Passive containment air cooling system capable of being used for floating nuclear power platform

Abstract

The invention provides a passive containment air cooling system capable of being used for a floating nuclear power platform. The passive containment air cooling system comprises a containment, a cold air loop, a hot air loop and an air guide plate. The cold air loop comprises a cold air inlet and a cold air annular descending section; the cold air inlet is provided with a first isolating valve for controlling the operation and stop of the passive containment cooling system; the hot air loop comprises a hot air outlet and a hot air annular rising section, and the hot air outlet is provided with a second isolating valve for controlling the operation and stop of the passive containment cooling system; the cold air annular descending section and the hot air annular ascending section are communicated at the bottom of the floating nuclear power platform and are isolated from the upper portion of the floating nuclear power platform through an air guide plate. According to the technical scheme, the heat of the containment can be smoothly exported, the temperature and pressure in the reactor core and the containment are maintained in a normal range, and the integrity of the containment structure is ensured.

Description

Technical Field

[0001] The invention belongs to the technical field of reactor safety systems for surface nuclear power platforms, and in particular relates to a passive containment air cooling system that can be used for floating nuclear power platforms. Background Art

[0002] When the floating nuclear power platform reactor system is operating normally, part of the heat generated by the reactor is released into the containment, causing the temperature and pressure in the containment to slowly rise. When a breach occurs in the floating nuclear power platform reactor system, the high-temperature, high-pressure and highly radioactive coolant ejected from the breach flashes in the containment, and the air in the containment expands rapidly due to the heat. The combined effect of the two will cause the pressure in the containment to rise sharply. Once the pressure in the containment exceeds its designed pressure capacity, an overpressure rupture accident will occur in the containment, causing the leakage of radioactive materials.

[0003] At present, most floating nuclear power platforms use a spray system to cool down and depressurize the containment after an accident. The cooling water sprayed by the spray system will cause irreversible damage to the mechanical and electrical equipment in the containment; the spray pump is extremely dependent on external power supply, and the spray system fails in the event of a power outage; in addition, the spray system cannot cool down and depressurize the containment when the reactor system is operating normally.

[0004] Therefore, how to provide a passive containment air cooling system that can be used for floating nuclear power platforms, so as to achieve smooth heat removal from the containment, maintain the temperature and pressure in the core and containment within normal ranges, and ensure the integrity of the containment structure without relying on external power supply and human intervention during normal operation of the reactor system or after a breach accident, has become a technical problem that needs to be solved urgently. Summary of the invention

[0005] The embodiment of the present invention provides a passive containment air cooling system that can be used for a floating nuclear power platform. During normal operation of the reactor system or after a breach accident, the system can smoothly remove the heat from the containment, maintain the temperature and pressure in the core and the containment within a normal range, and ensure the integrity of the containment structure without relying on an external power supply or human intervention.

[0006] In an embodiment of the present invention, a passive containment air cooling system that can be used for a floating nuclear power platform is provided, comprising: a containment 1, a cold air loop 2, a hot air loop 3 and an air guide plate 4.

[0007] The cold air circuit 2 comprises: a cold air inlet 2-1 and a cold air annular descending section 2-2, wherein the cold air inlet 2-1 is provided with a first isolation valve for controlling the operation and stop of the passive containment cooling system;

[0008] The hot air circuit 3 comprises: a hot air outlet 3-1 and a hot air annular ascending section 3-2, wherein the hot air outlet 3-1 is provided with a second isolation valve for controlling the operation and stop of the passive containment cooling system;

[0009] The cold air annular descending section 2-2 and the hot air annular ascending section 3-2 are connected at the bottom of the floating nuclear power platform and are isolated from the top of the floating nuclear power platform by an air guide plate 4.

[0010] Furthermore, the system comprises:

[0011] Reactor shielding materials are arranged on the containment vessel 1, and reactor heat insulation materials are arranged outside the shell of the cold air loop 2; the shell of the cold air loop 2 and the air guide plate 4 only bear the air circulation function and have no load-bearing function.

[0012] Furthermore, the system comprises:

[0013] When the temperature and pressure in the containment 1 rise to the set values, the first isolation valve arranged at the cold air inlet 2-1 and the second isolation valve arranged at the hot air outlet 3-1 are opened;

[0014] The air in the hot air loop 3 is heated by the containment vessel 1 , and the air density decreases, thereby forming a density difference with the cold air in the cold air loop 2 .

[0015] Furthermore, the system comprises:

[0016] The air density difference in the hot air loop 3 causes a pressure difference, which further drives the hot air in the hot air loop 3 to float from the hot air annular rising section 3-2 to the hot air outlet 3-1, and is discharged from the floating platform into the external atmospheric environment.

[0017] Furthermore, the system comprises:

[0018] The cold air outside the floating platform is driven by the pressure difference, enters the cold air loop 2 from the cold air inlet 2-1, and is replenished to the hot air loop 3 from the cold air annular descending section 2-2, and exchanges heat with the outer wall of the containment 1 to increase the temperature.

[0019] Furthermore, the system comprises:

[0020] The air in the cold air loop 2 and the hot air loop 3 circulates naturally driven by the density difference, continuously cooling the outer wall of the containment vessel 1 without relying on external power supply and little human intervention, maintaining the temperature and pressure inside the containment vessel 1 within the set range, and ensuring the structural integrity of the containment vessel 1.

[0021] Furthermore, the shell of the cold air circuit 2 and the air guide plate 4 shield the radiation released through the containment 1. The beneficial effects brought by the present invention are as follows:

[0022] It can be seen from the above scheme that an embodiment of the present invention provides a passive containment air cooling system that can be used for a floating nuclear power platform, including: a containment, a cold air circuit, a hot air circuit and an air guide plate. The cold air circuit includes: a cold air inlet and a cold air annular descending section, and the cold air inlet is provided with a first isolation valve for controlling the operation and stop of the passive containment cooling system; the hot air circuit includes: a hot air outlet and a hot air annular ascending section, and the hot air outlet is provided with a second isolation valve for controlling the operation and stop of the passive containment cooling system; the cold air annular descending section is connected to the hot air annular ascending section at the bottom of the floating nuclear power platform, and is isolated from the top of the floating nuclear power platform by an air guide plate. The technical solution of the present invention can realize the smooth extraction of heat from the containment, maintain the temperature and pressure in the core and the containment within the normal range, and ensure the integrity of the containment structure. BRIEF DESCRIPTION OF THE DRAWINGS

[0023] Figure 1 A schematic diagram showing a longitudinal section structure of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention;

[0024] Figure 2 A schematic cross-sectional structure diagram of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention;

[0025] Figure 3 A schematic diagram showing a waterline cross-sectional structure of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention;

[0026] In the figure, 1 is the containment, 2 is the cold air circuit, 2-1 is the cold air inlet, 2-2 is the cold air annular descending section, 3 is the hot air circuit, 3-1 is the hot air outlet, 3-2 is the hot air annular ascending section, and 4 is the air guide plate. DETAILED DESCRIPTION

[0027] In order to make the purpose, technical solution and advantages of the present invention clearer, the technical solution in the embodiment of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiment of the present invention. Obviously, the described embodiment is a part of the embodiment of the present invention, not all the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0028] In an embodiment of the present invention, a passive containment air cooling system that can be used for a floating nuclear power platform can achieve long-term heat removal from the containment without relying on an external power source and without human intervention, thereby ensuring the integrity of the containment structure.

[0029] like Figure 1 As shown, Figure 1 A schematic diagram showing a longitudinal section structure of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention; Figure 2 A schematic cross-sectional structure diagram of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention; Figure 3 A schematic diagram of a waterline cross-sectional structure of a passive containment air cooling system that can be used for a floating nuclear power platform according to an embodiment of the present invention is shown.

[0030] Figure 1 A passive containment air cooling system that can be used for a floating nuclear power platform includes: a containment 1, a cold air loop 2, a hot air loop 3 and an air guide plate 4.

[0031] The cold air circuit 2 comprises: a cold air inlet 2-1 and a cold air annular descending section 2-2, wherein the cold air inlet 2-1 is provided with a first isolation valve for controlling the operation and stop of the passive containment cooling system;

[0032] The hot air circuit 3 comprises: a hot air outlet 3-1 and a hot air annular ascending section 3-2, wherein the hot air outlet 3-1 is provided with a second isolation valve for controlling the operation and stop of the passive containment cooling system;

[0033] The cold air annular descending section 2-2 and the hot air annular ascending section 3-2 are connected at the bottom of the floating nuclear power platform and are isolated from the top of the floating nuclear power platform by an air guide plate 4.

[0034] In the embodiment of the present invention, the long-term heat removal of the containment of the floating nuclear power platform with little human intervention can be achieved without external power, wherein the cold air circuit shell and the air guide plate can perform multiple shielding of the radiation released through the containment. The technical solution of the present invention realizes the long-term heat removal function of the containment by only using the hull structure of the floating nuclear power platform, without other auxiliary equipment, and the system is simple and reliable.

[0035] In one embodiment of the present invention, the system comprises:

[0036] Reactor shielding materials are arranged on the containment vessel 1, and reactor heat insulation materials are arranged outside the shell of the cold air loop 2; the shell of the cold air loop 2 and the air guide plate 4 only bear the air circulation function and have no load-bearing function.

[0037] In another embodiment of the present invention, the system comprises:

[0038] When the temperature and pressure in the containment 1 rise to the set values, the first isolation valve arranged at the cold air inlet 2-1 and the second isolation valve arranged at the hot air outlet 3-1 are opened;

[0039] The air in the hot air loop 3 is heated by the containment vessel 1 , and the air density decreases, thereby forming a density difference with the cold air in the cold air loop 2 .

[0040] In another embodiment of the present invention, the system comprises:

[0041] The air density difference in the hot air loop 3 causes a pressure difference, which further drives the hot air in the hot air loop 3 to float from the hot air annular rising section 3-2 to the hot air outlet 3-1, and is discharged from the floating platform into the external atmospheric environment.

[0042] In another embodiment of the present invention, the system comprises:

[0043] The cold air outside the floating platform is driven by the pressure difference, enters the cold air loop 2 from the cold air inlet 2-1, and is replenished to the hot air loop 3 from the cold air annular descending section 2-2, and exchanges heat with the outer wall of the containment 1 to increase the temperature.

[0044] In another embodiment of the present invention, the system comprises:

[0045] The air in the cold air loop 2 and the hot air loop 3 circulates naturally driven by the density difference, continuously cooling the outer wall of the containment vessel 1 without relying on external power supply and little human intervention, maintaining the temperature and pressure inside the containment vessel 1 within the set range, and ensuring the structural integrity of the containment vessel 1.

[0046] In yet another embodiment of the present invention, the shell of the cold air circuit 2 and the air guide plate 4 shield the radiation released through the containment vessel 1 .

[0047] In the embodiment of the present invention, the pressure difference caused by the density difference between cold and hot air is used to drive cold air to continuously enter the cooling containment inside the floating nuclear power platform, and automatically discharge the hot air outside the floating nuclear power platform. Among them, the long-term heat removal of the containment of the floating nuclear power platform with little human intervention can be achieved without external power. The cold air loop shell and the air guide plate only have the function of air circulation, not the load-bearing function, and thin and light materials can be used to reduce the weight of the floating platform. In addition, the cold air loop shell and the air guide plate can shield the radiation released through the containment for multiple times.

[0048] like Figures 1 to 3 As shown, a passive containment air cooling system that can be used for a floating nuclear power platform includes: a containment 1, a cold air loop 2, a cold air inlet 2-1, a cold air annular descending section 2-2, a hot air loop 3, a hot air outlet 3-1, a hot air annular ascending section 3-2, and an air guide plate 4.

[0049] The cold air inlet 2-1 and the hot air outlet 3-1 are provided with isolation valves to control the operation and stop of the passive containment cooling system. The cold air annular descending section 2-2 and the hot air annular ascending section 3-2 are connected at the bottom of the platform and isolated by the air guide plate 4 at the top of the platform.

[0050] Reactor shielding materials can be arranged on the containment 1, and reactor thermal insulation materials can be arranged outside the shell of the cold air loop 2. The shell of the cold air loop 2 and the air guide plate 4 only bear the air circulation function and do not have the load-bearing function. Therefore, light and thin materials can be used to reduce the weight of the floating platform. The cold air loop 2 and the air guide plate 4 can perform multiple shielding on the radiation released through the containment.

[0051] When the reactor system is operating normally or an accident occurs, the temperature and pressure in the containment rise to the set values, and the cold air inlet 2-1 and hot air outlet 3-1 isolation valves are opened.

[0052] After the air in the hot air loop 3 is heated by the containment, its density decreases, forming a density difference with the cold air in the cold air loop 2. The pressure difference caused by the density difference drives the hot air in the hot air loop 3 to float from the hot air annular rising section 3-2 to the hot air outlet 3-1, and is discharged from the floating platform into the external atmospheric environment.

[0053] The cold air outside the floating platform is driven by the pressure difference to enter the cold air loop 2 from the cold air inlet 2-1, and is replenished to the hot air loop (3) from the cold air annular descending section (2-2), and heat-exchanges with the outer wall of the containment to increase the temperature, and enters the next cycle.

[0054] The air in the cold air loop 2 and the hot air loop 3 circulates naturally driven by the density difference, continuously cooling the outer wall of the containment without relying on external power and with little human intervention, maintaining the temperature and pressure inside the containment within a normal range and ensuring the structural integrity of the containment.

[0055] The technical solution of the present invention can realize the smooth extraction of heat from the containment, maintain the temperature and pressure in the core and the containment within a normal range, and ensure the integrity of the containment structure.

[0056] The above are preferred embodiments of the present invention. It should be pointed out that, for ordinary technicians in this technical field, several improvements and modifications can be made without departing from the principles of the present invention. These improvements and modifications should also be regarded as within the scope of protection of the present invention.

Claims

1. A passive containment air cooling system for a floating nuclear power platform, characterized in that: The system comprises: a containment vessel (1), a cold air circuit (2), a hot air circuit (3) and an air guide plate (4); The cold air circuit (2) comprises: a cold air inlet (2-1) and a cold air annular descending section (2-2); the cold air inlet (2-1) is provided with a first isolation valve for controlling the operation and stop of the passive containment cooling system; The hot air circuit (3) comprises: a hot air outlet (3-1) and a hot air annular ascending section (3-2); the hot air outlet (3-1) is provided with a second isolation valve for controlling the operation and stop of the passive containment cooling system; The cold air annular descending section (2-2) and the hot air annular ascending section (3-2) are connected at the bottom of the floating nuclear power platform and are isolated from the top of the floating nuclear power platform by the air guide plate (4).

2. A passive containment air cooling system for a floating nuclear power platform according to claim 1, characterized in that: The system comprises: Reactor shielding materials are arranged on the containment vessel (1), and reactor heat insulation materials are arranged outside the shell of the cold air loop (2); the shell of the cold air loop (2) and the air guide plate (4) only have the function of air circulation and do not have the function of bearing weight.

3. The passive containment air cooling system for a floating nuclear power platform according to claim 1, characterized in that: The system comprises: When the temperature and pressure in the containment (1) rise to set values, the first isolation valve arranged at the cold air inlet (2-1) and the second isolation valve arranged at the hot air outlet (3-1) are opened; The air in the hot air circuit (3) is heated by the containment vessel (1), and the air density is reduced, thereby forming a density difference with the cold air in the cold air circuit (2).

4. The passive containment air cooling system for a floating nuclear power platform according to claim 3, characterized in that: The system comprises: The air density difference in the hot air circuit (3) causes a pressure difference, which further drives the hot air in the hot air circuit (3) to float from the hot air annular rising section (3-2) to the hot air outlet (3-1), and is discharged from the floating platform into the external atmospheric environment.

5. The passive containment air cooling system applicable to a floating nuclear power platform according to claim 4, characterized in that: The system comprises: The cold air outside the floating platform is driven by the pressure difference, enters the cold air circuit (2) from the cold air inlet (2-1), and is replenished to the hot air circuit (3) from the cold air annular descending section (2-2), exchanging heat with the outer wall of the containment vessel (1) to increase the temperature.

6. The passive containment air cooling system for a floating nuclear power platform according to claim 4, characterized in that: The system comprises: The air in the cold air circuit (2) and the hot air circuit (3) circulates naturally driven by the density difference, continuously cooling the outer wall of the containment vessel (1) without relying on external power supply and with little human intervention, maintaining the temperature and pressure inside the containment vessel (1) within a set range, and ensuring the structural integrity of the containment vessel (1).

7. A containment pressure suppression filtration and drainage system for a floating nuclear power platform according to any one of claims 1 to 6, characterized in that: The shell of the cold air circuit (2) and the air guide plate (4) shield the radiation released through the containment vessel (1).

Images