KR100456499B1 - A Pressurized Water Reactor PWR2000 - Google Patents

Abstract

The present invention relates to a super-large pressurized water reactor PWR2000, in particular three cooling units are installed around the reactor, each cooling unit is composed of one steam generator and a pair of coolant pumps and associated piping (hot and cold). By applying a pressurizer to a high temperature tube of one cooling device, it is possible to produce a large-scale electric output of 2000MWe, and relates to a super-large pressurized water reactor PWR2000 which is intended to further improve economics and safety. To this end, in the pressurized water reactor, the coolant of the reactor is injected into the steam generator through the hot tube, and at the same time, the amount of coolant and the pressure of the coolant are adjusted by the pressurizer connected to the hot tube, and a pair of coolant pumps connected to the steam generator A first cooling unit for injecting coolant into the reactor; A pair of second coolers for injecting coolant of the reactor into a steam generator through a high temperature tube and injecting coolant into the reactor by a pair of coolant pumps connected to the steam generator; It characterized in that it comprises a plurality of safety injection section for filling and refilling the safety injection coolant in the reactor through the coolant pump and the low temperature pipe connected to the reactor.

Description

A large pressurized water reactor PPR2000 {A Pressurized Water Reactor PWR2000}

The present invention relates to a PWR2000, a super-large pressurized water reactor, and more specifically, three cooling devices are installed around the nuclear reactor. Each cooling device includes one steam generator and one pair of coolant pumps and associated pipes (high temperature pipe and low temperature pipe). It is composed of), and it is related to the PWR2000 by the ultra-large pressurized water reactor to improve the economics and safety by applying the pressurizer to the high-temperature tube of one cooling device to produce a large-scale electric output of 2000MWe.

1 is a configuration diagram showing a conventional pressurized water passage, and FIG. 2 is a configuration diagram showing another conventional pressurized water passage. 1 and 2, one steam generator 120 and one or two coolant pumps 160 are provided in one cooling device 400 installed around the reactor 10.

In addition, by installing one pressurizer 140 in the other cooling device 400, the amount of coolant and the pressure of the coolant are adjusted through the high temperature tube 20 connecting the steam generator 120 and the reactor 10. do.

Such a conventional pressurized water reactor (PWR) type can be largely classified into an evolution type and a passive type.

The improved type is designed to improve the design of the part while using the existing light-water reactor design almost as it is, and focuses on improving the reliability of the system and equipment and improving the connection design.

The passive type employs proven techniques in existing light water reactors, but relies on passive means of gravity, pressure and natural circulation rather than active devices requiring external power supply.

Therefore, there are various types of improved pressurized water reactors, such as System 80+ developed by ABB-CE in the US and APWR jointly developed by Westinghouse and Japanese companies, and are pursuing a large capacity of about 1300 MWe.

On the other hand, the passive pressurized water reactor applies the design concept of AP600, which is mainly developed by Westinghouse, but pursues the SPWR, 900-1000 MWe-type passive pressurized water reactor, which increases the number of cooling devices from two to three. have.

Accordingly, in view of the safety and power productivity of the conventional pressurized water reactor, a problem arises in that the maximum electric capacity does not remain at a level that cannot be increased at the current level of 1300 MWe.

The present invention is to solve the above problems, the object of the present invention, three cooling devices are installed around the nuclear reactor, each one of the steam generator and one pair of coolant pump and associated piping (high temperature) Tube and low temperature tube), and the high temperature tube of one cooling system is connected to pressurizer to produce 2000 MWe-class large-scale electric output. To provide.

In a configuration for achieving the above object, in the pressurized water reactor, the coolant of the reactor 10 is injected into the steam generator 120 through the hot tube 20, and at the same time, the pressurizer 140 connected to the hot tube 20 A first cooling unit (100) for adjusting a stock amount and a pressure of the coolant and injecting coolant into the reactor (10) by a pair of coolant pumps (160) connected to the steam generator (120); The coolant of the reactor 10 is injected into the steam generator 120 through the hot tube 20, and the coolant is injected into the reactor 10 by a pair of coolant pumps 160 connected to the steam generator 120. A pair of second cooling units 200; Through the coolant pump 160 and the low temperature pipe 50 connected to the reactor 10, a plurality of safety injection unit 300 for filling and refilling the safety injection coolant to the reactor 10, characterized in that it comprises It is achieved by PWR2000 with a very large pressurized water reactor.

Here, it is preferable that two safety injection units 300 are connected to the first cooling unit 100 and the pair of second cooling units 200, respectively.

The first cooling unit 100 includes a steam generator 120 through which coolant discharged from the reactor 10 is injected through the high temperature tube 20; A pressurizer 140 for adjusting a stock amount and a pressure of the coolant through a pressurized connection pipe 30 connected to the high temperature pipe 20; It is preferable to include a pair of coolant pumps 160 for injecting coolant into the reactor 10 through the low temperature pipe 50 connected to the steam generator 120.

The second cooling unit 200 includes a steam generator 120 through which coolant discharged from the reactor 10 is injected through the high temperature tube 20; It is preferable to include a pair of coolant pumps 160 for injecting coolant into the reactor 10 through the low temperature pipe 50 connected to the steam generator 120.

And, the safety injection unit 300, the safety injection pump 320 for continuously filling the coolant to the reactor 10 through the low temperature pipe (50); It is preferable that the accumulator 340 for refilling the coolant to the reactor 10 through the low temperature pipe 50 in an emergency.

When the coolant of the reactor 10 fails to infiltrate the reactor core 40, the safety injection unit 300 replenishes and refills the coolant to the reactor 10 through the low temperature pipe 50. It is preferable.

In addition, the reactor (10), the reactor core (40) for generating nuclear fission is located at the inner bottom of the reactor (10); It is preferable to include the furnace measurement nozzle 60 which is connected to the reactor core 40 and protrudes out of the reactor 10 by a predetermined height.

Here, the height of the reactor core 40 is preferably 4m to 4.5m.

In addition, it is most preferable that one of the first cooling unit 100 and two of the second cooling unit 200 having the safety injection unit 300 outputs a capacitance of 2000 MWe.

Other objects, specific advantages and novel features of the invention will become more apparent from the following detailed description and the preferred embodiments associated with the accompanying drawings.

1 is a configuration diagram showing a conventional pressurized water reactor,

2 is a configuration diagram showing another conventional pressurized water passage;

3 is a configuration diagram showing a super-large pressure water reactor PWR2000 according to the present invention;

4 is a front sectional view showing the nuclear reactor shown in FIG.

<Description of the symbols for the main parts of the drawings>

10 reactor 20 heat tube

30: pressurized connector 40: reactor core

50: low temperature pipe 60: furnace measurement nozzle

100: first cooling unit 120: steam generator

140: pressurizer 160: coolant pump

200: second cooling unit 300: safety injection unit

320: safety injection pump 340: accumulator

400: chiller

Hereinafter, exemplary embodiments of the present invention will be described in detail with reference to the accompanying drawings.

Figure 3 is a block diagram showing a super-large pressure water reactor PWR2000 according to the present invention. As shown in FIG. 3, one first cooling unit 100 and two second cooling units 200, which are installed around the reactor 10, are provided with two safety injection units 300, respectively. . In addition, the pressurizer 140 for adjusting the stock amount and the pressure of the coolant is connected to the first high temperature tube 20a of the first cooling unit 100 through the pressure connecting tube 30.

The first cooling unit 100 is a pressurizer connected to the first high temperature tube 20a as the coolant heated from the reactor 10 is injected into the first steam generator 120a through the first high temperature tube 20a. 140 adjusts the coolant inventory and the pressure of the reactor (10). In addition, the pair of first coolant pumps 160a connected to the steam generator 120a allows the coolant to be injected into the reactor 10.

Here, the safety injection unit 300 is connected to the first low temperature pipe (50a) is composed of a safety injection pump 320 and the accumulator 340, the safety injection pump 320 is a coolant to continuously cool the tube Filled with 50a, the accumulator 340 refills the reactor 10 through the cold tube 50a in an emergency when the coolant of the cold tube 50a is insufficient.

The second cooling unit 200 is different from the point in which the pressurizer 140 provided in the first cooling unit 100 is not configured, and the remaining second steam generator 120b and a pair of second coolant pumps ( 160b), the second high temperature tube 20b, the second low temperature tube 50b, and the safety injection part 300 are installed around the reactor 10 in the same state.

That is, the first cooling unit 100 and the second cooling unit 200 are first connected to the first and second steam generators 120a and 120b and the first and second coolant pumps 160a and 160b. And second low temperature tubes 50a and 50b and first and second high temperature tubes 20a and 20b, one pressurizer 140 in the first high temperature tube 20a of the first cooling unit 100. ) To control coolant inventory and pressure.

Here, the coolant inlet temperature of the reactor 10 coolant system is about 285 ° C to 290 ° C, and the coolant outlet temperature is about 325 ° C to 330 ° C. The water supply temperatures of the first and second steam generators 120a and 120b are about 230 ° C., and the steam pressure and temperature are about 7 MPa and about 280 ° C. to 300 ° C.

The three steam generators 120a and 120b each have a vertical U-tubular shape and are designed to have a total heat transfer area of about 15,000 m 2 with the number of Korean next-generation reactor steam generator tubes (not shown) being about 12,000 to 13,000. .

Accordingly, the first cooling unit 100 and the second cooling unit 200 adopt a CE reactor form, which is a prototype of the Korean next-generation reactor, and installs two coolant pumps 160 for one cooling device. By applying the two coolers to the three coolers as above, one coolant pump 160 may be responsible for the flow rate of about 5500 kg / sec.

The safety injection unit 300 is composed of six trains, one safety injection pump 320 and the accumulator 340 is connected to each train. Here, the safety injection pump 320 takes the coolant from the nuclear fuel reloading cavity located at the bottom of the containment container and fills the coolant with each of the low temperature pipes 50a and 50b.

And, the accumulator 340 is connected to each of the coolant low temperature pipe (50a, 50b), when the coolant is insufficient to refill the coolant in the reactor 10 through the low temperature pipe (50a, 50b).

4 is a front sectional view showing the nuclear reactor shown in FIG. As shown in FIG. 4, the reactor core 40 is positioned at the lower end of the reactor 10, and the in-vehicle measurement nozzle 60 is led out of the reactor 10 above the reactor core 40.

The average power density of the reactor core 40 is about 180 W / cm to 185 W / cm, which is similar to that of the Korean next generation reactor core. The height of the reactor core 40 is about 4m to 4.5m higher than that of the Korean next-generation reactor core.

Therefore, the number of fuel assemblies should be comprised between 290 and 340 to produce 2000 MWe of electrical output. In addition, a reflector (not shown) may be provided outside the reactor core 40 to minimize neutron loss and to minimize neutron irradiation on the reactor vessel wall to increase reactor vessel life.

As described above, according to the ultra-large pressurized water reactor PWR2000 according to the present invention, a large-capacity electricity is generated by using a steam generator, a coolant pump, a high temperature tube and a low temperature tube, and a pressurizer composed of three cooling apparatuses symmetrically around a nuclear reactor. I want to get.

The PWR2000 of the ultra-large pressurized water reactor according to the present invention combines three cooling devices and the design of the next-generation reactor in Korea, and has a feature of further improving the safety of the pressurized water reactor and producing a large capacity of 2000 MWe.

Although the invention has been described in connection with the preferred embodiments mentioned above, other various modifications and variations may be made without departing from the spirit and scope of the invention. Accordingly, it is intended that the appended claims cover such modifications and variations as fall within the true scope of the invention.

Claims (9)

It is composed of a reactor core 40 having a height of 4m to 4.5m and a nuclear fission reaction located in the inner bottom, and the furnace measuring nozzle 60 connected to the reactor core 40 and protrudes outside by a predetermined height. A relatively central cylindrical reactor (10); The first steam generator 120a connected to the hot tube 20a and the pressure connecting tube connected to the hot tube 20a to allow the coolant discharged from the reactor 10 to be injected through the first high temperature tube 20a. A pair of agents for injecting the coolant into the reactor (10) through the pressurizer 140 to adjust the inventory amount and pressure of the coolant through the 30 and the first low temperature pipe (50a) connected to the steam generator (120a) A first cooling unit 100 including a coolant pump 160a; A second steam generator 120b connected to the hot tube 20b and a second low temperature connected to the steam generator 120b such that the coolant discharged from the reactor 10 is injected through the second high temperature tube 20b. In a pressurized water reactor consisting of a pair of second cooling units 200 including a pair of second coolant pumps 160b for injecting coolant into the reactor 10 through a pipe 50b, When the coolant of the reactor 10 fails to submerge the core 40, the pair (two) first coolant pumps 160a and the two pairs (four) second coolant pumps 160b and the reactor ( 10 to fill and refill the safety injection coolant to the reactor 10 through a pair of (two) first low temperature pipes 50a and two pairs of (4) second low temperature tubes 50b. Safety injection pump 320 for filling a total of six coolants, one in each of the three pairs (total six) of the low temperature pipes (50a, 50b) connected to the first cooling unit 100 and the pair of second cooling unit 200 and PWR2000 ultra-large pressurized water reactor further comprising a; safety injection unit 300 is connected to the coolant emergency recharge accumulator 340 is connected. delete delete delete delete delete delete delete delete