Nuclear facilities and passive safety methods in nuclear facilities

Abstract

According to a first aspect of the application, a nuclear installation is proposed having a makeup network associated with a primary circuit arranged in an operation hall (100). In particular, the nuclear installation comprises a condensation surface (101, 102), a first primary circuit and a first collection means (131), all housed in the operation hall (100). The first collection means is configured to collect condensate on the condensation surface (101, 102). The nuclear installation further comprises a first makeup line (151) connecting the first collection means (131) and a respective water storage cavity of the first primary circuit (110). The nuclear installation further comprises a makeup liquid source (180) configured to selectively make up the first collection means (131) to establish a fluid phase change circulation along a recirculation flow path between the first primary circuit (110), the condensation surface (101, 102), the first collection means (131) and the first makeup line (151).

Description

Technical Field

[0001] This invention relates to nuclear facilities. Specifically, this disclosure relates to controlling the removal of heat (e.g., decay residual heat) from operating pools (e.g., reactor pools or spent fuel pools) within the operating halls (e.g., reactor halls or spent fuel halls) of a nuclear facility. Background Technology

[0002] Several different solutions are known in the prior art for removing decay heat from operating pools in nuclear facilities. Conventional solutions rely on long-term water storage mechanisms to inject water into the operating pool (particularly the reactor pool or spent fuel pool) from a safe water source in emergencies. Conventional systems depend on complex active control systems to ensure sufficient water is available in the operating pool in emergencies.

[0003] The purpose of this invention is to provide an effective alternative to existing technologies, offering greater passivity and less susceptibility to failure compared to conventional systems used to maintain sufficient water levels in the operating pool during emergencies. Certain embodiments specifically aim to address the long-term cooling challenges associated with multi-unit operation of small modular reactors (SMRs) in a shared reactor hall. Summary of the Invention

[0004] This invention is defined by the features in the independent claims. Certain specific embodiments are defined by the dependent claims.

[0005] In a first aspect, the present invention proposes a nuclear facility having a replenishment network associated with an operating pool located within an operating hall. Specifically, the nuclear facility includes a condensation surface, a first operating pool, and a first collection mechanism, all housed within the operating hall. The first collection mechanism is used to collect condensate from the condensation surface. The nuclear facility also includes a first replenishment conduit connecting the first collection mechanism to a corresponding water storage chamber in the operating pool. The nuclear facility further includes a recirculation path located between the operating pool, the condensation surface, the first collection mechanism, and the first replenishment conduit to establish a fluid phase change cycle along the recirculation path.

[0006] In a second aspect, the present invention proposes a passive safety method for facilitating heat removal from a first operating pool contained within the operating hall of a nuclear facility. The method includes establishing a fluid phase-change circulation along a replenishment flow path, which is at least partially formed by: a first collection mechanism for collecting condensate from a condensation surface of the operating hall; a first replenishment conduit for guiding fluid from the first collection mechanism to the operating pool; the operating pool; and the inner surface of the operating hall.

[0007] Certain specific variations of the disclosed aspects may include one or more features from the following detailed list: The recirculation path is formed at least in part by a first operating tank, a condensation surface, a first collection mechanism, and a first replenishment pipe; The first collection mechanism is replenished with liquid to establish a fluid phase change cycle along the replenishment flow path, which is at least partially formed by the first collection mechanism; The condensation surface is a ceiling surface or an interior wall surface, or is at least partially formed by a ceiling surface or an interior wall surface; The condensation surface is the ground, or at least partially formed by the ground; The supplementary piping is designed to selectively connect to the water storage chamber; The supply flow path can be a closed flow path or an open flow path; The replenishment liquid source is configured to selectively replenish the intermediate space via a first collection mechanism and a first replenishment pipe; The replenishment liquid source is a dedicated liquid storage unit located outside the operating pool; Nuclear facilities include a platform surrounding the operating pool; The platform is tilted towards the collection facility; The operating pool is either a reactor pool or a spent fuel pool; Nuclear facilities include dry wells located within the operations hall; The nuclear facility includes the first pool shell located within the operations hall; The shell of the first pool at least partially forms the first operating pool; The shell of the first pool defines the water storage chamber of the first operating pool; The shell of the first pool is located inside the dry well; An intermediate space was formed between the dry well and the pool shell; The first pool shell is configured inside the dry well such that no air gap is formed between the dry well and the pool shell; The replenishment liquid source is configured to selectively replenish the water storage chamber of the first operating pool via a first collection mechanism, a first replenishment pipe, and an intermediate space; The replenishment liquid source is connected to the first collection mechanism via a replenishment liquid source pipeline; The replenishment liquid source is selectively connected to the first collection mechanism via a replenishment liquid source pipeline; The outlet of the replenishment liquid source pipeline is set higher than the inlet of the first replenishment pipeline; The first supplementary pipeline leads to the first operating pool; The outlet of the replenishing liquid source pipeline is connected to the first collection mechanism; The inlet of the first replenishment pipeline is set to be higher than the highest liquid level of the first operating tank under normal operating conditions; The outlet of the first replenishment pipeline leading to the first operating tank is set to be higher than the rated liquid level of the first operating tank under normal operating conditions; The nuclear facility includes a first collection tank for storing a portion of the fluid collected by the first collection unit; The nuclear facility includes a first water collection tank conduit that connects the first water collection tank to the first collection mechanism; The first water collection tank pipe connects the first water collection tank to the bottom area of ​​the first collection mechanism; The inlet of the first water collection tank pipe at the first collection mechanism is set higher than the outlet of the first water collection tank pipe at the first water collection tank. Nuclear facilities include multiple such operating pools; The multiple operating pools include a second operating pool located in the operating hall and adjacent to the first operating pool, with the normal operating liquid level of the first operating pool being the same as that of the second operating pool; Nuclear facilities include multiple such collection facilities; Multiple collection agencies include a second collection agency; The second collection unit is located opposite the first collection unit in the operation hall; The second collection mechanism is designed to collect condensate from the condensation surface; The nuclear facility includes corresponding drainage pipes for connecting the collection units to the operating pool; Multiple drainage pipes include a second supplementary pipe, which connects to the corresponding water storage chambers of the second collection mechanism and the second operating pool; The replenishment liquid source is designed to simultaneously replenish all operating pools via a corresponding collection mechanism; The operating hall is either the reactor hall or the spent fuel hall; The operations hall forms an airtight boundary for the air space defined by the operations hall; The recirculation path is formed at least in part by the air space defined by the operating hall; The recirculated flow is a natural flow; The nuclear facility is a small, modular nuclear reactor facility; The operations hall is the reactor hall that houses multiple reactor pools.

[0008] Novel proposals can gain a significant advantage.

[0009] The collection mechanisms and piping form a novel supplemental network designed to ensure that water evaporating from the superheated pool can be returned to the pool without causing unnecessary water loss. By supplementing the collection mechanisms, a communicating vessel system is established. When water begins to evaporate due to reactor superheating, steam condensation occurring on the building envelope is collected in the collection mechanisms, thus enabling the communicating vessel system to compensate for the water loss in the affected pool. Attached Figure Description

[0010] Certain exemplary embodiments will now be described in detail with reference to the accompanying drawings, wherein: Figure 1 A schematic cross-sectional view of the passive safety systems in a nuclear power facility under normal operating conditions is shown. Figure 2 Showing Figure 1 A schematic top view of the system; Figure 3 Showing Figure 1 A schematic cross-sectional view of the system in an emergency state; Figure 4 Showing Figure 3 A schematic top view of the system; Figure 5 Showing Figure 1 A three-dimensional cross-sectional view of the system in the diagram; Figure 6 Showing Figure 5 A partial cross-sectional side view of the system's collection mechanism and water collection tank under normal operating conditions; Figure 7 Showing Figure 5 A partial cross-sectional side view of the system's collection mechanism and water collection tank in an emergency situation; Figure 8 Showing Figure 5 A partial cross-sectional side view of the system's collection mechanism and operating pool under normal operating conditions; and Figure 9 Showing Figure 5 A partial cross-sectional side view of the system's collection mechanism and operating pool in an emergency. Detailed Implementation

[0011] As will be clear from the following description, the disclosed embodiments provide an apparatus for maintaining water levels in a nuclear facility to ensure adequate cooling capacity in the event of an overheating event. The proposed embodiments include multiple return paths for evaporated water to replenish the pool and reduce water loss.

[0012] Figure 1 An exemplary operating hall 100 of a nuclear facility is schematically shown. The nuclear facility may be a small, modular nuclear reactor facility whose operating hall serves as a reactor hall housing one or more reactor pools. According to a particular embodiment, the nuclear facility is configured for district heating.

[0013] The illustrated operating hall 100 houses two operating pools 110 and 120. Specifically, the exemplary operating hall 100 is a reactor hall with two reactor pools. However, it should be noted that the two reactor pools 110 and 120 shown are merely examples, and the embodiments described herein are equally applicable to other operating halls in nuclear facilities and other numbers and types of pools, such as spent fuel halls each having one or more spent fuel pools. For clarity, the following description will be given in the context of the illustrated reactor pools, illustrating exemplary embodiments. One or more of these reactor pools may house one or more nuclear reactor cores enclosed in a pressure vessel. That is, the nuclear reactor may be submerged in the reactor pool.

[0014] The reactor hall 100 has a ceiling, walls, and / or other encapsulation structures that define the internal air space. These encapsulation structures (including the HVAC system if it is used) preferably form an airtight boundary for the internal air space.

[0015] Reactor pools 110 and 120 are formed by pool shells 112 and 122, which are embedded in dry wells 111 and 121 located at the bottom of the reactor hall 100. Optionally and preferably, the pool shells 112 and 122 are separated from the dry wells 111 and 121 by intermediate spaces 113 and 123 between them. The intermediate spaces 113 and 123 serve to facilitate the installation of seismic shock resistant protective equipment and / or maintenance. Alternatively or additionally, the intermediate spaces 113 and 123 can be used to provide an extended grace period to restore system configuration in the event of an unexpected false triggering of the system, thereby preventing damage to the pool shells 112 and 122 before they are affected by any impact.

[0016] The reactor hall 100 also houses one or more collection mechanisms 131, 132 for collecting condensate from one or more condensation surfaces. In the example shown, the reactor hall 100 houses two condensate collection mechanisms arranged around the perimeter. slot Collection mechanisms 131 and 132. However, it is also possible to use only one collection mechanism 131 to serve multiple operating pools 110 and 120. Conventionally, the reactor hall 100 has an elevated platform located next to the reactor pools 110 and 120 for technicians to walk on. Figure 1The diagram shows a collection platform 102a located between collection mechanisms 131, 132 and reactor pools 110, 120, and a pool platform 102b located between reactor pools 110, 120. The platform system formed by the various platform sections is preferably inclined towards pools 110, 120 or collection mechanisms 131, 132 to avoid water accumulation on the reactor hall floor. That is, platform systems 102a, 102b form a floor surface 102. It should be noted that some condensation may also accumulate on floor surface 102. Since floor surface 102 forms or may form part of a condensation surface, it is recommended that it be inclined. Figure 1 In the diagram, the tilt is shown on the collection mechanism platform 102a, which is tilted toward the collection mechanisms 131 and 132. These platforms may be above the preset water levels of the collection mechanisms 131 and 132 and the reactor pools 110 and 120.

[0017] Collection units 131 and 132 are connected to adjacent reactor pools 110 and 120 via pipes so that water accumulated in collection units 131 and 132 can be selectively used to replenish reactor pools 110 and 120. Figure 1 Two such pipes are shown: a first replenishment pipe 151 connecting a first collection mechanism 131 to a first reactor pool 110, and a second replenishment pipe 152 connecting a second collection mechanism 132 to a second reactor pool 120. The replenishment pipes 151 and 152 are inclined toward the reactor pools 110 and 120, meaning that the inlets of the replenishment pipes 151 and 152 at the collection mechanisms 131 and 132 are higher than the outlets at the reactor pools 110 and 120. The inlets of the replenishment pipes 151 and 152 at the collection mechanisms 131 and 132 are set higher than the rated water level of the collection mechanisms 131 and 132 during normal operation. This means that the replenishment pipes 151 and 152 will only replenish the reactor pools 110 and 120 when the water level of the collection mechanisms 131 and 132 exceeds the rated water level and is sufficient to reach the inlets of the replenishment pipes 151 and 152. Accordingly, after the collection mechanisms 131 and 132 are replenished, the reactor pools 110 and 120 are selectively replenished.

[0018] Figure 1 Optional replenishment valves 154 and 155, located on replenishment pipes 151 and 152, are also shown for additional replenishment control. Replenishment to pools 110 and 120 can be controlled by opening and closing replenishment valves 154 and 155, regardless of the water level in collection mechanisms 131 and 132. Furthermore, replenishment valves 154 and 155 can also be used for maintenance work. The pipe valves 154 and 155 can also be replaced by other mechanisms capable of controlling the flow of water in replenishment pipes 151 and 152, such as removable plugs or any other foreseeable mechanism.

[0019] Water from collection mechanisms 131, 132 and pools 110, 120 is connected to a replenishment network via replenishment pipes 151, 152, which also form part of the replenishment network. A replenishment liquid source 180 is connected to the replenishment network to regulate the amount of water contained within it. Specifically, the replenishment liquid source 180 can be configured to inject a single, predetermined amount of water into the replenishment network. Figure 1 An example of a water tank as such a replenishment liquid source 180 is shown. While the water tank can be located outside the reactor hall 100, it can actually be positioned almost anywhere, such as inside or above the reactor hall 100, or even below the reactor hall 100 if an additional pressure source is provided. The system can be replenished by releasing the contents of the water tank into the replenishment network, thus eliminating the need for additional water level adjustments.

[0020] Alternatively, the makeup liquid source 180 could also be configured as a pressurized water supply line. However, for practical reasons, it is preferable to install an external water tank that is elevated relative to the collection mechanism, as it does not occupy space within the reactor hall and does not require an additional pressure source. It should be understood that even if the makeup liquid source 180 is located within the reactor hall 100, its cavity is independent of the operating pools 110 and 120.

[0021] The replenishment liquid source 180 is connected to the replenishment network via the replenishment liquid source conduit 153. Figure 1 In the illustrated embodiment, the outlet of the replenishment liquid source conduit 153 is configured to allow water to be poured into the collection mechanism 131. This outlet is set above the rated water level of the collection mechanism 131 and above the inlet of the replenishment conduit 151, which communicates with the operating pool 110. Alternatively, the replenishment liquid source conduit 153 may be connected to any or all other parts of the replenishment network, such as the second collection mechanism 132 or any or all operating pools 110, 120. To control the selective release of the liquid contained in the replenishment liquid source 180, the replenishment liquid source conduit 153 is equipped with a replenishment liquid source valve 156. In the simple example shown, since the replenishment liquid source 180 is only connected to one part of the replenishment network (i.e., the first collection mechanism 131), only one valve 156 is needed. However, if replenishment is required for more than one part of the replenishment network, it is preferable to add valves to those parts that require independent replenishment.

[0022] Figure 2 The exemplary nuclear facility is shown more comprehensively through a top-down view. Figure 2 The arrangement of collection mechanisms 131 and 132 on the sides of a long and narrow reactor hall 100 is revealed, with operating pools 110 and 120 located at the center. Figure 2It also shows that the two running pools 110 and 120 are connected to the two collection mechanisms 131 and 132 via supplementary pipes 151 and 152.

[0023] Figure 2 The presence of a collection tank 141 connected to the collection mechanism 131 is also disclosed. While some embodiments may have only a single collection tank, the illustrated embodiment includes two collection tanks 141, 142 for serving the elongated reactor hall 100. The first collection tank 141 is located at one end (i.e., a longitudinal end) of the reactor hall 100, between the collection mechanisms 131, 132 at opposite lateral ends of the reactor hall 100. The first collection tank 141 is connected to the first collection mechanism 131 and the second collection mechanism 132 via collection tank pipes 161, 162. Similarly, the second collection tank 142 is located opposite the first collection tank 141 at the other longitudinal end of the reactor hall 100, between the collection mechanisms 131, 132 at the lateral ends. The second collection tank 142 is connected to the first collection mechanism 131 and the second collection mechanism 132 via collection tank pipes 163, 164. The positions and number of water collection tanks 141 and 142 relative to each other and / or relative to collection mechanisms 131 and 132 may vary.

[0024] Figure 5 The position of the first water tank 141 is shown from a more favorable viewing angle. Figure 5 The arrangement of the water collection tank 141 relative to the collection mechanism 131 is shown as the lowest elevation of the supplementary network. The water collection tank 141 is optional and can be added to ultimately collect water that accumulates in the collection mechanism 131 due to normal operation leaks in the operating hall, thereby allowing the water to be pumped out during normal operation. The water collection tank 141 is not essential for the operation of the supplementary network. However, with the aid of the water collection tank 141, the collection mechanism 131 can be designed to be relatively shallow. Figure 5 The diagram also shows a collection trough conduit 161 connecting a collection trough 141 to the bottom region of a collection mechanism 131, and sloping towards the collection trough 141. In the illustrated embodiment, the inlet of the collection trough conduit 161 is located at the bottom of the collection mechanism 131, but it is also conceivable that it could be located above the bottom point. The collection trough 141 may have a pump (not shown) for pumping out any normal drainage collected in the supplemental network.

[0025] The design of the water collection tank offers considerable flexibility, as long as its location and size do not interfere with the operation of the replenishment network. This means that the shape and volume of the water collection tank can be altered, provided that the tank's dimensions are considered when designing the volume of the replenishment liquid source 180 to achieve the rated replenishment water level, as will be described in detail below. Preferably, the water collection tank is positioned above the minimum height required for cooling heat sources (e.g., reactor or spent fuel) in the operating pools 110 and 120. This prevents accidental water loss from the operating pools to the water collection tank, thus avoiding the danger of insufficient water storage in the pools.

[0026] Figure 5 The presence of an optional auxiliary cavity 170 is also shown. In this document, auxiliary cavity 170 represents any additional cavity that may exist in the operating hall for collecting condensate. Auxiliary cavity 170 may be located at a lower elevation relative to the makeup water level (described below). While the depth and size of such auxiliary cavity 170 are not crucial for the operation of the makeup network, the connection to such cavity is preferably designed to prevent water stagnation within it. To ensure that any condensate seeping into auxiliary cavity 170 is drained, auxiliary cavity 170 is preferably connected to collection mechanisms 131, 132 via auxiliary cavity conduit 171. Auxiliary cavity 170 may be configured to be dry, or partially or completely filled with water, depending on its function. As an example, auxiliary cavity 170 may be used as a descaling pit that needs to be kept dry.

[0027] The following text describes the operation of nuclear facility 100 under normal operating conditions. Figure 1 , Figure 2 , Figure 5 , Figure 6 and Figure 8 The image shows the relative heights of pipes and water levels in the supplementary network.

[0028] like Figure 1 , Figure 2 , Figure 5 , Figure 6 and Figure 8 As shown, the water level in operating tanks 110 and 120 is maintained at the rated water level of 205. However, Figure 8 As shown, under normal operating conditions, the water levels in operating pools 110 and 120 can fluctuate between a minimum water level 206 and a maximum water level 204, with a rated water level 205 in between. It should be understood that the water referred to herein is an example of any liquid stored in an operating nuclear facility. That is, in this document, water can be equated with any liquid used in nuclear processes for storing spent fuel or for any other storage application in a nuclear facility.

[0029] Figure 6 and Figure 8Exemplary height settings between the pipes leading to and from the collection mechanism 131 and the pipes leading to the collection tank 141 and the operating pool 110 are also shown. The outlet of the replenishment liquid source pipe 153 is configured to be lower than the inlet of the replenishment pipe 151 and / or higher than the outlet of the replenishment pipe 151. When comparing the height or elevation of the inlets and outlets of the various pipes, the measurement is taken from the center point of the opening of the aforementioned inlet or outlet. On the other hand, the outlet of the replenishment liquid source pipe 153 is configured to be lower than the rated water level 203 of the replenishment liquid source (i.e., the water level expected to be reached after replenishment) and / or higher than the highest water level 204 of the first operating pool 110 under normal operating conditions. Since the replenishment pipe 151 is inclined toward the operating pool 110, its inlet is configured to be higher than its outlet. It should be noted that the outlet of the replenishment pipe 151 is configured to be higher than the rated water level 205 of the operating pool 110. In order to promote a uniform rise in the water level in the collection mechanism 131 before the water reaches the inlet of the replenishment pipe 151, it is preferable that the outlet of the replenishment liquid source pipe 153 leading to the collection mechanism 131 is set at a height lower than that of the inlet of the replenishment liquid source pipe 153.

[0030] exist Figure 6 In the illustrated state, all water accumulated in the collection mechanism 131 is directed to the collection tank 141, where the water level in the replenishment network does not reach the bottom of the collection mechanism 131, but rather reaches the collection tank pipe 141. This illustrated water level is predictable in practical applications, as it occurs when only a very small amount of condensate is generated during normal operation. In this case, the water level will not reach the inlet of the replenishment pipe 151.

[0031] exist Figure 8 In the indicated state, the water level in the operating pool 110 is at its rated water level 205. This means that all the water in the operating pool 110 is contained within the water storage chamber of the pool shell 112, and no water flows into the intermediate space 113 between the dry well 111 and the pool shell 112, nor into the replenishment pipes 131 and 132. Furthermore, all the water in the replenishment network is maintained between the collection mechanism 131 and the collection tank 141, and no water is transferred to the dry well through the replenishment pipe 151.

[0032] Under normal operating conditions at the nuclear facility, collection facilities 131 and 132 are relatively empty, such as Figure 2 As shown, the collection mechanisms 131, 132 and the water collection tanks 141, 142 are shown in light colors, while the operating pools 110, 120 are shown in dark colors, thus representing the degree of filling. Figure 1 The same situation was also shown in the image, which showed that the replenishment liquid source 180 was full and ready for use.

[0033] The following text describes the operation of nuclear facility 100 under emergency operating conditions. Figure 3 and Figure 4 The image shows the general operation of the supplementary network. Figure 7 and Figure 9 The image shows the relative heights of pipes and water levels in the supplementary network.

[0034] The replenishment network is replenished by releasing water from the replenishment liquid source 180 by opening the replenishment liquid source valve 156. With the replenishment liquid source valve 156 open, water flows through the replenishment liquid source pipe 153 to fill the first collection mechanism 131. Figure 3 The display shows that the replenishment liquid source 180 has been partially emptied. Water is thus distributed to the second collection mechanism 132 via collection tank pipes 161, 162, 163, 164 and collection tanks 141, 142, and to operating pools 110, 120 via replenishment pipes 151, 152. If the replenishment network includes replenishment pipe valves 154, 155 located in replenishment pipes 151, 152, these valves must remain open or be opened during replenishment. Figure 4 This displays an overall view of the supplementary network in its supplementary state, where all components are shown in dark to indicate a high fill level.

[0035] Figure 7 The status of the collection mechanism 131 and the water collection tank 141 in this emergency situation is shown. The collection mechanism 131 and the water collection tank 141 are filled to the rated replenishment water level 203, which is higher than the highest water level 204 of the first operating pool 110 under normal operating conditions, but lower than the pool platform water level 201 and the collection mechanism platform water level 202, so as to avoid submerging platforms 102a and 102b.

[0036] Figure 9 The status of the collection mechanism 131 and the operating pool 110 under this emergency condition is shown. Both the collection mechanism 131 and the operating pool 110 are filled to the rated replenishment water level 203. Figure 9 In the design shown, the outlet of supplementary conduit 131 leads to the intermediate space 113. Alternatively, the outlet of supplementary conduit 131 can be designed to span the pool shell 112, as... Figure 1 As shown. Regardless of the method, the replenishment of the replenishment network will raise the water level sufficiently above the height of the pool shell 112. Now, the water level in the operating pool 110 exceeds the highest water level 204 of the first operating pool 110 under normal operating conditions, thus water will flow across the edge of the pool shell 112 directly ( Figure 9 (The embodiments) or indirectly ( Figure 1 (In the embodiment) the intermediate space 113 is filled. It is understood that the cavity of the supplementary network is now filled, so that water can connect the collection mechanisms 131, 132, the water collection tanks 141, 142 and the operation pools 110, 120 together through the supplementary network.

[0037] Figure 3 The principle of the water replenishment mechanism formed under such an emergency situation is illustrated. In the example shown, the first operating pool 110 is the reactor pool, which contains the abnormal heat to be dissipated from the reactor core. The heat source heats the water contained in the reactor pool 110, causing the water to evaporate, which is depicted as a curve in the air space of the reactor hall 100. The reactor hall 100 includes multiple surfaces that intersect with the internal air space, forming condensation surfaces 101 for the condensation of water vapor. In the example shown, the ceiling of the reactor hall 100 is identified as the condensation surface 101; however, in practice, there may be other additional surfaces that cause condensation, such as the walls of the reactor pool 110 or any other superstructure located on top of the reactor pool 110. As condensate accumulates on the condensation surface 101, it eventually begins to flow toward collection mechanisms 131, 132, which are located at the edges of the downward-sloping condensation surface 101. When the condensate reaches the collection mechanisms 131, 132, it can be replenished to the water storage chamber of the reactor pool 110 through the replenishment network. exist Figure 3 In the example, the collected condensate flows from the condensation surface 101 to the collection mechanism 131 and then through the replenishment pipe 151 to the reactor pool 110.

[0038] Generally, it is preferable that the inlet and outlet of the supplemental network are configured such that any normal drainage buildup will not reach a height that would allow water to flow through the supplemental network (particularly through supplemental pipes 151, 152 to the operating tanks 110, 120). If there are multiple operating tanks 110, 120, it is preferable to ensure that the supplemental elevation of all connected storage chambers of the supplemental network is the same during operation.

[0039] Once the root cause of the emergency has been eliminated, normal operation can be restored by removing excess water from the system. For example, water can be pumped out of the replenishment network by a pump (not shown) located in a collection tank or intermediate space to restore normal function.

[0040] In light of the above, the following summary can be made: the replenishment network is configured to establish a phase change recirculation path for water. When the replenishment network is replenished via replenishment liquid source 180, the recirculation path is partially formed by the following components of the replenishment network: condensate surface 101, collection mechanisms 131, 132, replenishment conduits 151, 152, and operating pools 110, 120. If the nuclear facility includes more than one collection mechanism, replenishment conduit, or operating pool, one or more of these components may also participate in the formation of the replenishment network. Optionally, the air space formed under the enclosure structure of the operating hall 100 (through which water flows in the form of steam) may also be considered as part of the recirculation path.

[0041] A novel concept for forming a phase change recirculation flow path for water within an operations hall 100 of a nuclear facility can be used to achieve a passive safety method for heat removal from an operations pool 110 contained within such an operations hall 100. In this method, a collection mechanism 131 is replenished with liquid to establish a fluid phase change circulation along a replenishment flow path, which is at least partially formed by: a collection mechanism 131 for collecting condensate on the inner surface 101 of the operations hall 100; a replenishment conduit 151 for guiding fluid from the first collection mechanism 131 to the operations pool 110; the operations pool 110; and the inner surface 101 of the operations hall 100.

[0042] The embodiments described herein can be modified in various ways.

[0043] For example, the first pool shell can be disposed in the dry well 111, so that no air gap is formed between the dry well 111 and the pool shell 112.

[0044] In the illustrated embodiment, the condensation surface is formed by the inner surface of the operating hall, which is shown to include at least the wall and ceiling surfaces and the floor. The interior space of the operating hall may also include other structures capable of condensing moisture. These structures are preferably configured to direct condensate flow to a collection mechanism. Alternatively or additionally, the operating hall may also include dedicated condensation structures, such as covers or baffles, configured to collect and guide moisture rising from the operating pool to the collection mechanism. Such covers may, for example, take the form of a sloping ceiling above the operating pool.

[0045] The embodiments shown herein relate to an open supply path spanning the internal air space of the operating hall. However, it is also possible to force steam rising from the operating pool to follow a specific path toward the condensing surfaces 101, 102. According to one embodiment, the operating hall includes ducts disposed in the internal air space to guide evaporated steam toward the condensing surfaces, thereby closing the recirculation path to follow a predetermined route.

[0046] The disclosed condensate recirculation occurs naturally through evaporation, convection, and condensation. This recirculation can also be assisted by a fan blowing air into the intermediate space, a wick on the condensation surface, or other facilitating units.

[0047] It should be understood that the embodiments disclosed herein are not limited to the specific structures, processes, or materials disclosed herein, but can be extended to equivalents that would be recognized by one of ordinary skill in the art. It should also be understood that the terminology used herein is for describing specific embodiments only and is not intended to be limiting.

[0048] The terms "an embodiment" or "an embodiment" as used in this specification mean that a particular feature, structure, or characteristic described in connection with that embodiment may be included in at least one embodiment of the invention. Therefore, the terms "in one embodiment" or "in an embodiment" in this specification do not necessarily refer to the same embodiment.

[0049] In this document, for convenience, multiple components, structural elements, constituent elements, and / or materials may be presented in a common list. However, these lists should be interpreted as each individual item in the list being individually identifiable as a separate and unique entity. Therefore, unless otherwise stated, entities in such lists should not be considered substantially equivalent to any other entity in the same list simply because they appear in a common group. Furthermore, various embodiments and examples of the invention may also have alternatives to the various components mentioned herein. It should be understood that such embodiments, examples, and alternatives should not be construed as being substantially equivalent to each other, but should be regarded as independent and autonomous representations of the invention.

[0050] Furthermore, the described features, structures, or characteristics can be combined in one or more embodiments in any suitable manner. Numerous specific details, such as examples of length, width, shape, etc., are set forth herein to facilitate a comprehensive understanding of embodiments of the invention. However, those skilled in the art will recognize that the invention can also be practiced without one or more specific details, or using other methods, components, materials, etc. Additionally, well-known structures, materials, or operations are not shown or described in detail herein to avoid obscuring the key technical points of the invention.

[0051] While the foregoing examples illustrate the principles of the invention in one or more specific applications, it will be apparent to those skilled in the art that many modifications in form, usage, and implementation details may be made without inventiveness and without departing from the principles and concepts of the invention. Therefore, the invention is not intended to be limited in any way other than the following claims.

[0052] The terms “comprising” and “including” as used herein are open-ended restrictions, neither excluding nor requiring the presence of any unlisted features. Unless otherwise expressly stated, the features listed in the dependent claims may be freely combined. Furthermore, it should be understood that the use of “a” or “an” (i.e., the singular form) herein does not exclude plural cases.

[0053] List of reference numerals

Claims

1. A nuclear facility, comprising: Operations Hall (100); Condensation surfaces (101, 102) housed within the operating hall (100). as well as A first collection mechanism (131) is housed within the operating hall (100) and configured to collect condensate from the condensation surfaces (101, 102). Its features are: Multiple operation pools (110, 120) are housed within the operation hall (100); and Multiple supplementary pipes (151, 152) connect the corresponding first collection mechanism (131) and the multiple operating pools (110, 120) to the supplementary network to selectively connect the corresponding water storage chambers of the first collection mechanism (131) and the operating pools (110, 120) together.

2. The nuclear facility according to claim 1, characterized in that, The nuclear facility includes a recirculation path for fluid phase change cycling, the recirculation path comprising at least a portion of: The multiple running pools (110, 120). The condensation surfaces (101, 102). The first collection mechanism (131), and The multiple supplementary conduits (151, 152).

3. The nuclear facility according to claim 1 or 2, characterized in that, The nuclear facility includes a replenishment liquid source (180) configured to selectively replenish the first collection mechanism (131) to establish a fluid phase change cycle along the recirculation path.

4. The nuclear facility according to any one of the preceding claims, characterized in that, The condensation surfaces (101, 102) are ceiling surfaces or inner wall surfaces, or are at least partially formed by the ceiling surfaces or inner wall surfaces.

5. The nuclear facility according to any one of the preceding claims, characterized in that, The supplementary pipes (151, 152) are configured to selectively connect to the water storage chamber.

6. The nuclear facility according to any one of the preceding claims, characterized in that, The recirculation path can be a closed or open path.

7. The nuclear facility according to any one of the preceding claims, characterized in that, The replenishment liquid source (180) is configured to selectively replenish the intermediate space (112) via the first collection mechanism (131) and the first replenishment conduit (151).

8. The nuclear facility according to any one of the preceding claims, characterized in that, The supplemental liquid source (180) is a dedicated liquid storage unit located outside the operating pools (110, 120).

9. The nuclear facility according to any one of the preceding claims, characterized in that, The nuclear facility includes platforms (102a, 102b) surrounding the operating pool (110, 120), which are inclined toward the collection mechanism (131, 132).

10. The nuclear facility according to any one of the preceding claims, characterized in that, One or more of the plurality of operating pools (110, 120) are reactor pools or spent fuel pools.

11. The nuclear facility according to claim 10, characterized in that, The nuclear reactor, enclosed in a pressure vessel, is submerged in the reactor pool.

12. The nuclear facility according to any one of the preceding claims, characterized in that: The nuclear facility includes dry wells (111, 121) located within the operations hall (100); and The nuclear facility includes pool shells (112, 122) located within the operations hall (100), the pool shells (112, 122): At least partially forming the plurality of operating pools (110, 120), and The water storage chambers (114, 124) of the plurality of operating pools (110) are defined.

13. The nuclear facility according to claim 12, characterized in that, The pool shell (112, 122) is arranged within the dry well (111, 121) such that an intermediate space (113, 123) is formed between the respective dry well (111, 121) and the pool shell (112, 122).

14. The nuclear facility according to claim 12, characterized in that, The pool shell (112, 122) is arranged within the dry well (111, 121) such that no air gap is formed between the dry well (111, 121) and the pool shell (112, 122).

15. The nuclear facility according to claim 13, characterized in that, The replenishment liquid source (180) is configured to selectively replenish the water storage chambers (114, 124) of the operating pool (110, 120) via the first collection mechanism (131), replenishment pipes (151, 152) and intermediate spaces (113, 123).

16. The nuclear facility according to any one of the preceding claims, characterized in that: The replenishment liquid source (180) is connected via a replenishment liquid source conduit (153), and is particularly selectively connected to the first collection mechanism (131), and The outlet of the replenishment liquid source pipeline (153) connected to the first collection mechanism (131) is configured to be higher than the inlet of the replenishment pipeline (151) leading to the corresponding operating pool (110, 120).

17. The nuclear facility according to claim 16, characterized in that, The inlet of the supplemental pipes (151, 152) leading to the operating pool (110) is set to be higher than the highest liquid level (204) of the operating pool (110, 120) under normal operating conditions.

18. The nuclear facility according to claim 16 or 17, characterized in that, The outlet of the supplementary pipeline (151, 152) leading to the operating pool (110, 120) is configured to be higher than the rated liquid level (205) of the operating pool (110) under normal operating conditions.

19. The nuclear facility according to any one of the preceding claims, characterized in that: The nuclear facility includes multiple water collection tanks (141, 142) for storing a portion of the fluid collected by the first collection mechanism (131); The nuclear facility includes water collection tanks (141, 142) connected to the first collection mechanism (131), and preferably water collection tank pipes (161, 162, 163, 164) connected to the bottom area of ​​the first collection mechanism.

20. The nuclear facility according to claim 19, characterized in that, The inlet of the water collection pipe (161, 162, 163, 164) at the first collection mechanism (131) is configured to be higher than the outlet of the water collection pipe (161, 162, 163, 164) at the water collection tank (141, 142).

21. The nuclear facility according to any one of the preceding claims, characterized in that, The operating pools (110, 120) are arranged adjacent to each other in the operating hall (100), and their liquid levels are level during normal operation.

22. The nuclear facility according to claim 21, characterized in that: The nuclear facility includes a plurality of the collection units, including a second collection unit (132) located opposite the first collection unit (131) within the operating hall (100). The second collection mechanism (132) is configured to collect condensate on the condensation surfaces (101, 102); and The nuclear facility includes a plurality of corresponding drainage pipes for connecting the collection mechanism to the operating pool, the plurality of drainage pipes including a second supplementary pipe (152) connecting the second collection mechanism (132) to a corresponding water storage chamber of the second operating pool (120).

23. The nuclear facility according to claim 21 or 22, characterized in that, The replenishment liquid source (180) is configured to simultaneously replenish all operating pools via a corresponding collection mechanism.

24. The nuclear facility according to any one of the preceding claims, characterized in that, The operating hall (100) is either the reactor hall or the spent fuel hall.

25. The nuclear facility according to any one of the preceding claims, characterized in that, The operating hall (100) forms an airtight boundary over the air space defined by the operating hall (100).

26. The nuclear facility according to any one of the preceding claims, characterized in that, The recirculation path is formed at least in part by the air space defined by the operating hall (100).

27. The nuclear facility according to any one of the preceding claims, characterized in that, Recirculation is a natural cycle.

28. A passive safety method for facilitating heat removal from multiple operating pools (110, 120) housed within an operating hall (100) of a nuclear facility, the method comprising establishing a fluid phase change circulation along a recirculation path, the recirculation path comprising at least in part: A first collection mechanism (131) collects condensate from the condensation surfaces (101, 102) of the operating hall (100); Multiple supplementary conduits (151, 152) guide fluid from the first collection mechanism (131) to the multiple operating pools (110, 120). The multiple running pools (110, 120); and The inner surface (101) of the operating hall (100).

29. The method according to claim 28, characterized in that, The nuclear power facility is the nuclear power facility defined in any one of claims 1 to 27.

30. The method according to claim 28 or 29, characterized in that, The fluid phase change cycle is established by replenishing the first collection mechanism (131).

31. The method according to claim 28, 29 or 30, characterized in that, This includes simultaneously replenishing the multiple operation pools (110, 120) housed within the operation hall (100).

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