Reactor cartridge core barrel

Abstract

To reduce potential relative movement between a reactor core and control elements.SOLUTION: A method of constructing a nuclear reactor is provided, comprising attaching a core barrel to a control element support structure, where the core barrel is hung from the control element support structure configured to support the weight of each of one or more control elements, the core barrel, and a reactor core.SELECTED DRAWING: Figure 11

Description

Detailed Description of the Invention

[0001] [Cross - Reference to Related Applications This application claims the benefit of U.S. Patent Application No. 17 / 164,820, titled "CARTRIDGE CORE BARREL FOR NUCLEAR REACTOR", filed on February 1, 2021, which claims priority to Provisional Patent Application No. 63 / 066,785, titled "CARTRIDGE CORE BARREL FOR NUCLEAR REACTOR", filed on August 17, 2020. The entire content thereof is incorporated herein by reference.

[0002] [Background Most nuclear reactors have a core, within which fuel elements and control elements are supported in various interrelated arrangements to support the critical reactivity and control the output of the nuclear reactor. The coolant is typically forced through passages between the fuel elements and the control elements, and thus the heat generated by the nuclear fission fuel elements is transferred to a heat exchanger for beneficial purposes.

[0003] In some cases, molten metal is used as the coolant, and in some cases, the molten metal is sodium. In some nuclear reactors (e.g., pool - type nuclear reactors where the core is immersed in a pool of coolant held within a reactor vessel), the core is often supported by the reactor vessel, while the control elements are often supported from a deck of a vessel head surrounding the upper end of the reactor vessel.

[0004] This control element support arrangement is often preferred from a safety perspective. For example, if the control element support structure fails, the control element will fall into the reactor vessel, reducing the reactivity within the core. Typically, like the in - vessel handling systems for fuel elements and reactivity elements, the weight of the core, along with the fuel elements and reactivity elements, is supported by the reactor vessel.

[0005] In addition to the weight of the reactor core, the vessel also supports the weight of the coolant it contains. Therefore, the vessel must be robust enough to support not only the loads applied in a static state, but also the loads during seismic events, which can be dramatically larger than those in a static state.

[0006] Furthermore, any relative motion between the core and control elements can affect the reactivity within the core; therefore, reactors are designed to minimize this relative motion. If the reactor vessel is supported from the sides or bottom, and the coolant inventory is moved by events such as earthquakes, the flexibility of the reactor vessel can move the core relative to the control elements suspended from the vessel head. This can cause swings in the reactivity coefficient (Keff) in both positive and negative directions.

[0007] 〔overview〕 According to several embodiments, reactor configurations are described in which the reactor vessel is suspended from the reactor head. However, the weight of the core does not necessarily have to be supported by the reactor head, but rather may be directly transmitted to a support structure located outside the reactor vessel and supported by the ground. In some examples, the core is supported by a cartridge suspended from the reactor vessel head, and thus the load paths of both the core and the control elements are coupled to a common support structure. This reduces the potential relative motion between the core and the control elements.

[0008] According to some embodiments, the reactor core support system comprises a support cylinder having an upper and a lower part, and a mount on the upper part that engages with a reactor vessel head and supports the weight of the support cylinder from the reactor vessel head, wherein the support cylinder is suspended from the reactor vessel head.

[0009] In some cases, the reactor core is located inside the support cylinder. The support cylinder and the reactor core may be pre-assembled and transported to the reactor installation site.

[0010] In some examples, the fuel element handling system is located within the support cylinder. Furthermore, the control element support system may also be located within the support cylinder.

[0011] In some embodiments, the support cylinder and the control element drive system share a common load path. That is, the weight of the support cylinder and the control element drive system are supported by the same structure.

[0012] For example, both the support cylinder and the control element drive system may be suspended from a portion of the reactor vessel head.

[0013] In some cases, the core support located within the support cylinder does not transmit load to the reactor vessel. For example, the core may be located within the support cylinder, and the weight of the core may be supported by the reactor vessel head.

[0014] According to some embodiments, a method for constructing a nuclear reactor includes the steps of: manufacturing a reactor vessel in a manufacturing facility; manufacturing a cartridge core barrel in the manufacturing facility; manufacturing a core in the manufacturing facility; manufacturing a control element drive system in the manufacturing facility; assembling the control element drive system and the core in the cartridge core barrel to form a core module in the manufacturing facility; and transporting the core module to a construction site.

[0015] The method may further include the step of transporting the reactor vessel to the construction site. In some cases, the method may further include the step of installing the reactor vessel in the reactor building. The method may further include the step of arranging the reactor module inside the reactor vessel.

[0016] The method for constructing a reactor may optionally further include the step of integrating the core module with a first portion of the reactor vessel head. The method may optionally include the step of integrating the control element drive system with the first portion of the reactor vessel head.

[0017] According to some embodiments, the lower core support structure for a reactor core includes a conical support portion, a cylindrical support portion coupled to the conical support portion by a transition portion, and one or more vertical ribs.

[0018] The one or more vertical ribs may be connected to the conical support portion. The conical support portion may include a conical tension skirt having a large-diameter periphery connected to the cylindrical support portion. In some cases, the one or more vertical ribs are connected to the upper surface of the conical tension skirt.

[0019] [Brief explanation of the drawing] Figure 1 is a schematic diagram of a reactor support structure according to several embodiments; Figure 2 shows a lower core support structure for the core-vessel interface according to several embodiments; Figure 3 shows a lower core support structure for the core-vessel interface according to several embodiments; Figure 4 shows a lower core support structure with a suspension tension skirt for the core-vessel interface according to several embodiments; Figure 5 shows a lower core support structure having multiple ribs according to several embodiments; Figure 6 shows a lower core support structure independent of the reactor vessel according to several embodiments; Figure 7 shows a lower core support structure in a bottom-supported vessel configuration according to several embodiments; Figure 8 shows a core support structure configured to be suspended from the reactor head, according to several embodiments; Figure 9 shows a core support structure that utilizes a cartridge to connect the core support to the control rod support, according to several embodiments; Figure 10 shows load paths through the lower core support structure and reactor vessel according to several embodiments; Figure 11 shows a cartridge core support structure that supports the core independently of the reactor vessel, according to several embodiments; Figure 12 shows a cartridge module according to several embodiments.

[0020] [Detailed explanation] This disclosure relates, in general, to devices for lower core supports, such as reactor vessel supports (which are conical supports that transition in some cases to cylindrical supports of the reactor vessel) or reactor core supports. In some cases, multiple vertical ribs within the conical support section provide additional stiffness, rigidity, and support.

[0021] In some cases, the core is supported from below by multiple ribs, skirts, or platforms. In some embodiments, the core is supported by a rim. The core may have a structure that engages with the upper rim of the core and is suspended from the support by the rim. In some cases, a vertical cylinder includes a core support structure and multiple core baffles. The core may be inserted from the top of the reactor and supported by a reactor head. In some embodiments, the disclosed configurations and support structures facilitate the transportation of pre-fabricated and assembled or partially assembled components, and the final assembly of such components at the reactor installation site.

[0022] According to some embodiments, the structural cylinder supports the load and transmits the load to the reactor head. According to some embodiments, the control package and core control package may be fabricated and then lowered into predetermined positions within the structural cylinder. The structural cylinder may support the loads of the control package and core control package.

[0023] The support cylinder may be manufactured at a manufacturing facility and may include a core barrel and core components that are already installed before the support cylinder is transported to the reactor installation site. The support cylinder may further have a rotating plug, ports, and other components that are pre-installed before transportation to facilitate later assembly. This improves accuracy, tolerances, and manufacturing and assembly times.

[0024] The following description is useful in the design and configuration of a sodium-cooled fast reactor (SFR), but many of the concepts disclosed herein may equally apply to other reactor types. The present disclosure should not be limited to SFR technology unless otherwise specified.

[0025] FIG. 1 shows a core support structure (CSS) for a reactor core. The reactor includes a core 102 located within a reactor vessel 104. The reactor vessel 104 typically has its lower end closed by a bottom head 106 coupled to a cylindrical portion 108. A vessel head 110 fits over the top of the cylindrical portion 108 to enclose the reactor vessel 104 and further supports the reactor internal structures (such as a rotating plug, core support structure, flow-directing members, control element handling system, fuel element handling system, and other internal vessel equipment).

[0026] In many reactors, the reactor vessel 104 is suspended from the reactor head 110. Also, the reactor head 110 is supported by a structure that forms part of the building in which the reactor is housed. For example, a plurality of support structures 112, which may be concrete, are connected to a foundation 114. The plurality of support structures 112 further support the reactor head 110 such that the weight of the reactor head is supported in a compressed state by the plurality of support structures 112. The reactor vessel 104 is typically suspended from the reactor head 110, and thus its weight is also supported by the plurality of support structures 112 that transfer the load to the foundation 114.

[0027] The reactor vessel 104 houses the internal reactor structure. In some cases, the internal reactor structure includes a lower core support structure (not shown), an upper core support structure, and an in-core instrumentation support structure. The internal structure is configured to support, align, and guide the core components, to direct the flow of coolant from core component to core component, and to guide and support the in-core instrumentation. The lower core support structure is typically coupled to the core 102 and transfers the weight of the core 102 to the bottom head 106 of the reactor vessel 104. The lower core support structure may be a column, pier, or other support beneath the core that allows the core 102 to be supported by the bottom head 106 of the reactor vessel 104.

[0028] The core barrel supports and houses the fuel elements and guides the flow of the coolant. In some cases, the core barrel is suspended from the upper ledge of the reactor vessel. In some cases, the core barrel is capable of thermal expansion in the radial and axial directions. However, lateral movement of the core barrel is restricted to suppress mismatches between the fuel elements and control elements. The core barrel may be coupled to the reactor vessel via any suitable structure that allows the weight of the core barrel to be supported by the reactor vessel from which the core barrel is suspended.

[0029] With respect to Figure 2, the lower core support 200 includes a conical support 202 that transitions into a cylinder 204 that joins to the bottom reactor vessel head. One or more vertical ribs 206 help to position and support the ex-core barrel shielding and flow guides. Furthermore, the vertical ribs 206 help to connect the core support structure and the core-vessel interface structure to a single structure, which may be transportable as a unit. This facilitates the manufacturing of the lower core support structure in-house and the transportation of the core support structure as an assembly to the construction site.

[0030] Figure 3 shows another example of a lower core support structure 300 integrated with the reactor vessel bottom head 302. The core support structure 300 includes several ribs 304 to enhance the rigidity and lateral stability of the core support structure 300. A grid plate 306 is supported by the ribs 304 and supports the core on which it rests. The reactor vessel bottom head 302 is suspended from the cylindrical portion of the reactor vessel.

[0031] Integrating the lower core support structure 300 with the reactor vessel bottom head offers several advantages. For example, it reduces the number of components and assemblies, allows for compatibility with the reactor vessel auxiliary cooling system (RVACS), and provides a level of lateral stability for supporting the core.

[0032] Figure 4 shows another example of a lower core support structure 400 in which a conical tension skirt 402 supports a grid plate structure 404. The core is supported on the grid plate structure 404. The load of the core is transmitted directly to the cylindrical portion 406 of the reactor vessel through the conical tension skirt 402. In some cases, this configuration avoids the load of the core being applied to the bottom head 408 of the reactor vessel, and rather the load of the core is transmitted directly to the cylindrical portion 406 of the reactor vessel.

[0033] As a result, relatively simple manufacturing becomes possible. The conical tension skirt 402 improves the need for internal support from the bottom reactor vessel head 408 and transfers the loads of the core and internal structure through the cylindrical portion 406 of the reactor vessel by tension.

[0034] Figure 5 shows an alternative configuration of the lower core support structure 500, similar to the structure shown in Figure 4, with the addition of multiple ribs 502 above the conical tension skirt 402. The multiple ribs 502 support the flow guides, provide coolant channels, and provide additional rigidity.

[0035] Figure 6 shows an alternative configuration for the lower core support 600. The lower core support 600 includes a cylindrical portion 602 and a conical tension skirt 604 hanging down from the cylindrical portion 602.

[0036] The lower core support 600 may, in some cases, be independent of the reactor vessel 606 to reduce stress on the reactor vessel 606. In some cases, the lower core support 600 may be attached to the reactor vessel 606 by welding to provide tight surface contact, distribute stress, improve rigidity, and distribute the core load to the cylindrical portion of the reactor vessel 606. In some embodiments, the core may be coupled to the lower core support 600 at a manufacturing facility (e.g., a factory), and the entire core with the lower core support 600 may be lowered into the reactor vessel and assembled into the reactor vessel at the construction site.

[0037] Figure 7 illustrates an alternative to the lower core support 700, to which the core load path is transmitted to the bottom support. The reactor vessel 702 has a cylindrical portion 704 coupled to the bottom vessel head 706. In some cases, the bottom vessel head 706 rests on one or more supports to transmit the weight of the reactor vessel 702 downward, ultimately to the base of the reactor building. In some cases, the lower core support 700 is coupled to the reactor vessel 702, and the core load is similarly transmitted to the support and ultimately downward to the base of the reactor building. In embodiments in which the core load is transmitted downward to a support below the reactor vessel 702, the core load does not need to be supported by the reactor vessel 702. Therefore, the flexibility of the reactor vessel 702 reduces the influence on the alignment of the control elements and the core.

[0038] Furthermore, the lateral core supports include a considerably lower core structure that is attached to the same supports that support the reactor vessel 702. This not only significantly reduces the load path of the core load but also supports the core substantially along its center of gravity, providing robust core support.

[0039] Referring to Figures 8 and 9, the configuration of the cartridge 800 in which the core load is supported vertically through the core barrel is shown. The cartridge 800 is generally a cylindrical chamber 802 that allows the reactor core to be inserted from the top. The cartridge 800 includes a cooperative bottom support structure 804 that joins with a lower core support 806 held by a reactor vessel bottom head 808. The cooperative lower core support structure 804 facilitates lowering the cartridge 800 into the reactor vessel 810 and positioning the cartridge 800 relative to the vessel bottom head 808.

[0040] In some cases, the core load is supported by the cartridge 800 in the separated portion of the reactor head. In some cases, the cartridge 800 also supports and houses the rotating plug assembly. By utilizing the cartridge 800 as illustrated and described, factory manufacturing and on-site assembly are simplified because the cartridge 800 can be manufactured at a manufacturing facility and assembled with the pre-installed core and internal structures before transport.

[0041] In some cases, the cartridge 800 is supported from above by the reactor head. This provides the further advantage of coupling the core to the same load path as the control element support. Thus, any differential motion between the core and the control elements due to seismic events, etc., is further reduced.

[0042] In the illustrated example, the core support is directly coupled to the control element support. This further reduces the importance of the reactor vessel in providing support to the core. Consequently, the precision required in the fabrication and assembly of the core relative to the reactor vessel 810 is reduced.

[0043] The reactor vessel 810 may include additional structures required for operation, such as one or more heat exchangers 812 and one or more pumps 814 for circulating coolant through the reactor vessel and core.

[0044] According to some embodiments, the load chain, including the core, cartridges, and reactor vessel head, can be manufactured in a manufacturing facility and transported to the construction site as modules for final assembly. This not only reduces the required on-site manufacturing work but also improves efficiency by allowing the reactor vessel, vessel head, and internal structures to be lifted and placed inside the reactor building. In some cases, the core and cartridges may be manufactured as modules and transported to the construction site for final assembly together with the reactor vessel head, which is a separate module.

[0045] In addition, the illustrated cartridge configuration 800 further decouples the nuclear heat and control modules from their heat transfer functions, so that a standard central cartridge 800 and core module can be inserted into various reactor configurations with minimal modification. In other words, the entire cartridge 800, including the core, control elements, and internal core structures, can be removed from the reactor, and another cartridge 800 can be installed in its place.

[0046] Figure 10 shows a schematic diagram of a reactor 1000, including a reactor vessel 1002, a core barrel 1004, and a core 1006. The reactor vessel 1002 further includes a vessel bottom head 1008 and a vessel head 1010. The vessel head 1010 includes a control element support structure 1012 that supports a control element 1014. The control element 1014 may be used to control the reactivity within the core 1006.

[0047] In the illustrated embodiment, the weight of the reactor core is supported by the core barrel 1004. The core barrel 1004 is further supported by a lower core support 1016 that transmits the core load to the reactor vessel bottom head 1008. In some cases, the reactor vessel 1002 is supported by mounts such as flanges formed on the vessel head 1010. The reactor vessel 1002 is suspended from the vessel head 1010. Thus, the weight of the reactor vessel, together with the core and core barrel, is supported by the vessel head 1010. In some examples, there may be additional support structures, for example, below the reactor vessel 1002 or adjacent to the reactor barrel 1004 to support against lateral loads.

[0048] One area requiring attention in reactor construction is the response of internal reactor structures to seismic events. For example, seismic events can cause the reactor vessel 1002 to move both laterally and axially in response to seismic forces. Similarly, the control element 1014 can move in response to seismic forces. If there is differential motion between the control element 1014 and the reactor vessel 1002, the reactivity within the core 1006 will be affected. In addition, manufacturing the control element support 1012 and the configuration that aligns the core 1006 with the control element 1014 requires tight tolerances and high-quality manufacturing to ensure safe and predictable reactor operation.

[0049] In the illustrated embodiment, the weight of the reactor core is supported by the reactor vessel 1002. Meanwhile, the weight of the control element 1014 is held by the control element support 1012, which forms part of the vessel head 1010. In an earthquake event that causes movement of the reactor vessel 1002, the movement around the reactor vessel head 1010 is translated into lateral movement of the control element 1014 around a pivot point located substantially within the vessel head 1010. Meanwhile, the reactor core 1006 is subject to movement related to the height of the reactor vessel 1002. That is, the reactor core 1002 is subject to movement related to the vessel bottom head 1008, which has a motion of magnitude proportional to the height of the reactor vessel 1002. Often, earthquake events tend to cause greater lateral movement of the reactor core 1006, supported by the reactor vessel 1002, compared to the movement of the control element 1014. The differential motion between the reactor core and the control element 1014 can cause responsiveness fluctuations that can be undesirable and unpredictable.

[0050] Figure 11 shows a schematic diagram of a reactor 1100, including a reactor vessel 1002, a core cartridge 1102, and a core 1006. The reactor vessel 1002 further includes a vessel bottom head 1008 and a vessel head 1010. The vessel head 1010 includes a control element support structure 1012 that holds one or more control elements 1014. The control element support structure 1012 is coupled to the core cartridge 1102 so that the core cartridge 1102 is suspended from the control element support structure 1012. Thus, the load paths of both the core 1006 and the control elements 1014 are coupled to each other by sharing a common support structure 1012 that supports both the control elements 1014 and the core 1006. This significantly reduces differential motion between the control elements 1014 and the core 1006, for example, in response to seismic events.

[0051] Furthermore, the illustrated configuration provides a cartridge 1102 that can be manufactured in a factory, transported to the construction site, and lowered into the reactor vessel even after the reactor vessel 1002 has been installed inside the reactor building. In some cases, the cartridge 1102 may be manufactured in a factory to include the core 1006 and internal core structures before transport. This improves the precision in manufacturing delicate components, reduces the amount of on-site manufacturing work, and significantly reduces the time required to install components on-site.

[0052] Furthermore, the illustrated embodiment reduces complexity and eliminates the reliance of the reactor vessel 1002 walls on supporting the core 1006. As described herein, the first cartridge 1102 may be removed from the reactor vessel 1002 and replaced with a second cartridge 1102. In some embodiments, the second cartridge 1102 has a different configuration from the first cartridge.

[0053] Figure 12 shows a cartridge core barrel 1200, which includes a substantially cylindrical cartridge 1202, a core 1006, and a control element support 1204. The control element support 1204 may include a plurality of openings that allow a control element 1014 to be selectively inserted into and withdrawn from the core 1006. The cartridge core barrel 1200 includes a mounting structure 1206 which may include one or more flanges that engage with a cooperative structure on the reactor vessel head. Thus, the cartridge core barrel 1200 is suspended from the reactor head. The cartridge core barrel 1200 may further include a lower core support 1208 which may cooperate with a fitting structure on the reactor vessel bottom head to provide further support to the core barrel 1200.

[0054] In some embodiments, the cartridge core barrel 1200 may be manufactured in a manufacturing facility and transported to the construction site as a module. The core barrel 1200 may be manufactured to include the core 1006, optional internal core structures, a control element drive system, and a control element support 1204. The load paths of the control element 1014 and the core 1006 are coupled together so that motion related to the reactor vessel head is transmitted to both the core 1006 and the control element 1014 in the same direction and magnitude. This allows the control element 1014 to remain aligned with the core 1006 to a level not previously achieved in reactors where the core load path and the control element are not coupled to each other via a common load path.

[0055] In addition, the cartridge core barrel 1200 may be manufactured as a module and installed inside the reactor vessel after the reactor vessel has been installed inside the reactor building. This improves assembly efficiency, reduces on-site manufacturing, and increases tolerances by manufacturing and assembling the module in a manufacturing facility. According to some embodiments, the cartridge core barrel 1200 may be manufactured as a module including the core, a rotating stopper, and a control element support structure. This module may be manufactured in-house to have tight tolerances that would be very difficult to achieve with on-site manufacturing techniques, and then the module, with its internal elements already installed, may be transported to the construction site for installation.

[0056] In some embodiments, the cartridge core barrel 1200 may be a single module, and the reactor vessel may be a separate module. In some cases, the reactor vessel may be sliced ​​into segments along its longitudinal direction to facilitate transport and assembly. For example, the reactor vessel may be divided into cylindrical segments of appropriate length (e.g., 8 feet, 10 feet, 12 feet, or 15 feet, or more) to facilitate transport of the reactor vessel to the construction site. Multiple segments may be joined together at the site. For example, multiple segments may be joined together at a predetermined location within the reactor building by aligning and installing a first segment in a predetermined location within the reactor building, and then attaching two segments to the first segment. Once the reactor vessel is assembled and installed within the reactor building, the cartridge core barrel 1200 may be lowered into the reactor vessel with the assistance of the lower core support 1208 and positioned within the reactor vessel. Support structures for positioning control elements relative to the core require high-precision manufacturing processes. This is much more easily fulfilled by providing a cartridge core barrel 1200 that is manufactured in a manufacturing plant and transported to the construction site. The cartridge core barrel 1200 may, in some cases, include a core and other internal elements that are pre-assembled before shipment. This greatly simplifies construction, improves accuracy, and eliminates reliance on the reactor vessel to support the weight of the core. By removing the reactor vessel from the load path of the core, the reactor vessel may be manufactured to looser tolerances and less robust. This leads to a reduction in the time and cost of manufacturing the reactor vessel. In other words, the reactor vessel is separated from the cartridge core barrel 1200 and the core 1006. In some cases, the reactor vessel does not participate in supporting the core. However, in some embodiments, the reactor vessel may include one or more spacers in the ring between the reactor vessel and the cartridge core barrel to provide radial lateral stability.

[0057] The cartridge core barrel 1200 may incorporate any suitable lower core support 1208 (e.g., any structure illustrated and described in relation to Figures 2 to 7). Furthermore, the concepts presented herein may be applicable to any reactor type and are particularly suited to reactors that depend on near-atmospheric pressure conditions.

[0058] This disclosure presents exemplary embodiments. Therefore, this disclosure is not intended in any way to limit the scope of the embodiments and the attached claims. Embodiments have been described above with the help of functional configuration blocks illustrating the implementation of the identified functions and their relationships. In this specification, the boundaries of these functional configurations are arbitrarily defined for explanatory purposes. Alternative boundaries may be defined to the extent that the identified functions and their relationships are adequately implemented.

[0059] The general nature of the embodiments of this disclosure will be sufficiently evident from the preceding description of such particular embodiments to the extent that, without departing from the general idea of ​​the embodiments of this disclosure, others may readily modify and / or adapt specific embodiments for various applications by applying the knowledge of those skilled in the art without excessive experimentation. Therefore, such adaptations and modifications are intended to fall within the meaning and scope of the equivalents of the disclosed embodiments, based on the teachings and guidance presented herein. The terminology or language used herein is intended to be explained, and not to be limiting, so that such terminology or language may be interpreted by those skilled in the art in light of the teachings and guidance presented herein.

[0060] The breadth and scope of the embodiments of this disclosure should not be limited by any of the exemplary embodiments described above, but should be defined solely in accordance with the following claims and their equivalents.

[0061] Unless otherwise specified, or unless otherwise understood in the context in which they are used, conditional terms, particularly “may,” “may,” “may,” or “may,” are generally intended to indicate that a particular implementation may include certain features, elements, and / or behaviors, while other implementations may not. Thus, such conditional terms are generally not intended to imply that features, elements, and / or behaviors are required in any way in one or more implementations, nor are they intended to imply that logic for determining whether these features, elements, and / or behaviors are included in any particular implementation, or whether these features, elements, and / or behaviors should be performed in any particular implementation, is necessarily included in one or more implementations, regardless of user input or prompts.

[0062] The specification and drawings disclose examples of systems, apparatus, devices, and technologies that can manufacture reactor modules within a manufacturing facility and transport them to a manufacturing site where the modules are assembled, thereby significantly reducing the complexity and cost of on-site manufacturing. Furthermore, the reactor systems are simplified and further facilitate factory manufacturing instead of on-site manufacturing.

[0063] Those skilled in the art will recognize that any process or method disclosed herein can be modified in many ways. The process parameters and sequences of the processes described and / or illustrated herein are given merely as examples and can be changed as desired. For example, the processes illustrated and / or described herein may be shown or described in a particular order, but these processes do not necessarily have to be performed in the order illustrated or described.

[0064] Various exemplary methods described and / or illustrated herein may omit one or more of the steps described or illustrated herein, or may include additional steps in addition to the disclosed steps. Furthermore, any step of any method disclosed herein may be combined with any one or more steps of any other method disclosed herein.

[0065] Of course, it is impossible to describe all possible combinations of elements and / or methods for the purpose of illustrating the various features of this disclosure. However, those skilled in the art will recognize that many further combinations and substitutions of the disclosed features are possible. Thus, various modifications can be made to this disclosure without departing from the scope or spirit of this disclosure. Furthermore, other embodiments of this disclosure may become apparent by considering the specification and the accompanying drawings and by practicing the disclosed embodiments presented herein. The examples presented herein and in the accompanying drawings should be considered in all respects as illustrative and not restrictive. Certain terms are used herein, but these terms are used in a general and descriptive sense only and not for restrictive purposes.

[0066] Unless otherwise specified, the terms “connected” and “joined” (and their derivatives) used in this specification should be interpreted as allowing both direct and indirect (i.e., through other elements or components) connection. Furthermore, the terms “a” or “an” used in this specification should be interpreted as meaning “at least one of.” Finally, for ease of use, the terms “include” and “have” (and their derivatives) used in this specification should be interchangeable with the word “equipped” and have the same meaning.

[0067] From the foregoing and the accompanying drawings, it will be understood that while specific implementations are described herein for illustrative purposes, various modifications are possible without departing from the intent and scope of the attached claims and the requirements enumerated therein. In addition, while specific embodiments are presented below in specific claims, the inventors envision various embodiments in any available claims. For example, while only some embodiments may be described as being embodied in a particular configuration, other embodiments may be embodied in the same way. Various modifications and changes are possible that would be obvious to those skilled in the art who benefit from this disclosure. It is intended to encompass all such modifications and changes. Therefore, the above description should be considered in an illustrative rather than restrictive sense. [Brief explanation of the drawing]

[0068] [Figure 1] This is a schematic diagram of a reactor support structure according to several embodiments. [Figure 2] Several embodiments of a lower core support structure for a core-vessel interface are shown. [Figure 3] Several embodiments of a lower core support structure for a core-vessel interface are shown. [Figure 4] The following describes a lower core support structure having a suspension tension skirt for the core-vessel interface, according to several embodiments. [Figure 5] Several embodiments of a lower core support structure having multiple ribs are shown. [Figure 6] Several embodiments of a lower core support structure independent of the reactor vessel are shown. [Figure 7] The following shows a lower core support structure in a bottom-supported vessel configuration according to several embodiments. [Figure 8] The following are some embodiments of a core support structure configured to be suspended from the reactor head. [Figure 9] Several embodiments of a core support structure that utilizes a cartridge to connect the core support to the control rod support are shown. [Figure 10] The load paths through the lower core support structure and reactor vessel according to several embodiments are shown. [Figure 11] Several embodiments of a cartridge core support structure that supports the core independently of the reactor vessel are shown. [Figure 12] Several embodiments of a cartridge module are shown.

Claims

1. In the manufacturing facility, the steps include manufacturing the reactor vessel, In the aforementioned manufacturing facility, the steps include manufacturing a core barrel, In the aforementioned manufacturing facility, the steps include manufacturing the reactor core, The manufacturing equipment includes the steps of manufacturing a control element drive system, In the manufacturing facility, the steps include assembling the control element drive system and the core in the core barrel to form a core module, The steps include transporting the aforementioned core module to the construction site, The manufacturing equipment includes the steps of manufacturing a reactor vessel head to be attached to the upper end of the reactor vessel, A step of assembling the reactor vessel head together with a control element support structure, wherein the control element support structure is attached to the reactor vessel head and configured to hold one or more control elements, A step of attaching the core barrel to the control element support structure, wherein the core barrel is suspended from the control element support structure, and the control element support structure is configured to support the weight of one or more control elements, the core barrel, and the core, A method for constructing a nuclear reactor, comprising the steps of: connecting the core barrel to the lower part of the reactor vessel and constructing a lower core support structure that restricts relative motion between the core barrel and the reactor vessel.

2. A method for constructing a nuclear reactor according to claim 1, further comprising the step of transporting the reactor vessel to the construction site.

3. A method for constructing a nuclear reactor according to claim 2, further comprising the step of installing the reactor vessel in a reactor building.

4. A method for constructing a reactor according to claim 3, further comprising the step of arranging the core module inside the reactor vessel.

5. A method for constructing a reactor according to claim 4, further comprising the step of coupling the core module to the reactor vessel head.

6. A method for constructing a nuclear reactor according to claim 5, further comprising the step of coupling the control element drive system to the reactor vessel head.

7. A method for constructing a nuclear reactor according to claim 1, wherein the step of manufacturing the core barrel includes the step of forming the core barrel into a cylindrical shape.

8. A method for constructing a nuclear reactor according to claim 6, wherein the core barrel receives the core and supports the weight of the core.

9. A method for constructing a nuclear reactor according to claim 1, wherein the control element drive system is inserted into the core barrel and supported by the core barrel.

10. A reactor vessel head having a first opening, A control element support structure attached to the reactor vessel head at the first opening, comprising a control element support structure that supports a plurality of control elements, It comprises a support cylinder having an upper and lower part, which supports the core internally, The upper part is attached to the control element support structure, and the support cylinder is supported by the control element support structure. The support cylinder is suspended from the control element support structure within a reactor vessel having a plurality of control elements, and the control element support structure supports the weight of each of the plurality of control elements, the support cylinder, and the reactor core. A reactor core support system further comprising a lower core support structure that is removably coupled to the lower part of the support cylinder, the lower core support structure engaging with the lower part of the reactor vessel to restrict the lateral movement of the support cylinder relative to the reactor vessel.

11. The reactor core support system according to claim 10, further comprising a control element support system for inserting and withdrawing a plurality of control elements from the reactor core, wherein the control element support system is attached to the support cylinder.

12. The reactor core support system according to claim 10, wherein the reactor core is located inside a support cylinder, and the entire weight of the reactor core is supported by the reactor vessel head via the support cylinder.

13. The reactor core support system according to claim 10, further comprising a fuel element handling system for loading and unloading fuel elements from the reactor core, wherein the fuel element handling system is mounted on a support cylinder.

14. A reactor vessel head having a first opening, A control element support structure attached to the reactor vessel head at the first opening, comprising a control element support structure that supports a plurality of control elements, It comprises a support cylinder having an upper and lower part, which supports the core internally, The upper part is attached to the control element support structure, and the support cylinder is supported by the control element support structure. The support cylinder is suspended from the control element support structure within a reactor vessel having a plurality of control elements, and the control element support structure supports the weight of each of the plurality of control elements, the support cylinder, and the reactor core. The support cylinder is further coupled to a lower core support structure, the lower core support structure engaging with the lower part of the reactor vessel to restrict the lateral movement of the support cylinder relative to the reactor vessel. The reactor core support system comprises a lower core support structure comprising a conical support portion and a cylindrical support portion connected by a transition portion.

15. The reactor core support system according to claim 14, wherein the lower core support structure further comprises one or more vertical ribs that are coupled to the conical support portion to provide additional rigidity and stability.

16. The reactor core support system according to claim 10, wherein the support cylinder is configured to expand radially and axially while restricting lateral movement to maintain alignment with the plurality of control elements.

17. The reactor core support system according to claim 10, wherein the support cylinder is coupled to the control element support structure such that seismic forces acting on the reactor vessel head cause substantially the same movement of the support cylinder and the plurality of control elements, and maintain the alignment of the reactor core and the plurality of control elements.

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