circulation pump, intermediate heat exchanger, and many other components are installed in the reactor vessel, and when testing the performance of these components, it is necessary to test the performance of these components in an actual nuclear reactor plant. It is desirable to create a system similar to that and conduct tests while driving it.

On the other hand, such a test system requires a heating device that does not use nuclear energy. However, it is clear that a heating device that does not use nuclear energy and can obtain an output close to the reactor core output would be extremely large, and if such a heating device is built into a simulated reactor vessel, Then,
The problem is that the simulated container also becomes extremely large.

Furthermore, even if a large-sized simulated container were created and a heating device was installed, the presence of the large-sized heating device would make it difficult to install the various components to be tested inside the simulated container. It is expected that this will happen.

[Purpose of the invention]

The present invention was made based on these circumstances, and its purpose is to enable performance tests of nuclear reactor components without making the simulated vessel particularly large, and to provide a simulated vessel for the reactor components to be tested. An object of the present invention is to provide a component testing device for a tank-type nuclear reactor that can be easily installed.

[Summary of the invention]

In order to achieve the above objectives, the component testing device for a tank-type nuclear reactor according to the present invention includes a simulated vessel that simulates the reactor vessel of a tank-type nuclear reactor, and a high-temperature plenum above and a low-temperature lower part of the simulated vessel. a partition wall that partitions the plenum into a plenum; a shield that blocks the upper opening of the simulated container; a primary heating system that is provided outside the simulated container and heats a primary coolant; A tank inlet pipe that is connected and allows the primary coolant heated by the primary heating system to flow into the high-temperature plenum, and a secondary tank that is supported by the shield and sucks the primary coolant that has flowed into the high-temperature plenum from the tank inlet pipe. an intermediate heat exchanger that exchanges heat with the coolant; a primary circulation pump that is supported by the shield and boosts the pressure of the primary coolant flowing out from the intermediate heat exchanger into the low-temperature plenum; and a discharge port of the primary circulation pump. a tank outlet pipe connected to the tank outlet pipe for supplying the primary coolant pressurized by the primary circulation pump to the primary heating system; and a primary coolant in the low-temperature plenum connected to the tank inlet pipe via a check valve. a natural convection pipe that flows from the tank inlet piping into the high temperature plenum by natural convection; It is equipped with a heating element that heats the primary coolant flowing therethrough.

[Embodiments of the invention]

An embodiment of the present invention will be shown below.

FIG. 1 shows the overall configuration of the test system. Reference numeral 1 is a simulated vessel simulating a reactor vessel of a tank-type nuclear reactor, and its upper opening is closed off by a shielding body 2. Reference numerals 3, 4, and 5 indicate a primary heating system, a secondary heat removal system, and a loop reactor simulation system, respectively.

A partition wall 8 is provided inside the simulated container 1 to partition the inside of the container 1 into an upper high temperature plenum 6 and a lower low temperature plenum 7. A primary circulation pump 9 and an intermediate heat exchanger 10 are supported by the shield 2 and extend through the partition wall 8 into the low-temperature plenum 7. Note that the lower half of the primary circulation pump 9 is surrounded by an outer cylinder 11, and this outer cylinder 11 also passes through the partition wall 8. In addition, one side of the high temperature plenum 6 is a semi-cylindrical hanging body 12.
A core upper mechanism 13 supported by the shield 2 is disposed inside the suspension shell 12. A high-temperature coolant inlet 14 is provided in the partition wall 8 so as to be located below the core upper mechanism 13 . Moreover, a plurality of flow holes 15 are provided in the hanging body 12.

A tank inlet pipe 16 is provided at the bottom of the simulated container 1.
A tank outlet pipe 17 is provided to penetrate the bottom plate of the container 1. And tank inlet pipe 1
One end of the tank 6 is connected to the high temperature coolant inlet 14, and one end of the tank outlet pipe 17 is connected to the discharge port of the primary circulation pump 9.
The other end of 17 is connected to the primary heating system 3. Also, in the middle of the tank inlet piping 16,
As shown in FIGS. 3 and 4, a natural convection pipe 19 opening into the low temperature plenum 7 is connected via a check valve 18. Note that the suction port of the primary circulation pump 9 communicates with the low-temperature plenum 7 through the outer cylinder 11 .

The primary system inlet 10a of the intermediate heat exchanger 10 is located in the high temperature plenum 6, and the primary system outlet 10b is located in the low temperature plenum 7. Further, numerals 20 and 21 are a secondary coolant inflow pipe and a secondary coolant outflow pipe, respectively, and these pipes 2
0 and 21 are intermediate heat exchangers 10 on the upper surface side of the shielding body 2
It is connected to the.

Further, in FIG. 1, reference numeral 22a is an intermediate heat exchanger attachment plug, 22b is a core upper mechanism attachment plug, and 22c is an intermediate heat exchanger attachment plug.
are dummy plugs, and these plugs 22a, 22
b and 22c are both attached to the upper surface of the shielding body 2 with bolts. Also, in the center of the core upper mechanism mounting plug 22b is a heating element mounting plug 23a shown in FIG. 4 or a dummy plug 23 shown in FIG.
Either one of b is attached replaceably. The heating element attachment plug 23a holds a heating element 24 such as an electric heater at its lower end, and when attached to the plug 22b, the lower end holding the heating element 24 is located within the high temperature coolant inlet 14. Further, the lower end of the dummy plug 23b is positioned above the high temperature coolant inlet 14 when it is attached to the plug 22b.

Liquid sodium is contained inside the simulated container 1 as a primary coolant.

The primary heating system 3 is for heating the primary coolant in the simulated container 1, and includes a heater 25.
and a fuel tank 26 that supplies fuel such as LPG to the heater 25. Both ends of the heating pipe 27 in the heater 25 are connected to the tank inlet pipe 16 and the tank outlet pipe 17 via a tank inlet valve 28 and a tank outlet valve 29, respectively.

The configuration of the secondary heat removal system 4 will be explained with reference to FIG. 2.

That is, the reference numeral 30 is a superheater, 31 is an evaporator, and 32 is a secondary circulation pump. The superheater 30 and the evaporator 31 are connected in series to the secondary coolant outflow pipe 21, 31 is connected to the suction port of the secondary circulation pump 32, and the discharge port of the secondary circulation pump 32 is connected to the inflow port of the intermediate heat exchanger 10 via the secondary coolant inflow pipe 20. . Therefore, by operating the secondary system circulation pump 32, the secondary coolant is circulated in the order of the intermediate heat exchanger 10→superheater 30→evaporator 31. Note that a switching valve 33 is inserted in the middle of the secondary coolant inflow pipe 20, and a switching valve 34 and a flow rate adjustment valve 35 are inserted in the middle of the secondary coolant outflow pipe 21.
They are inserted sequentially from the 0 side toward the superheater 30. Further, flow rate regulating valves 37 and 38 are provided in the middle of the pipe 36 connecting the evaporator 31 and the secondary circulation pump 32.
are sequentially inserted from the evaporator 31 side toward the pump 32. An overflow tank 39 is connected to the secondary circulation pump 32 .

An air cooler 40 and a bypass pipe 41 are connected in parallel between the inlet side of the flow rate regulating valve 35 and the outlet side of the flow rate regulating valve 37. Switching valves 42 and 43 are provided on the inlet side of the air cooler 40 and in the middle of the bypass piping 41, respectively.

Further, reference numeral 44 is a water/steam circulation pipe provided via the evaporator 31 and superheater 30,
In the middle of this circulation pipe 44, from the superheater 30 side toward the evaporator 31, there are temperature and pressure reducing devices 45, 46,
A condenser 47, a condensate pump 48, a deaerator 49, a feed water pump 50, and a feed water superheater 51 are inserted in this order.

Further, a cooling water circulation pipe 52 is provided which passes through the condenser 47, and a cooling tower 53 and a cooling water pump 54 are inserted into this pipe 52.

Next, the configuration of the loop type nuclear reactor simulation system 5 will be explained with reference to FIG.

This system 5 simulates a loop type nuclear reactor plant, and 55 is an intermediate heat exchanger, and 56 is a primary circulation pump.

The primary system inlet 57 of the intermediate heat exchanger 55 is connected to the outlet side of the superheater 25 via an inlet valve 58, and the primary system outlet 59 of the intermediate heat exchanger 55 is connected to the primary system circulation via a switching valve 60. It is connected to the suction port of the pump 56. Further, a discharge port of the primary circulation pump 56 is connected to the inlet side of the superheater 25 via an outlet valve 61. An overflow tank 62 is connected to the primary circulation pump 56.

An air cooler 63 and a bypass pipe 64 are connected in parallel between the inlet side of the inlet valve 58 and the outlet side of the switching valve 60. Switching valves 65 and 66 are connected to the inlet and outlet sides of the air cooler 63, respectively, and the bypass piping 64
A switching valve 67 is inserted in the middle.

The inlet side of the air cooler 63 and the outlet side of the tank inlet valve 28 are connected via a switching valve 68. Moreover, between the inlet side of the tank outlet valve 29 and the suction port of the primary system circulation pump 56,
They are connected via a switching valve 69. Further, the inlet side of the inlet valve 58 and the outlet valve 61 are connected via a bypass valve 70.

On the other hand, the secondary cooling pair inflow pipe 71 of the intermediate heat exchanger 55 is connected to the discharge port of the secondary circulation pump 32 of the secondary heat removal system 4 via the switching valve 72 (see FIG. reference). Further, the secondary coolant outflow pipe 73 of the intermediate heat exchanger 55 is connected to the inlet of the superheater 30 of the secondary heat removal system 4 via the switching valve 74 and the flow rate adjustment valve 35.
Further, the outlet side of the switching valve 60 is connected to the suction port of the secondary circulation pump 32 of the secondary heat removal system 4 via the switching valve 75 and the flow rate adjustment valve 38 (see FIG. 2).

The secondary coolant outlet of the intermediate heat exchanger 55 and the inlet side of the inlet valve 58 are connected via a bypass valve 76 .

With the above configuration, the components of a tank-type nuclear reactor,
For example, primary circulation pump 9, intermediate heat exchanger 1
0, the performance of the partition wall 8, the shield 2, and other components can be tested, and by switching the valves, the performance of the components of the loop reactor can also be tested.

First, performance tests of the components of a tank-type nuclear reactor will be conducted as follows.

The simulated container 1 is equipped with the components to be subjected to a performance test. In this case, the components to be tested are the primary circulation pump 9 and the intermediate heat exchanger 1.
0, when the corresponding component is installed in the simulated container 1, the corresponding component is replaced with the corresponding component and installed in the simulated container 1.

And as shown in FIGS. 1 and 2, the valve 5
8 and 61 are closed, and valves 28, 29, 33, and 34 are opened. In addition, in the figure, the black valves indicate the closed state, and the white valves indicate the open state. In addition, as shown in FIG. 3, the core upper mechanism mounting plug 22b
A dummy plug 23b is attached to the check valve 18, and the check valve 18 is held in a closed state.

Therefore, when the primary circulation pump 9 and the primary heating system 3 are operated, the primary coolant heated by the heater 25 passes through the tank inlet piping 16 and enters the suspension shell 1 of the high temperature plenum 6 from the high temperature coolant inlet 14.
2. Flow into the interior. Then, it flows to the outside of the suspension shell 12 through the flow hole 15, passes through the intermediate heat exchanger 10, and reaches the low-temperature plenum 7. Here, since the secondary coolant is flowing through the intermediate heat exchanger 10 by the secondary circulation pump 32 of the secondary heat removal system 4, heat exchange is performed between the two coolants. The primary coolant in the low-temperature plenum 7 flows out through the tank outlet pipe 17 by the primary circulation pump 9, is heated again by the heater 25, and circulates.

On the other hand, the secondary coolant that has become high in temperature through heat exchange in the intermediate heat exchanger 10 passes through a superheater 30 and an evaporator 31 . And water/steam circulation piping 44
The water in the condenser 4 is superheated and converted into high-temperature steam.
7. The water flowing out from the condenser 47 is degassed by a deaerator 49, heated by a feed water heater 51, and then reaches the evaporator 31 again.

During this operation, performance tests of the components installed in the simulated vessel 1 can be performed under conditions almost identical to the high-output conditions of an actual nuclear reactor plant.

By the way, it is also extremely important to test the performance of nuclear reactor components in the low power state of a nuclear reactor plant, that is, in the natural environment of the coolant inside the reactor. Therefore, it is necessary to simulate the process of transition from a high power state to a low power state and the flow state of the coolant only within the reactor. Therefore, when conducting such a test, as shown in FIG. 4, replace the dummy plug 23b attached to the core upper mechanism attachment plug 22b with the heating element attachment plug 23a, stop the primary heating system 3, Tank inlet valve 28 and tank outlet valve 29 are closed.

Then, the primary coolant whose heat has been removed by the intermediate heat exchanger 10 is transferred to the check valve 1 from the opening of the natural convection pipe 19.
8 into the tank inlet pipe 16, passes through the tank inlet pipe 16, is heated by the heating element 24, and flows out from the high temperature coolant inlet 14 to the high temperature plenum 6,
An environmental path to the intermediate heat exchanger 10 is formed.
Therefore, during this operation, the performance test of the components installed in the simulated vessel 1 can be performed under substantially the same conditions as the low power state of the actual nuclear reactor plant.

Next, the performance test of the components of the loop reactor is as follows:
Similarly, the loop reactor simulation system 5 is equipped with a component to be subjected to a performance test, or replaced with a corresponding component installed in the simulation system 5. Then, as shown in FIGS. 5 and 6, valves 28, 29, 33, and 34 are closed, and valve 5 is closed.
By opening the valves 8 and 61 and operating the primary system circulation pump 56 and the primary system heating system 3, test conditions almost identical to those of an actual nuclear reactor plant can be obtained, and the performance of the predetermined components can be determined under these conditions. Tests can be conducted.

[Effects of the Invention] As detailed above, according to the test system of the present invention, a primary system heating device in place of the reactor core is provided outside the simulated vessel, and low-output heating elements are appropriately installed inside the reactor. By doing so, it is possible to equip the simulated vessel with nuclear reactor components and conduct a performance test without making the simulated vessel particularly large. Furthermore, the work of equipping the simulated vessel with reactor components to be tested can be easily carried out since there is no large heating system in the simulated vessel.

[Brief explanation of the drawing]

The drawings show one embodiment of the present invention. Figure 1 is an overall configuration diagram of the test system showing the state in which performance tests are performed on the components of a tank-type nuclear reactor, and Figure 2 is a diagram of the secondary system removal showing the same state. Thermal system configuration diagram, Figure 3 is a schematic cross-sectional view showing the dummy plug installed state, Figure 4
The figure is a schematic cross-sectional view showing the state in which the heating element attachment plug is installed, and FIG.
FIG. 6 is a configuration diagram of the secondary heat removal system showing the same state. 1... Simulation container, 2... Shielding body, 3... Primary heating system, 4... Secondary heat removal system, 6...
... High temperature plenum, 7 ... Low temperature plenum, 8 ... Partition wall, 9 ... Primary circulation pump, 16 ... Tank inlet piping, 18 ... Check valve, 19 ... Natural convection pipe, 24 ... Heating element .

Claims (1)

[Claims] 1. A simulated vessel that simulates a reactor vessel of a tank-type nuclear reactor, a partition wall that partitions the inside of this simulated vessel into an upper high-temperature plenum and a lower low-temperature plenum, and a shield that closes off the upper opening of the simulated vessel. a primary heating system installed outside the simulated container to heat the primary coolant; and a tank connected at one end to the lower surface of the partition wall and allowing the primary coolant heated by the primary heating system to flow into the high-temperature plenum. an inlet pipe, an intermediate heat exchanger supported by the shield and sucking the primary coolant flowing into the high-temperature plenum from the tank inlet pipe and exchanging heat with the secondary coolant; A primary circulation pump that pressurizes the primary coolant flowing out from the heat exchanger into the low-temperature plenum, and a primary circulation pump that is connected to the discharge port of the primary circulation pump and supplies the primary coolant pressurized by the primary circulation pump to the primary heating system. a natural convection pipe that is connected to the tank inlet pipe via a check valve and causes the primary coolant in the low-temperature plenum to flow from the tank inlet pipe into the high-temperature plenum by natural convection; A heating element supported by the shielding body and heating the primary coolant flowing from the low-temperature plenum into the high-temperature plenum by natural convection through the natural convection pipe and the tank inlet pipe. Tank-type nuclear reactor component test equipment.