KR102046537B1 - Small modular reactor system and the method of rapid reaching to begining critical condition using it - Google Patents

Abstract

The present invention relates to an integral reactor system which can rapidly reach a threshold condition at the initial stage of the operation since a heating means is provided outside the reactor to enable smooth convection of a primary coolant inside the reactor without obstacles. The present invention consists of a reactor vessel (11), a nuclear fuel assembly (101), a core (12), a core support barrel (19), a riser (13), a steam generator (17), a pressurizer (not shown), and a residual heat removal system (20) to remove the residual heat of a secondary coolant during emergency operation in which the secondary coolant has to be cooled rapidly. The residual heat removal system (20) includes a cold heat and thermal heat supply unit (27), which is a cycle device providing both cold and thermal heat, to remove the residual heat of the secondary coolant by receiving cold heat from the cold heat and thermal heat supply unit (27) during the emergency cooling situation of the reactor and to heat the secondary coolant by receiving the thermal heat from the cold heat and thermal heat supply unit (27) during the initial derive of the reactor, thereby increasing the temperature of the primary coolant inside the reactor to the threshold condition temperature. Accordingly the present invention can avoid interference with occupied space for surrounding facilities and significant additional costs since there is no heater acting as an obstacle to the flow of the primary coolant inside the reactor and no separate heater is also installed outside the reactor; and can rapidly reach a threshold condition temperature at the initial stage of the operation of the reactor by using existing facilities.

Description

Small modular reactor system and the method of rapid reaching to begining critical condition using it}

The present invention relates to a small integrated reactor system and a method for rapidly reaching the initial critical condition of an integrated reactor using the same. In particular, a heating means is provided outside the reactor, so that the primary coolant inside the reactor can be convection smoothly without obstacles, thereby critically initiating the operation. An integrated reactor system capable of quickly reaching conditions and a method for rapidly reaching initial critical conditions of an integrated reactor using the same.

The main supply market for nuclear power in the world has been formed around large-capacity reactors. Since the 2000s, however, efforts to develop small and medium-sized nuclear reactors, which are suitable for non-power generation, such as heat merger, seawater desalination energy sources, district heating, and ship-propelled power sources, have been increasing worldwide. In addition, interest and demand for small and medium-sized nuclear reactors are increasing, especially in developing countries with distributed power generation areas, small power grid capacity, or water shortage countries considering seawater desalination using nuclear power. In addition, due to the financial crisis, the difficulty of financing due to the rapid increase in the construction cost of large nuclear power plants, and the increase in investment risk, the modular integrated small and medium-sized reactor (SMR), which is relatively inexpensive in construction cost, short in air, and can be built to meet small demand Increasingly, interest in small modular reactors is growing.

As the unitary reactor is an integral unit, the evaporator is installed inside the reactor vessel. Outside the reactor, when the behavior of the primary coolant loses its stability, the secondary coolant is urgently removed from the primary coolant and the secondary coolant that exchanges heat with the primary coolant, thereby rapidly reducing the abnormal high temperature of the primary coolant on the secondary coolant conduit. Residual heat removal system is installed.

In addition, the integrated reactor is provided with a heater for raising the temperature of the primary coolant to the critical condition temperature in the initial startup of the reactor. However, the heater must be installed on the natural circulation passage of the primary coolant so that the entire amount of the primary coolant is quickly heated while passing through the heater, but the heater is installed in the natural circulation passage of the primary coolant. There is a problem that it is difficult to reach the critical condition because it acts as an obstacle to the natural circulation flow formed by the density difference.

When the primary coolant heater is installed outside, there is a problem that the installation cost is too high compared to the production power of the conventional large commercial nuclear power plant because the interference with the surrounding facilities and additional costs are required.

Therefore, there is a need for a technology that can increase the primary coolant temperature during the initial start-up of an integrated reactor by utilizing existing facilities without installing a heater inside the reactor and installing a separate heater outside the reactor.

Registered Patent Publication No. 10-1261518 (Notification Date: May 06, 2013)

Therefore, the present invention prevents a heater that acts as an obstacle to the flow of the primary coolant inside the reactor and does not have a separate heater installed outside the reactor, thereby preventing the problem of interference with the occupied space of the surrounding facilities and a considerable additional cost. In the meantime, the present invention provides an integrated reactor capable of rapidly reaching the critical condition temperature during the initial operation of the reactor using an existing facility, and a method for rapidly reaching the initial critical condition of the integrated reactor system using the same.

An integrated reactor system according to the present invention for achieving this object is a nuclear fuel assembly 101 made of a reactor vessel (11), a fuel rod bundle embedded in the reactor vessel (11), loaded with a pellet-type nuclear fuel, and the nuclear fuel The core assembly 12 is seated, the core 12 in which the nuclear fission reaction proceeds, and the core support barrel 19, which is a structure that is enclosed in the reactor vessel 11 and surrounds the lower portion of the nuclear fuel assembly 101 in the form of a cylinder. And a riser formed between an inner circumferential surface of the core support barrel 19 and an outer circumferential surface of the nuclear fuel assembly 101 so that a primary coolant filled in the reactor vessel 11 is heated in the core 12 to rise upward. (13) and an inlet and outlet formed between the outer circumferential surface of the core support barrel 19 and the inner circumferential surface of the reactor vessel 11, through which the primary coolant filled in the reactor vessel 11 can pass, and 2 inside car A heat exchange tube through which coolant flows is installed, and heat exchange is performed in a state in which the primary coolant heated in the core 12 is isolated from the secondary coolant, and thermal energy of the primary coolant is transferred to the secondary coolant to vaporize the secondary coolant. The steam generator 17 and the reactor vessel 11, which is manufactured to be installed on the nuclear fuel assembly 101, are installed above the reactor assembly 11 to regulate the pressure inside the reactor so that the primary coolant is stably heated in the core 12 without a sudden phase change. A pressurizer (not shown) for compensating for volume change of the primary coolant so as to be convection, and a secondary coolant for connecting a turbine installed inside the reactor vessel 11 and outside the reactor vessel 11, The residual heat removal system 20 is configured to remove residual heat of the secondary coolant during emergency operation in which emergency cooling of the secondary coolant is urgently performed. Connected with the cold and cold heat supply unit 27, the cold heat is supplied from the cold heat supply unit 27 in the emergency cooling situation of the reactor to remove the residual heat of the secondary coolant, and the cold heat supply unit 27 during the initial start-up of the reactor The heat is supplied from the secondary coolant to heat the primary coolant temperature inside the reactor to the critical condition temperature.

Here, the cold and hot heat supply unit 27 is preferably part of the heat sink tank 271, the heat sink tank 271, the secondary coolant extraction pipe flowing secondary coolant therein, and the heat sink tank 271 As a pipe embedded in the heat sink, the coolant heat transfer unit 2711 for exchanging heat with the secondary coolant extraction tube as the refrigerant flows therein, and the compressor 274 and the condensation unit connected to the coolant heat transfer unit 2711 and the refrigerant pipe in turn. 272) and an expansion valve 273, in which the refrigerant flowing along the refrigerant pipe in the emergency cooling situation is evaporated inside the cold / heat heat transfer unit 2711 to transfer the cold heat to the secondary coolant extraction pipe to remove heat of the secondary coolant. In addition, the auxiliary heat evaporator 275 is further installed in the cold / hot heat supply unit 27, and during initial startup of the reactor, the refrigerant flowing along the refrigerant pipe is evaporated from the auxiliary evaporator 275 and then passed through the compressor 274. By condensing in the cold / hot heat transfer unit 2711, the secondary coolant is heated by transferring heat from the refrigerant to the secondary coolant extraction tube.

In this case, the cold heat supply unit 27 is preferably branched from a refrigerant pipe connecting the expansion valve 273 and the cold heat transfer unit 2711 to the refrigerant pipe connecting the cold and hot heat transfer unit 2711 and the compressor 274. Branched from a first bypass pipe 277-1 to be connected and a refrigerant pipe connecting the condensation unit 272 and the compressor 274 to a refrigerant pipe connecting the compressor 274 and the cold / hot heat transfer unit 2711. A refrigerant branched from the second bypass pipe 277-2 to be connected and the refrigerant pipe connecting the condensation unit 272 and the expansion valve 273 to connect the expansion valve 273 and the cold / hot heat transfer unit 2711. A third bypass pipe 277-3 connected to the pipe is installed, and the first bypass pipe 277-1 is installed to pass through the auxiliary evaporator 275 to connect the first bypass pipe 277-1. The refrigerant passing through is heated by the auxiliary evaporator 275 to be evaporated, and then passed through the compressor 274, and then the second bypass pipe ( 277-2) flows into the cold / hot heat transfer unit 2711 and condenses in the cold / hot heat transfer unit 2711 to heat the secondary coolant, and then passes through the third bypass pipe 277-3 and then expands the expansion valve 273. The secondary coolant is heated by the cold / hot heat transfer unit 2711 at the initial startup of the reactor to reach the critical condition temperature.

In this case, preferably, the first bypass pipe 277-1 between the point where the first bypass pipe 277-1 branches from the refrigerant pipe and the point where the third bypass pipe 277-3 branches from the refrigerant pipe. ) Branch is formed closer to the expansion valve (273) than the branch point of the third bypass pipe (277-3), the branch and the third bypass point of the first bypass pipe (277-1) Between the points where the pass pipe 277-3 branches, a first shutoff valve 278-1 is provided, and a point at which the first bypass pipe 277-1 is connected to the refrigerant pipe and a second bypass pipe. The point where the second bypass pipe 277-2 is connected to the point where the first bypass pipe 277-1 is connected to the refrigerant pipe among the points where the 277-2 is connected to the refrigerant pipe is connected to the compressor 274. And a second blocking valve 278- between the point at which the first bypass pipe 277-1 is connected to the refrigerant pipe and the point at which the second bypass pipe 277-2 is connected to the refrigerant pipe. 2) Hypothesis And the first and second shut-off valves 278-1 and 278-2 are shut off at the time of initial start-up of the reactor, so that the refrigerant flowing in the cold / hot heat supply part 27 is sequentially expanded to the expansion valve 273 and the auxiliary. The evaporator 275, the compressor 274, and the cold / hot heat transfer unit 2711 flow in and circulate.

On the other hand, the method for rapidly reaching the initial critical condition of the integrated reactor system using the integrated reactor, the refrigerant pipe connecting the condensation unit 272 and the expansion valve and the compressor 274 in the initial starting state of the reactor, respectively; Closing the first and second shutoff valves 278-1 and 278-2, opening the first to third bypass pipes 277-1, 277-2 and 277-3, and the compressor 274. And the auxiliary evaporator 275 are circulated to sequentially flow the refrigerant to the expansion valve 273, the auxiliary evaporator 275, the compressor 274, and the cold / hot heat transfer unit 2711.

According to the present invention, the method for rapidly reaching the initial critical condition of the integrated reactor system and the integrated reactor system using the same does not have a heater installed as an obstacle to the flow of the primary coolant inside the reactor, and no separate heater is installed outside the reactor. While the problem of interference with occupied facilities occupied space and significant additional costs is avoided, the existing equipment can be used to quickly reach critical condition temperatures during initial operation of the reactor.

1 is a front cross-sectional view of an integrated reactor in an integrated reactor system in accordance with the present invention;
2 is an overall configuration diagram of an integrated reactor system according to the present invention;
3 is a configuration diagram of the residual heat removal system in FIG.
4 is a view showing a refrigerant flow at the time of residual heat removal start in FIG.
5 is a view showing a refrigerant flow in the process of reaching the initial threshold condition in FIG.

Specific structural or functional descriptions presented in the embodiments of the present invention are only illustrated for the purpose of describing the embodiments according to the inventive concept, and the embodiments according to the inventive concept may be implemented in various forms. In addition, it should not be construed as limited to the embodiments described herein, it should be understood to include all modifications, equivalents, and substitutes included in the spirit and scope of the present invention.

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

As shown in FIG. 2, the integrated reactor system according to the present invention includes a reactor vessel 11, a nuclear fuel assembly 101 embedded in the reactor vessel 11, a core 12, a core support barrel 19, and a riser ( 13), a pressurizer (not shown), a steam generator 17, and the residual heat removal system 20 installed outside the reactor vessel (11).

The reactor vessel 11, also known as the reactor pressure vessel, is a single vessel containing the core 12 and the main equipment. It acts to protect the main equipment inside from external loads and acts as a barrier to prevent the leakage of radioactive materials to the outside during normal operation and accidents.

The fuel assembly 101 is a state in which fuel rods loaded with a pellet-type fuel are woven in a bundle form, and a support grid (not shown), an upper structure (not shown), and a lower structure (not shown) capable of supporting the fuel bundle in an upright form. Not shown) is installed. In addition, the control rod 16 and the guide rod is installed between the nuclear fuel bundle is the same as the case of the general loop reactor.

The core 12 is disposed below the fuel assembly 101, and is a portion where nuclear fission occurs in a normal operation process after reaching a critical condition. The core 12 is provided with a core 12 support structure (not shown), and the core 12 support structure is designed to satisfy the requirement that the control rod 16 can be inserted by maintaining the core 12 shape.

The core support barrel 19 serves to support the fuel assembly 101 from the outside as a structure surrounding the lower portion of the fuel assembly 101 in a cylindrical shape.

The riser 13 is formed between the inner circumferential surface of the core support barrel 19 and the outer circumferential surface of the nuclear fuel assembly 101 so that the primary coolant filled in the reactor vessel 11 may rise to the upper portion by being heated in the core 12. It is a passage.

The steam generator 17 is installed between the outer circumferential surface of the core support barrel 19 and the inner circumferential surface of the reactor vessel 11, and has an inlet and an outlet through which the primary coolant filled in the reactor vessel 11 can pass. The heat exchanger tube through which the secondary coolant flows is installed, and heat exchange is performed in a state in which the primary coolant heated in the core 12 is isolated from the secondary coolant, and thermal energy of the primary coolant is transferred to the secondary coolant to provide the secondary coolant. It acts to vaporize. The primary coolant and the secondary coolant are disconnected from each other so that mass exchange is blocked and only heat exchange takes place. Secondary coolant vaporized in the steam generator 17 is sent to the turbine assembly 80 during normal operation to produce power.

A pressurizer (not shown) is installed on the nuclear fuel assembly 101 inside the reactor vessel 11 to regulate the internal pressure of the reactor vessel 11 so that the primary coolant is stably heated in the core 12 without a sudden phase change. It compensates for the volume change of the primary coolant to allow convection. The pressurizer (not shown) absorbs thermal expansion of the primary coolant during normal operation and is designed to control the pressure of the primary system without a separate spray or heater.

The residual heat removal system 20 is installed in a pipeline through which a secondary system coolant (hereinafter referred to as "secondary coolant") for connecting a turbine installed inside the reactor vessel 11 and the reactor vessel 11 outside, and is a secondary coolant. Eliminate the residual heat of the secondary coolant in emergency operation where it is necessary to cool rapidly. That is, if an accident occurs, the residual heat removal system 20 serves to lower the temperature of the primary system coolant (hereinafter referred to as "primary coolant") from the normal operation temperature to the reload operation temperature. In case of design standard accident, residual heat removal system 20 is operated by driven concept using natural circulation flow through the steam generator 17 secondary side, and if the primary system is cooled and sufficient driving force for natural circulation flow is not secured. The primary system is cooled by forced circulation flow using a maintenance cooling pump (not shown).

The residual heat removal system 20 includes a cold / hot heat supply unit 27 which is a cycle device that provides both cold and warm heat, so that in the emergency cooling situation of the reactor, cold heat is supplied from the cold / hot heat supply unit 27 to recover residual heat of the secondary coolant. In the initial start-up of the reactor, the secondary coolant is heated by receiving warm heat from the cold / hot heat supply unit 27 to raise the primary coolant temperature inside the reactor to the critical condition temperature.

That is, in the present invention, the residual heat removal system 20 which functions to lower the temperature of the primary system coolant is generally used, and performs the action of heating the primary coolant until the critical condition is reached during the initial operation.

More specifically, as shown in FIG. 3, the cold heat supply part 27 includes a heat sink tank 271 and a part of the heat sink tank 271, and a secondary coolant extraction pipe 23 through which a secondary coolant flows. ) And a secondary coolant return tube (24) and a cold / hot heat transfer unit (2711) that exchanges heat with the secondary coolant extraction tube (23) while the refrigerant flows therein as a tube embedded in the heat sink water tank (271); The compressor 274, the condensation unit 272, and the expansion valve 273, which are sequentially connected to the heat transfer unit 2711 and the refrigerant pipe, are included.

The cold / hot heat supply unit 27 transfers cold heat to the secondary coolant extraction pipe 23 while the coolant flowing along the coolant pipe evaporates inside the cool / heat heat transfer unit 2711 in an emergency cooling situation due to an accident during normal operation. The amount of heat is recovered from the coolant.

In addition, the secondary evaporator 275 is further installed in the cold / hot heat supply unit 27. Therefore, in the initial start-up of the reactor, the refrigerant flowing along the refrigerant pipe is evaporated in the auxiliary evaporator 275 and then passed through the compressor 274 and then condensed in the cold / hot heat transfer unit 2711, thereby extracting the secondary coolant extraction pipe from the refrigerant ( 23) the secondary coolant is heated by transferring heat. The heated secondary coolant transfers heat from the steam generator 17 to the primary coolant rather. As a result, even though a separate heater is not installed inside the reactor vessel 11, the primary coolant temperature may reach a critical condition temperature, and the primary coolant is heated inside the reactor vessel 11 while the natural convection required for normal operation may vary in temperature. And it is generated by the difference in density, there is no separate heater structure there is no obstacle to natural convection can be quickly generated convection.

Hereinafter, the configuration and operation of the cold / hot heat supply unit 27 to enable mutually opposite operations such as residual heat removal or secondary coolant heating will be described.

As shown in FIG. 3 and FIG. 4, the cold / hot heat supply unit 27 basically has a cold / hot heat transfer unit 2711, a compressor 274, a condensation unit 272, and an expansion valve 273, which are connected to the refrigerant tube in turn, to form a refrigerant. Is formed in a circulating structure, and the cold / hot heat transfer unit 2711 is installed inside the heat sink water tank 271 and acts as an evaporator to recover the residual heat of the secondary coolant inside the heat sink water tank 271 in an emergency cooling situation. Eliminate the residual heat of the secondary coolant. In FIG. 4, the coolant flow indicated by the thick line represents the coolant flow when the cold / hot heat supply part 27 serves to remove residual heat of the secondary coolant.

Three bypass tubes (277-1, 277-2, 277-3) and the auxiliary evaporator (275) is installed here, the cold and hot heat transfer unit (2711) installed inside the heat sink tank 271 acts as a condenser, not an evaporator, emergency cooling Contrary to the situation, heat is supplied to the secondary coolant.

The three bypass tubes 277-1, 277-2, and 277-3 include the first bypass tube 277-1, the second bypass tube 277-2, and the third, as shown in FIGS. Bypass tube 277-3.

The first bypass pipe 277-1 branches from the refrigerant pipe connecting the expansion valve 273 and the cold / hot heat transfer unit 2711 to be connected to the refrigerant pipe connecting the cold / hot heat transfer unit 2711 and the compressor 274. It is a tube.

The second bypass pipe 277-2 branches from the refrigerant pipe connecting the condensation unit 272 and the compressor 274, and is connected to the refrigerant pipe connecting the compressor 274 and the cold / hot heat transfer unit 2711.

The third bypass pipe 277-3 is branched from the refrigerant pipe connecting the condensation unit 272 and the expansion valve 273 to be connected to the refrigerant pipe connecting the expansion valve 273 and the cold / hot heat transfer unit 2711. .

The auxiliary evaporator 275 is installed in the first bypass pipe 277-1 to vaporize the refrigerant passing through the first bypass pipe 277-1. In this case, a boiler 276 for supplying heat to the auxiliary evaporator 275 may be further installed.

As shown in FIG. 3, the branch point of the first bypass tube 277-1 is a1, the connection point of the first bypass tube 277-1 is a2, and the branch point of the second bypass tube 277-2 is a3, when the connection point of the second bypass pipe 277-2 is a4, the branch point of the third bypass pipe 277-3 is a5, and the connection point of the third bypass pipe 277-3 is a6, When the a1 position is closer to the expansion valve 273 than a5, and a2 is closer to the compressor 274 than a4, the flow path and the flow direction of the refrigerant are formed in the direction of the arrow along the thick line shown in FIG.

For reference, the 'branch point' is the point where the refrigerant enters the bypass pipes 277-1, 277-2, and 277-3, and the 'junction point' is the point where the refrigerant leaves the bypass pipes 277-1, 277-2 and 277-3.

When the refrigerant flows in the direction of the thick line and the arrow shown in FIG. 5, the refrigerant enters the auxiliary evaporator 275 through the expansion valve 273 and a1 and evaporates, and the evaporated refrigerant passes through the a2 compressor 274. After passing through, passing through the second bypass pipe (277-2) through a3 passes through the cold and hot heat transfer unit (2711), the refrigerant passing through the cold and hot heat transfer unit (2711) while passing through a5. After passing through the third bypass pipe 277-3, a circulation path passing through the a6 and passing through the expansion valve 273 is formed again.

At this time, in order for the refrigerant to flow in the direction of the arrow along the path of the thick line shown in FIG. 5, the refrigerant is directed only in the designated direction at the point where the first to third bypass pipes 277-1, 277-2, and 277-3 are joined. Valves that make it flow need to be installed. However, specific positions and types of the valves shown in FIGS. 3 to 5 are just examples, and specific types and installation positions of the valves may be changed if the flow of the refrigerant is maintained in the thick line of FIG. 5.

The valves shown in the embodiments of FIGS. 3 to 5 include first to fourth blocking valves 278-1, 278-2, 278-3, 278-4, and first to third bypasses installed in a path indicated by the thick line of FIG. 4. First to sixth initial opening valves 279-1, 279-2, 279-3, 279-4, 279-5, and 279-6 provided near both ends of the pipes 277-1, 277-2, and 277-3. For reference, the term 'initial opening valve' is the first to sixth opening valve (279-1,279-2,279-3,279-4,279-5,279-6) all rapidly cool the temperature of the primary coolant in the initial operation of the reactor It is a fixed name in the sense of valves that are opened to reach.

The refrigerant flow path indicated by thick lines and arrows in FIG. 4 shows the refrigerant flow when a situation in which residual heat of the secondary coolant needs to be removed is generated. At this time, the first to fourth blocking valves 278-1,278-2,278-3,278-4 are all open, and the first to sixth opening valves 279-1,279-2,279-3,279-4,279-5,279-6 are All are blocked. Therefore, the refrigerant is prevented from flowing into each of the bypass tubes 277-1, 277-2, and 277-3, and the refrigerant is largely circulated in the counterclockwise direction.

The coolant flow path indicated by thick lines and arrows in FIG. 5 is a coolant flow path in a cycle in which the cold / hot heat transfer unit 2711 acts as a condenser to raise the primary coolant temperature to the critical temperature at the beginning of the reactor operation.

Here, the first to sixth initial opening valves 279-1, 279-2, 279-3, 279-4, 279-5, and 279-6 are all open, and the first to fourth blocking valves 278-1, 278-2, 278-3, and 278-4 are all open. It is blocked. Therefore, the refrigerant condenses in the cold / hot heat transfer unit 2711 and transfers heat to the secondary coolant so that the heat is finally transferred from the steam generator 17 to the primary coolant, and the heated primary coolant separates the flow from the inside. Since there is no heater, the critical condition can be reached quickly due to the density difference smoothly generated by the temperature difference.

On the other hand, the method for rapidly reaching the initial critical condition of the integrated reactor using the integrated reactor system according to the present invention is to shut off the refrigerant pipe connecting the condensation unit 272 to the expansion valve and the compressor 274 in the initial starting state of the reactor, respectively. Closing the first and second shut-off valves 278-1, 278-2, opening the first to third bypass tubes 277-1, 277-2, 277-3, and a condenser and an auxiliary evaporator. By operating 275, the refrigerant is circulated in order to flow to the expansion valve 273, the auxiliary evaporator 275, the compressor 274, and the cold / hot heat transfer unit 2711.

This initial critical condition rapid approach method overlaps with the description of the integrated reactor system described above, so the detailed description thereof will be omitted.

The present invention described above is not limited to the above-described embodiment and the accompanying drawings, and various substitutions, modifications, and changes are possible within the scope without departing from the technical spirit of the present invention. It will be evident to those who have knowledge of.

10 integrated reactor 11: reactor vessel
12: Core 13: Riser
15: upper header
16: control rod 17: steam generator
18: lower header 19: core support barrel
20: residual heat removal system 21: steam supply pipe
22: recovery pipe 23: secondary coolant extraction pipe
24: secondary coolant return tube 25: heat exchange tube
27: cold and hot heat supply unit 30: reload tank
40: safety injection system 50: stop cooling system
60: chemical and volume control system 70: coolant pump
80 turbine assembly 101 fuel assembly
271: heat sink tank 272: condensation unit
273 expansion valve 274 compressor
275: auxiliary evaporator 276: boiler
277-1: 1st bypass pipe 277-2: 2nd bypass pipe
277-3: 3rd bypass pipe 278-1: 1st shutoff valve
278-2: 2nd shutoff valve 278-3: 3rd shutoff valve
278-4: 4th shutoff valve 279-1: 1st initial open valve
279-2: 2nd initial open valve 279-3: 3rd initial open valve
279-4: fourth initial open valve 279-5: fifth initial open valve
279-6: 6th initial release valve 2711: Cold and heat transfer unit

Claims (5)

A reactor vessel 11;
A nuclear fuel assembly (101) built into the reactor vessel (11) and comprising a fuel rod bundle loaded with a pellet-type nuclear fuel;
A core 12 on which the nuclear fuel assembly 101 is seated and in which a nuclear fission reaction proceeds;
A core support barrel (19) embedded in the reactor vessel (11), which is a structure surrounding the lower portion of the nuclear fuel assembly (101) in a cylindrical shape;
A riser formed between an inner circumferential surface of the core support barrel 19 and an outer circumferential surface of the nuclear fuel assembly 101, and a primary coolant filled in the reactor vessel 11 may be heated in the core 12 to rise upwards. 13);
It is installed between the outer circumferential surface of the core support barrel 19 and the inner circumferential surface of the reactor vessel 11, the inlet and outlet openings through which the primary coolant filled in the reactor vessel 11 can pass are formed, and inside the heat exchanger through which the secondary coolant flows. The pipe is installed, and the heat exchange is performed in a state in which the primary coolant heated in the core 12 is isolated from the secondary coolant, and heat energy of the primary coolant is transferred to the secondary coolant to vaporize the secondary coolant. A generator 17;
Installed in the nuclear fuel assembly 101 inside the reactor vessel 11 to control the internal pressure of the reactor so that the primary coolant in the core 12 can be stably heated and convection without sudden phase change, thereby changing the volume of the primary coolant. Pressurizer to compensate for; And,
Residual heat which is installed in the pipeline through which the secondary coolant flowing between the reactor vessel 11 and the turbine installed outside the reactor vessel 11 flows to remove the residual heat of the secondary coolant during emergency operation in which the secondary coolant has to be cooled rapidly. Removing system 20; consisting of,
The residual heat removal system 20 includes a cold / hot heat supply unit 27 which is a cycle device that provides both cold and warm heat, and receives residual heat of the secondary coolant by receiving cold heat from the cold / hot heat supply unit 27 in an emergency cooling state of the reactor. In the initial start-up of the reactor, the secondary coolant is heated by receiving heat from the cold / hot heat supply unit 27 to raise the primary coolant temperature inside the reactor to a critical condition temperature,
The cold and hot heat supply unit 27 is embedded in the heat sink tank 271, the heat sink tank 271, a part of the heat sink tank 271, the secondary coolant extraction pipe flowing the secondary coolant therein, and the heat sink tank 271 A coolant heat transfer unit 2711 and a coolant heat transfer unit 2711 which are heat exchanged with the secondary coolant extraction tube 23 and the secondary coolant return tube 24 while the refrigerant flows inside the tube are connected to the refrigerant tube in turn. Compressor 274, condensation unit 272, and expansion valve 273, the refrigerant flowing along the refrigerant pipe in the emergency cooling situation is evaporated inside the cold and hot heat transfer unit 2711 to transfer the cold heat to the secondary coolant extraction pipe To remove heat from the secondary coolant,
A secondary evaporator 275 is further installed in the cold / hot heat supply unit 27, and upon initial start-up of the reactor, the refrigerant flowing along the refrigerant pipe is evaporated in the secondary evaporator 275 and then passed through the compressor 274, followed by cold and heat transfer. Condensing in the unit (2711), thereby transferring heat from the refrigerant to the secondary coolant extraction tube to heat the secondary coolant. delete The method of claim 1,
The first via is branched from the refrigerant pipe connecting the expansion valve 273 and the cold / hot heat transfer unit 2711 to the cold / hot heat supply unit 27 and connected to the refrigerant pipe to connect the cold / hot heat transfer unit 2711 and the compressor 274. Pass pipe 277-1,
A second bypass pipe 277-2 branched from a refrigerant pipe connecting the condensation unit 272 and the compressor 274 and connected to a refrigerant pipe connecting the compressor 274 and the cold / hot heat transfer unit 2711;
A third bypass pipe 277-3 branched from the refrigerant pipe connecting the condensation unit 272 and the expansion valve 273 and connected to the refrigerant pipe connecting the expansion valve 273 and the cold / hot heat transfer unit 2711. Is installed,
The first bypass pipe 277-1 is installed to pass through the auxiliary evaporator 275 so that the refrigerant passing through the first bypass pipe 277-1 is heated by the auxiliary evaporator 275 to be evaporated, and then the compressor ( After passing through 274, the secondary coolant is heated by flowing through the second bypass pipe 277-2 to the cold / hot heat transfer unit 2711 and condensed in the cold / hot heat transfer unit 2711, and then the third bypass tube 277. After passing through -3) and entering the expansion valve 273 and circulating again, the secondary coolant is heated by the cold and heat transfer unit 2711 at the initial start-up of the reactor to reach a critical condition temperature. . The method of claim 3,
The first bypass pipe (277-1) branched from the point where the first bypass pipe (277-1) branched from the refrigerant pipe and the third bypass pipe (277-3) branched from the refrigerant pipe The point is formed closer to the expansion valve 273 than the point at which the third bypass pipe 277-3 diverges,
A first blocking valve 278-1 is installed between the branch point of the first bypass pipe 277-1 and the branch point of the third bypass pipe 277-3,
The first bypass pipe 277-1 is connected to the refrigerant pipe between the first bypass pipe 277-1 and the point where the second bypass pipe 277-2 is connected to the refrigerant pipe. The point connected to the compressor 274 is formed closer to the compressor 274 than the point at which the second bypass pipe 277-2 is connected,
A second blocking valve 278-2 is provided between the point where the first bypass pipe 277-1 is connected to the refrigerant pipe and the point at which the second bypass pipe 277-2 is connected to the refrigerant pipe,
In the initial start-up of the reactor, the first and second shut-off valves 278-1 and 278-2 are shut off,
The refrigerant flowing in the cold / hot heat supply (27) is sequentially integrated into the expansion valve (273), the auxiliary evaporator (275), the compressor (274), the cold and hot heat transfer unit (2711). A method for rapidly reaching an initial critical condition of an integrated reactor using the integrated reactor system according to any one of claims 1 or 3 or 4,
Blocking each refrigerant pipe connecting the condensation unit (272) with the expansion valve and the compressor (274) in the initial startup of the reactor;
Shutting off the first and second shut-off valves (278-1, 278-2);
Opening the first to third bypass tubes 277-1, 277-2, and 277-3; And,
By operating the compressor 274 and the auxiliary evaporator 275, circulating the refrigerant flows to the expansion valve 273, the auxiliary evaporator 275, the compressor 274, the cold and hot heat transfer unit (2711) in turn. How to quickly reach the initial critical condition of an integrated reactor system

Images