KR820000931B1 - Nuclear reactor apparatus - Google Patents

Abstract

A nuclear powered energy generating system is housed within a containment together with certain of its auxiliary components and materials for its operation. The reactor (23) and the containment are supported on a base consisting of a predominantly hollow truss. The truss (55) has an upper and a lower bounding plate, interconnected by a vertical bounding wall. Within the boundary are various other horizontal plates (57) (59) and internal vertical walls (61) (67). These are formed into a rigid structural unit, and form chambers (115) within which some of the auxiliary components and material are housed.

Description

Atomically

1 is a perspective view showing an embodiment of the present invention.

2 is a partial vertical view showing the safety injection system of the device according to the invention.

3A and 3B are vertical sectional views taken along the line III-III of FIGS. 5A and 5B.

4A and 4B are vertical sectional views taken along the line IV-IV of FIGS. 5A and 5B.

5a and 5b are horizontal sectional views taken along the line VV of FIGS. 4a and 4b.

6a and 6b are horizontal cross-sectional views taken along line VI-VI of FIGS. 4a and 4b.

7A and 7B are horizontal sectional views taken along the line VII-VII of FIGS. 4A and 4B.

8A and 8B are horizontal sectional views taken along the line VII-VII of FIGS. 4A and 4B.

9A and 9B are horizontal sectional views taken along the line VII-VII of FIGS. 4A and 4B.

10A and 10B are horizontal sectional views taken along the line VII-VII of FIGS. 4A and 4B.

11A and 11B are horizontal cross-sectional views taken along the line I-XI of FIGS. 4A and 4B.

The present invention relates to power generation, and more particularly, to a power generator whose main energy source is a nuclear reactor.

Reactors usually have reactors in containment vessels of vertical, semi-spherical, cylindrical form of reinforced or pre-compressed concrete. The inlet and outlet passages for the primary coolant extend radially at different angles between the reactor and the steam generator. Usually the coolant is pressurized water at a temperature of about 332 ° C. and a pressure of about 158 Kg per square cm.

Other coolants may be used as the primary and secondary coolants or only one fluid may be used in the boiling water reactor and these other coolants may be used in the reactor without departing from the spirit of the present invention. The steam generator and primary coolant passages are in the containment vessel and are supplied to the turbine outside the secondary coolant containment vessel from the steam generator. Auxiliary devices such as pump devices and various tanks are located in other auxiliary structures outside the containment vessel.

The containment vessel and the reactor are supported on a flat solid foundation, which is formed with a vertical thickness between 274 cm and 1524 cm depending on the earthquake conditions. The containment vessel and the base are sometimes referred to as containment structures. There is a groove in the base, the cross section of which is a key groove, through which the reactor and core pipes extend. In a post tension containment vessel, there is a peripheral chamber that can enter and exit a stress tendon anchorage extending around the vessel just below the foundation. Fuel replacement coolant (usually water) storage tanks, which are normally used to fill spent fuel transfer passages and are used for emergency core cooling in the event of a coolant leak, are installed outside the vessel.

The pumping devices, valves, and electrical switching equipment making up the safety injection system are in an auxiliary structure on the outside of the vessel. There are usually two, three or four safety injection systems for safety, which are two, three or four safety injections that inject coolant at a location remote from the reactor's primary cooling system during operation. There is a system.

Each system is located at the other bottom of the auxiliary bulb, and piping and conductors from each system are guided around the containment vessel around the containment passage area to enter the containment vessel. Inside the containment vessel, the pipes and electricity move around the interior to reach areas connected to the reactor. The sump is also connected to the pump, valve and switching device via a conductor between the inside of the containment vessel and the other bottoms of the auxiliary structure.

An auxiliary structure including the safety injection system, the containment vessel and its pedestal are erected to withstand an earthquake shock. However, the buildings, containment vessels and pedestals at different locations react differently to impacts in the event of an earthquake, and the resulting breakdown of the interconnection between containment vessels and safety injection systems will further weaken the destruction by earthquakes. There is a number.

The cost of safety injection systems, auxiliary structures and components of conventional reactor equipment is expensive. A reasonable estimate of these parts of a typical conventional device with one, two or three safety injection systems based on the 1973 price is $ 15 million for pipes and valves and $ 5 million for auxiliary structures. All costs $ 20 million.

The main object of the present invention is to overcome the above-mentioned difficulties and disadvantages of the prior art, to provide a nuclear power plant at a substantially lower price than the prior art, and to simplify the structure of the safety injection system in the prior art.

To this end, the present invention relates to a containment vessel of a reactor and an auxiliary part and the material of the reactor, the containment vessel having a base for supporting the reactor and the containment vessel, the base being the upper horizontal plate 57 and the lower portion. It has a vertical wall 61,67 between the horizontal plate 59 and this horizontal plate 57,59, and the vertical wall 61,67 and the horizontal plate 57,59 have a compartment 115-119 separated between the vertical wall and the horizontal plate. It forms a structure, and the compartment is characterized by receiving materials necessary for the operation of the auxiliary component 113 and the reactor 23.

The upper and lower slabs or plates are rigid structures with annular and radial walls or metal plates. Slabs are usually reinforced concrete, such as vertical walls or metal plates, and they are trus or foundation-forming components, which are extremely hard and consist of about the same amount of concrete. If the diameter of the circle is larger than that of the container, if the perimeter of the trasit is suitable to extend beyond the container, the container and its depth and internal structure extending into the mold section provide extra support surfaces and supported members and thus Provides pressure and improved stability of the soil.

The sphere is a large range of pupils, which provide a useful internal volume. In this part of the space, a fuel supply coolant storage tank for the safety injection system is appropriately installed.

The machinery and tanks of the auxiliaries are installed in part of the mold volume. Between them there are two, three, four or more electrical devices of the same fluid and safety injection system in parallel. The isolation between these devices is secured by installing each device in its original separate sealing area.

However, all safety injection systems are installed in a rigid base with containers, which makes them more resistant to earthquakes and other disruptive causes. The connectors are also much shorter tubes that reduce the chance of destruction or failure.

The invention can be more readily understood from the accompanying drawings and the description of the following examples.

The apparatus shown in FIG. 1 is a nuclear power plant 21. Specifically, but not limited to the invention, the apparatus 21 whose motive power is 23 with pressurized water is described below. In such a reactor, the coolant is water. The pressurized water reactor usually has a heat output of 3400 megawatts at the reactor output.

The apparatus shown in the figure includes a reactor 23 and a plurality of steam generators 25 and a primary coolant (pressurized water) passage loop 27 between the reactor 23 and each generator 25. Usually there are four loops 27 (figure 9). The primary coolant is driven through the coolant loop 27 by the coolant pump 29. The steam passage 31 circulates secondary fluid and steam through a powered turbine and is located in the turbine structure 33.

The operator crane 35 (FIG. 3) can also adjust the internal parts of the reactor (not shown) during the fueling or maintenance of the reactor. Chain lines 39 (FIG. 9B) and 37 (FIG. 10A) show where the top and bottom of the reactor are moved during this operation. The apparatus also has a recycle heat exchanger 41 (FIGS. 2, 8B and 9), each exchanger connected to a safety injector system that cools the coolant (water) back to the reactor during the coolant spill. .

While control rods are inserted into the reactor core during this event to minimize energy generation, energy is actually generated at about 1% or less. There are also regenerators 43 (Figs. 8, 9 and 10b), pressurizer 45 (Fig. 3b), ventilator 47 (Fig. 11b) and other auxiliary devices.

Reactor 23 and crane 35, steam generator 25 and primary coolant pipe 27, and pump 29, recirculating heat exchanger 41, regenerator 43, pressurizer 45, and ventilator 47 are contained within containment structure 51 (degrees 1, 2, 3 and 4a). have. The structure 51 usually includes a vertical cylindrical upper hemispherical vessel 53 and a generally circular support cavity.

Form 55 is underground and serves as the foundation for Structure 51. Vessel 53 usually has a diameter of about 43 m and a height of about 61 m, and mold 55 is usually about 55 m in diameter and about 11 m deep.

Form 55 includes an upper plate ie upper slab 57 and a lower plate ie lower slab 59 integral with the wall of the container 53. Plates 57 and 59 are connected to a rigid fixture by radial walls 67 and annular walls 61 providing compartments in the mold, so that typically the walls of vessel 53 are about 61 cm thick, about 152.4 cm top plate, about 122 cm bottom. Plate, except the center, has a vertical wall of about 45.7 cm and a radial wall of about 30 cm. Well 69 (1, 2, 3b, 4b, 6a, 7 degrees) is provided by a wall near the plate that extends from the vessel to plate 59 and is usually 152.4 cm thick and has a keyhole cross section with a clump annulus.

The linear part of the keyway is about 91.4 cm thick. On this part, wall 71 is immersed into a closed annular cross section (Figure 7) which immerses it higher into the sealed hexagonal section (Figure 8). In FIGS. 9 and 10, the wall 71 serves as the center of the brick covering the annular wall 73, the transverse wall 74 and the radial wall 75, which are the steam generator 27, the pump 29, the pipe 31, the heat exchanger 41 and the heat exchanger 43. And the compartments that shield other parts of reactor 23. Walls 73,75 and top wall 71 are usually 61 thick.

The wall 71 (first and fourth degrees) in the vessel has a shoulder, or shelf, on which reactor 23 is supported. Flange 77 of reactor 23 rests on this shoulder and the perimeter of the flange is sealed. Within the compartment above the top of reactor 23 is water 79. The crane 35 is placed on the shoulder 81 near the top of the wall 71. The core new ube mechanism 83 (FIG. 3) carrying the cable mechanism extends from the bottom of the reactor through the billows in the wall 71 to the bottom of the mold sphere 55 to pass through the core mechanism chamber 85.

Plates 57 and 59 are formed of reinforced concrete. The wall of the container 55 is pre-compressed by a tendon anchor 91, which passes around the wall and passes through the container wall. The tension device 93 of the tenton anchor 91 is installed in the annular compartment 95 under the peripheral frame of the plate 57. The annular compartment 95 also serves as a passage for management personnel and also serves as a passage for clear air.

The rounded part of compartment 101 in the form of a keyhole (1, 2, 3a, 4, 5, 6 degrees) is generally annular, extending around the well 69 below the coolant passage 27 and serving as a fuel feed coolant storage tank. do. The compartment 101 extends between the upper plate 57 and the lower plate 59 and has a corrosion resistance (stainless steel) lining 103. Lining 103 extends like steel lining 105 (FIG. 2) with lining 105 covering the walls of containment vessel 53.

Linings 103 and 105 are connected to weld 107. The lining 105 usually extends down the plate 57 to a depth of about 30 cm. Chamber 101 has outlet 102 (FIG. 4B) for excessive vapor evacuation. In general, yarn 101 has an inner diameter of 10.36 m, an outer diameter of 24.4 m and a height of 8.23 m. There is about 2,089,768 liters of coolant in compartment 101 as fuel feed coolant at a depth of 7 meters. The amount of coolant in the reactor is small compared to this amount.

Compartment 101 has a number of outlets 109 (2, 4a, 5 degrees). Gravity discharge pipe 111 from outlet 109 discharges coolant to compartment 101 in the event of a coolant leak. Outlet 109 is configured to block the flow of sediment generated by leaking reactor coolant into tank 101. Exhaust pipe 111 is contained in containment vessel 53 buried below the coolant level to minimize the recycling of radioactive vapor (water vapor).

A number of independent safety injection systems 113 (2, 3b, 5, 6, 7 degrees) supply coolant to the reactor from the fuel feed coolant storage tank 101. Each device 113 is arranged in a number of separate compartments 115,117, which extend outward from containment vessel 53 and from the bottom of the annulus of form 55. These devices 113 are easily accessible from the hatch 121 in the annular plate 57 extending out of the containment vessel 53. Compartments 115, 117, and 119 are isolated to reduce the possibility of damage from external or internal missiles or deliberate sabotage, and to prevent one unit from flooding by destroying the coolant line of another unit.

Each safety injection system includes a high head pump 131, a low head pump 133, 135, and a vessel injection pump 2,5 (2, 5 degrees). These pumps 131, 133, 135 are supplied from the fuel supply coolant storage tank 101. Injection pump 135 is supplied with additional material from injection additional tank 136 in compartment 119. The high head pump 131 is the low head pump 133 is usually multiphase vertical. Suitable headlium is provided for removal and replacement. In the individual shielded compartments 115, 117, 119 in the outer annulus of the tool sphere 55 these pumps achieve these objectives. At low compression, the pumps 131, 133 and 135 are connected to the fuel supply coolant storage tank 101 and the device via valve 137 (FIG. 2) is sealed in the water tank 138 by the suction pipe 139. This line 139 is installed in the shallow trench 141 in the plate 59 to ensure uninterrupted work and maintenance of the passageway between the interior and exterior equipment of the toolbox 55.

The high pressure discharge line 145 from the high head pump 131 is connected to the reactor cooling system via valve 147. The high pressure discharge line 149 from the low water pump 133 is connected to the cooling system via the valve 151 and the recirculation heat exchanger 41 to the containment injection system 155 via the valve 157 through the high pressure discharge line 149 from the injection pump 135.

The high pressure discharge lines 145, 149, 153 pass through valves 147, 151, 157 through piping chase 154 (FIG. 3B) and pass through the upper horizontal concrete slab 57 of inlet 55 (FIG. 2) to enter the reactor containment vessel. The running of high energy pipes inside and outside the vessel is shortened by this device. Lines from pumps 131,133,135 in containment 53 are connected to the reactor via control and check valve arrangements as shown in RESAR 41 (not shown).

Power is supplied to the safety device 113 from the device in the seal 161 (3b, 8, 9 degrees) arranged near the safety device, respectively. Each seal 161 has suitable transformers 163 and 165 switchgear safety guidance devices 167 and 169. Each compartment is powered by a diesel unit 170 that can operate when the power supplied by reactor 23 is interrupted.

In an embodiment of the present invention, the fuel change coolant storage tank 101 remains filled with coolant while in reactor operation. When the reactor is shut down for nuclear fuel replacement, the coolant in the fuel replacement coolant storage tank is used for its normal mission to fill the consumable fuel transfer path. According to the invention, the outlet 109 is connected directly to the safety device 113 through the fuel supply coolant tank 101, which in turn re-supply the coolant to the reactor in the event of a coolant leak. The conversion required in the device according to the prior art is unnecessary. The coolant passages 139 are simply compared to those required by the prior art because they only need to pass from each safety device 113 disposed around the tank 101 near the penetration 171 (FIG. 2) in the tank 101. .

The passages 145, 149, 153 are short because they only need to pass from the safety device 113 to the parts of the reactor 23 having the same angular position with respect to the axis of the reactor as safety devices.

Normally the safety pipes or passages are installed from the outlet and the fuel replacement coolant storage tank to the reactor via a vessel to an average of about 143 m in conventional devices and 56.4 m in average in the device according to the invention. This reduction, which is reduced by more than 50%, is due to a simpler safety injection system, which removes the separate suction line from the outlet 109 of the container and the fuel change coolant storage tank 101. Another auxiliary device has a pipe which is reduced by 15% to 30% by the present invention, which transcends the prior art according to a particular device. It is therefore estimated that the present invention saves at least 20% on pipes. This represents about $ 4 million in savings in 1973 dollars.

In this comparison, it can be seen that the price is almost the same as the price of the external fuel supply tank and the inner annular tank 101 lining with basic stainless steel. Many components and equipment installed in the auxiliary structure by conventional techniques are installed in tras 55. Among them are chemical and volume control devices, waste gas handling devices, waste liquid handling devices and steam generator outlets.

Some of the chemical and volume control devices are installed in the mold 55 and some in the simplified structure. The requirements of the device (which are more rigorous by the rapid fuel supply) are to position the volume control tank 181 (Fig. 7b) at a high height (usually about 274 cm above the plate 57) and discharge pump 183 (Fig. 6b) at the lowest height. ) To establish a high suction head that lowers the low gas pressure in the volume control tank 181. The head of the pump increases from about 457 cm to about 1219 cm and the high pressure pipe connected to the exhaust reactor cooling system by the discharge pump is somewhat shortened by the position of the pump and control tank.

The rest of the control and volume control (outside the vessel) are located in a mechanical auxiliary structure (not shown) to locate the mineral ion controllers 185 (figure 5b, 6b) and their filters 187 (figure 4b, 6b). Fix and reduce the parts of the coolant pipes required for the heat exchanger of this unit.

All waste gas handling devices are located within form 55 because they are only large volume radioactive devices with the requirements for proper operation and maintenance. This location provides radiological shielding and missile defense and has the necessary entrances for operation and maintenance. The waste gas handling device includes a quench tank 189 (FIGS. 4b, 5b), a pump recombination device and a compressor (not shown).

It is usually not sufficient to install all waste liquid handling devices within the mold 55 and filter mineral ion removers, evaporators and cylindrical equipment are installed for the operation and maintenance of the apparatus, but it is useful to locate the main radioactive collection tanks in the mold 55. It is practical to use low heights for shielding and gravity drainage. Thus, waste support tank 201 (FIG. 5B) bottom discharge tank 203, laundry and hot water shower tank 209 (FIG. 5A) chemical discharge tanks 211 (FIG. 5B) (refer to their support delivery pumps (not shown)). It is coupled within the sphere.

One of the remaining compartments 221 serves as the house of the radioactive steam generator outlet 223 (FIG. 4a). Heat exchanger 225, pump 227 and surge tank 229 are installed in mold 55 adjacent to the auxiliary structure of the apparatus.

Form 55 has facilities for caretakers, for example, melee passage 231 (Fig. 7b) for tendon anchor 91. There are also annular access passages 233 (figure 5b) and valve passage 234 (figure 5b) for the managers. Above passage 233 is another valve passage 235 (FIG. 6B) and a hot pipe groove 237.

Claims (1)

In the containment vessel structure surrounding the reactor having a base for supporting the reactor and the containment vessel, the base 55 is divided and the upper horizontal plate 57, the lower horizontal plate 59 and the horizontal plates 57 A vertical brick 61, 67 installed between the vertical bricks 61, 67 and the horizontal plates 57, 59, the compartments 115-119 provided between the vertical bricks and the horizontal plates; And a base structure for supporting the container, wherein the compartments contain materials necessary for the operation of the auxiliary part 113 and the gastric furnace 23. Containment structure.

Images