Mechanical support for the micro reactor core

Abstract

A reactor core mechanical support bracket is disclosed that includes a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging the spring to compress and release the spring as the shaft moves in and out of the housing, a shaft travel pin to limit movement of the shaft, and a flange for mounting the support bracket to a canister of a nuclear reactor, the shaft including a plug configured to connect with a reactor core component.

Description

Technical Field

[0001] Cross - Reference to Related Applications This application claims the benefit of U.S. Provisional Patent Application No. 17 / 156,977, filed on January 25, 2021, entitled "MICRO - RACTOR CORE MECHANICAL SUPPORT", the entire disclosure of which is incorporated herein by reference under 35 U.S.C. § 119(e).

[0002] This disclosure generally relates to nuclear power generation, and more particularly to an improved device configured to mechanically support the core of a nuclear reactor.

[0003] Statement Regarding Federally Sponsored Research and Development This disclosure was made with government support under Contract No. DE - NE0008853 with the Department of Energy. The United States Government has certain rights in this disclosure.

Summary of the Invention

[0004] The following summary is provided to facilitate understanding of some innovative features specific to the aspects disclosed in this application and is not intended as a complete description. To fully understand the various aspects of this disclosure, it is necessary to consider the entire specification, claims, and abstract of this application comprehensively.

[0005] In one aspect, the disclosure provides a mechanical support bracket for a nuclear reactor core. The support bracket includes a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging the spring to compress and release the spring when entering and exiting the housing, a shaft travel pin that limits the movement of the shaft, and a flange for attaching the support bracket to a canister of the nuclear reactor. The shaft further includes a plug portion configured to interface with nuclear reactor core component equipment.

[0006] In another embodiment, the Disclosure provides a reactor comprising a core, a canister for containing the core therein, and a core mechanical support system configured to be attached to the canister, the core mechanical support system comprising a radial core mechanical support system for supporting the core radially and an axial core mechanical support system for supporting the core axially.

[0007] In yet another embodiment, the Disclosure provides a nuclear reactor, which includes a core, a canister for containing the core therein, a core mechanical support system configured to be attached to the canister, a radial reflector disposed within the canister, a support beam disposed between the inner wall of the canister and the radial reflector, and plates disposed at each end of the core, wherein the axial core mechanical support system is configured to connect to the plates. The radial support bracket and the axial support bracket each include a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when moving in and out of the housing, the shaft having a socket configured to connect to the support beam or the plates, a shaft travel pin to restrict the movement of the shaft, and a flange for attaching the support bracket to the canister. The core mechanical support system includes a radial core mechanical support system for supporting the core radially and an axial core mechanical support system for supporting the core axially. The support beams are positioned along the axial length of the reactor core. The radial core mechanical support system includes radial support brackets configured to connect with the support beams.

[0008] Furthermore, please understand that one or more of the forms, representations of forms, or examples described below can be combined with one or more of the other forms, representations of forms, or examples described below.

[0009] The above summary is illustrative and not intended to limit in any sense. Additional aspects, embodiments, and features other than those described above will become apparent by referring to the accompanying drawings and the detailed description below. [Brief explanation of the drawing]

[0010] Various features of the embodiments described in this application are specifically described in the attached claims. However, various embodiments of the operating mechanism and method and their advantages will be better understood by the following description with reference to the attached drawings.

[0011] [Figure 1] A perspective view of a reactor including a core mechanical support system, based on at least one non-limiting aspect of this disclosure.

[0012] [Figure 2] Figure 1 is a longitudinal cross-sectional view of a reactor, based on at least one non-limiting aspect of this disclosure.

[0013] [Figure 3] These are cross-sectional views of the reactor shown in Figures 1 and 2, based on at least one non-limiting aspect of the present disclosure.

[0014] [Figure 4] Figures 1-3 show perspective longitudinal and transverse cross-sectional views of a reactor, based on at least one non-limiting aspect of this disclosure.

[0015] [Figure 5] This is a perspective view of a radial and axial support bracket based on at least one non-limiting aspect of the present disclosure.

[0016] [Figure 6] A perspective view of a disc spring based on at least one non-limiting aspect of the present disclosure.

[0017] [Figure 7] Figures 1-4 show perspective longitudinal cross-sectional views of a reactor core, based on at least one non-limiting aspect of this disclosure.

[0018] The same reference numerals refer to corresponding parts in several drawings. The embodiments described herein illustrate various aspects of the claimed subject matter in one aspect, and such embodiments are not to be construed in any way as limiting the scope of the claimed subject matter. [Modes for carrying out the invention]

[0019] The applicant of this application also owns the following U.S. provisional patent applications filed on the same date, the disclosures of which are incorporated in their entirety by reference into this application. • U.S. Patent Application No. 17 / 080,241, filed on October 26, 2020, entitled "ENHANCED GRAPHITE NEUTRON REFLECTOR WITH BERYLLIUM OXIDE INCLUSIONS" • U.S. Patent Application No. 17 / 084,365, filed on October 29, 2020, entitled "DEVICES, SYSTEMS, AND METHODS FOR ADJUSTING THE OUTPUT OF A REACTOR CORE," and U.S. Patent Application No. 17 / 084,403, filed on October 29, 2020, entitled "DEVICES, SYSTEMS, AND METHODS FOR CONFIGURING THE LAYOUT OF UNIT CELL OF A REACTOR CORE".

[0020] Prior to describing various aspects of a nuclear reactor including a core mechanical support system, it should be noted that the exemplary embodiments illustrated herein are not limited to the details of the structure and arrangement of the components illustrated in the accompanying drawings and description in their application or use. Exemplary embodiments may be implemented or incorporated in other aspects, variations, and modifications and may be practiced or carried out in various ways. Further, unless otherwise specified, the terms and expressions employed herein are selected for the purpose of describing the embodiments for the convenience of the reader and are not intended to limit the embodiments. Also, it will be understood that one or more of the aspects, expressions of aspects, and / or embodiments described below may be combined, without limitation, with any one or more of the other aspects, expressions of aspects, and / or embodiments described below.

[0021] In various aspects, the present disclosure relates to a nuclear reactor including a core mechanical support system for supporting a core and maintaining the core in a predetermined position. In one aspect, the nuclear reactor is an all-solid micro nuclear reactor including an active core, a reflector, and a core mechanical support system. The core provides nuclear, thermal, and mechanical interfaces for, for example, fuel, heat removal systems, shutdown systems, reactivity control systems, instrumentation, etc. The core is disposed within a pressure-resistant canister. The core mechanical support system is configured to mechanically support the nuclear reactor core and associated component equipment without limitation in all events such as transportation and handling, operation, accidents, off-design accident conditions, etc., and keep them in a predetermined position and configuration. In order to avoid excessive restraint and excessive stress on the core component equipment, the thermo-mechanical design of the core mechanical support system can cope with various static and dynamic loads, thermal expansion differences, and shape changes (expansion, contraction, etc.) of the core component equipment during irradiation.

[0022] Next, referring to the figures, FIG. 1 is a perspective view of a nuclear reactor 10 including a core mechanical support system based on at least one non-limiting aspect of the present disclosure. In one aspect, the nuclear reactor 10 is an all-solid micro nuclear reactor. The nuclear reactor 10 includes a core 100 (FIGS. 2-4 and 7), a reflector 106 (FIGS. 2-4 and 7), and a core mechanical support system, all of which are housed within a pressure canister 120. The core 100, reflector 106, and other components within the canister 120 are mechanically sealed by front and rear canister closure partitions 122, 124.

[0023] FIG. 2 is a longitudinal cross-sectional view of the nuclear reactor 10 shown in FIG. 1 based on at least one non-limiting aspect of the present disclosure. Referring to FIGS. 1 and 2, the core 100 is housed within the canister 120. The core 100 includes a plurality of reactivity control cells 104 configured to accommodate a plurality of reactivity control rods 115. By the collective functioning of the shutdown control rods, the core 100 can be prevented from reaching critical temperature in case of a loss of power and / or a criticality accident in the nuclear reactor 10, in order to control the nuclear fission occurring within the core 100. In various non-limiting aspects, the amount of nuclear fission within the core 100 can be reduced or completely eliminated, and in the latter case, the core 100 can be shut down. The reactivity control rods 115 contemplated by the present disclosure can include neutron absorbers and are configured to be inserted into the reactivity control cells 104 to slow down and / or stop the nuclear reaction in case of an emergency. The reactivity control configuration of the core 100 represents the characteristics of a state-of-the-art micro nuclear reactor with excellent portability and a wider range of commercial applications. Therefore, with the rise of micro nuclear reactors, the popularization of nuclear power technology is promoted, and the risk of major harmful events associated with the popularization can be minimized.

[0024] The reactor core 100 includes a graphite core block 130, a radial reflector 106 surrounding the graphite core block 130, and other components described herein. According to an unspecified embodiment of Figure 2, the reflector 106 may include a fixed portion and a movable portion. The movable portion may be a control drum including sections of a reflector (e.g., beryllium oxide [BeO]) and an absorbent (e.g., boron carbide [B4C]). The drum functions as both a reflector and an absorbent by rotation relative to the graphite core block. In one embodiment, the reflector 106 includes one or more plates made of a thick neutron moderator configured to substantially surround the graphite core block 130. The reactor core 100 provides nuclear, thermal, and mechanical interfaces to fuel, a heat removal system, a shutdown / reactivity control system, instrumentation, etc. The reactor core 100 is located within a pressure-resistant canister 120 and surrounded by the reflector 106. The reactor core 100 and its associated components are mechanically supported by a mechanical support system under all conceivable conditions, including transportation and handling, operation, accidents, and non-design accident conditions.

[0025] The core mechanical support system, comprising a radial support system 125 and an axial support system 127, supports and maintains the core 100 in a predetermined position and configuration under a variety of anticipated events, including transportation and handling, operation, accidents, and off-design accident conditions, without limitation. To avoid excessive constraint and stress on the core 100 and associated components, the thermomechanical design of the core mechanical support system can accommodate various static and dynamic loads, thermal expansion differences, and morphological changes (expansion, contraction, etc.) of core components during irradiation. The core support system separates the axial and radial support of the horizontally positioned cylindrical core 100 (to the extent practically possible). In this embodiment, radial dimensional changes of the core 100 components do not significantly affect the axial reaction forces, and vice versa.

[0026] The radial support system 125 includes a number of radial support brackets 126 surrounding the core 100, and the axial support system 127 includes a number of axial support brackets 128 located at both ends of the core 100. The radial support brackets 126 and axial support brackets 128 support and maintain the core 100 in predetermined radial and axial positions during transport and handling, operation, accidents, and off-design accident conditions. The radial support brackets 126 distribute the load of the core 100 uniformly by connecting to support beams 132 that engage with the radial reflector 106, as will be described in more detail later. The support beams 132 are positioned between the inner wall of the canister 120 and the reflector 106. The support beams 132 are positioned along the axial length of the core 100. The axial support brackets 128 distribute the load of the core 100 uniformly by connecting to plates 148, as will be described in more detail later. Referring here to Figures 5 and 6, each of the radial / axial support brackets 126, 128 includes at least one spring 134 compressed by a shaft 136 that moves in and out of the housing 138 of the radial / axial support bracket 126, 128. The radial / axial support brackets 126, 128 connect to the support beam 132 and / or plate 148 at the connecting insert 140 of the radial / axial support brackets 126, 128. In the illustrated embodiment, each radial / axial support bracket 126, 128 includes four springs 134, and each spring 134 includes a number of washers 146.

[0027] Figure 3 is a cross-sectional view of the reactor 10 shown in Figures 1 and 2, based on at least one non-limiting aspect of the present disclosure. Figure 4 is a perspective longitudinal and transverse cross-sectional view of the reactor 10 shown in Figures 1-3, based on at least one non-limiting aspect of the present disclosure. Referring now to Figures 1-4, according to one non-limiting aspect, the reactor core 100 comprises a plurality of unit cells 102, which together form a hexagonal core boundary. Each unit cell 102 can be configured to house a heat pipe 113 and a certain amount of fuel (e.g., in the form of rods 111 and / or stack configurations), and together they can generate nuclear power and manage thermal energy throughout the reactor core 100. In some non-limiting aspects, one or more unit cells 102 may further include a moderator configuration that can slow down neutrons emitted from the fuel. The unit cells 102 can be arranged such that the reactor core 100 includes a hexagonal geometry. However, in other non-limiting embodiments, the unit cells 102 may be arranged such that the core 100 includes one of a number of different geometric configurations, depending on the intended use and / or user preference.

[0028] Referring to Figures 3 and 4, the reflector 106 may further include a plurality of control drums 108 configured to house neutron absorbers and reflectors. In the event of a reactor and / or power outage, the control drums 108 may be rotated inward toward the core 100 to allow the absorbers to shut down the reactor. In some non-limiting embodiments, the reflector 106 may further include a gamma-ray shield configured to provide gamma-ray and neutron shielding. The reflector can further reduce radiation by configuring itself to substantially surround the neutron shield, the core 100, and the in-reactor components 102, 104, 111, 113, 115. As shown in the non-limiting embodiments of Figures 3 and 4, the reflector 106 may be arranged to surround a plurality of hexagonally arranged unit cells 102 in a circular fashion. However, in other non-limiting embodiments, the reflectors 106 may be arranged around a plurality of unit cells 102 to form one of a number of different geometric configurations, depending on the intended use and / or user preference.

[0029] Continuing to refer to Figures 3 and 4, as a means of controlling and promoting a desired amount of heat transfer, the reflector 106 may be divided so that a gap is created between the unit cell 102 and the reflector 106. For example, the reflector 106 may be formed from multiple module plates and integrated to form the aforementioned gap. However, in other non-limiting embodiments, the reflector 106 can be formed integrally. Furthermore, the reflector 106 may be configured to extend along the axial direction that defines the length of the core 100. Multiple unit cells 102 may also be configured to extend along the entire length of the core 100.

[0030] Some small reactors function as "nuclear batteries," generating electricity using energy from the nuclear fission of nuclear materials (such as uranium in oxide, metal, and silicide forms). Since the unit cell is configured to accommodate any form of fuel, including such radioactive isotopes, the length L of the core 100 can be made to correspond to the fuel mass required to maintain the desired power output and criticality of the reactor. The increasing versatility of microreactors means that, as an additional and / or alternative, the core 100 must be configurable for a wide variety of applications, many of which may have size and / or weight constraints. Therefore, the design of the core 100 allows for a specific length L to be configured to meet the power, size, and / or weight requirements of the reactor.

[0031] Continuing to refer to Figures 3 and 4, a hexagonal configuration can be established in an unlimiting embodiment of the core 100 by identifying the arrangement of the multiple unit cells 102 and the multiple reactivity control cells 104. It is also clear that each of the multiple unit cells 102 and each of the multiple reactivity control cells 104 similarly include a hexagonal configuration. However, it should be understood that the hexagonal configuration is depicted solely for illustrative purposes. Thus, this disclosure also intends other unlimiting embodiments in which the unit cells 102 and reactivity control cells 104 include any number of geometric configurations (e.g., squares, circles, triangles, rectangles, pentagons, octagons), and the cells are arranged so that the core 100 may include any number of geometric configurations.

[0032] Referring further to Figures 3 and 4, multiple unit cells 102 and multiple reactivity control cells 104 can be arranged radially, thereby defining the radial dimensions of the core 100. Specifically, the core 100 shown in Figures 3 and 4 includes 48 unit cells 102 and 13 reactivity control cells 104. However, this disclosure also intends other non-limiting embodiments in which the core 100 may include any number of unit cells 102 and reactivity control cells 104. It will be understood that the number of unit cells 102 or reactivity control cells 104 in the core 100 can be easily added or removed without dramatically changing the design of the core 100, so that the core 100 can be easily scaled according to the intended application and / or user preferences. Thus, it is also easy to adjust the output of the core 100 design to suit many applications and requirements. For example, the radial and / or axial dimensions of the core 100 can be changed by increasing or decreasing the unit cells 102 or reactivity control cells 104 of the core 100. Since the unit cells are configured to contain fuel containing radioactive isotopes, the output of the core 100 can be changed by increasing or decreasing the size of the radial dimensions. Thus, the radial dimensions of the core 100 can be made to correspond to the desired output of the reactor, depending on the intended application and / or user preference. As an additional and / or alternative, the radial dimensions of the core 100 can be specially configured to meet a number of size and / or weight requirements that vary depending on the application. Thus, changes in the radial and / or axial dimensions of the core 100 can be accommodated by modifying the core mechanical support system by increasing or decreasing the radial / axial support brackets 126, 128 of the radial support system 125 and the axial support system 127.

[0033] The term “radial” as used in this disclosure should be understood to refer to any direction extending from the center of the core 100 when viewed from above. Therefore, the use of the term “radial” is not limited to circular or circular-like configurations, and should not be interpreted as meaning that the core 100 in Figures 1-4 is limited to circular or circular-like configurations. For example, this disclosure also intends non-limiting embodiments, including those in which the cross-sectional configuration of the core 100 is rectangular. In such embodiments, the core 100 may include one or more radial dimensions of different lengths. Referring to Figures 2 and 4, the multiple unit cells 102 and the multiple reactivity control cells 104 can be integrally formed from a solid material (e.g., graphite) block 130. Thus, the heat pipe channels, fuel channels, moderator channels, and / or similar internal features of the unit cell 102 can be integrally formed by hollowing out the solid material block. However, in other non-limiting embodiments, the design of the core 100 can be made more adaptable by modularizing each of the multiple unit cells 102 and each reactivity control cell 104 and integrating them into the core block 130.

[0034] In any case, the core 100 can be readily manufactured to include any number of unit cells 102 and / or reactivity control cells 104. This allows for easy scaling of the core 100 design, enabling significant improvements over known reactors. For example, by changing the number of unit cells 102 and reactivity control cells 104, the radial dimension R and axial length L (Figure 1) of the core 100 can be changed, thereby modifying the power and flexibility for applications with unique power and / or space constraints. However, since the design of the core 100 remains fundamentally unchanged, production volume and performance can be predicted even with differences in power and size. This capability also helps reduce the amount of recurring engineering work required for designing new applications, ensuring consistency in manufacturing and standardizing components. While the core 100 can be scaled as a means of adjusting its power, scaling requires further consideration of the rated power of the implemented heat pipes, the appropriate number of reactivity control rods required for the tuned power, and the effectiveness of the control drum.

[0035] In other non-limiting embodiments, the unit cell 102 may further include a moderator channel configured to house a moderator for the core 100 (e.g., a hydride-based moderator, such as BeO), which may be configured to slow the propagation of neutrons emitted from the fuel inserted into the plurality of fuel channels 110. Alternatively and / or additionally, the unit cell 102 may include additional features configured to house other instrumentation for the core 100.

[0036] Continuing to refer to Figures 3 and 4, the unit cell 102 may also include features configured to accommodate a neutron absorber that can slow down the nuclear reactions occurring in the fuel channel 110 of the unit cell 102. Thus, the power distribution and radial power peaking of the unit cell 102, and consequently the power peaking of the core 100 itself, can be further tuned through the influence of the neutron absorber. In some non-limiting embodiments, the design of the core 100 can be adapted to applications where the core 100 is not subject to stringent transport requirements. As an alternative and / or additional measure, the core 100 can use high-density fuel. In such embodiments, the axial power peaking coefficients and axial power distribution of the unit cell 102 and the core 100 can be controlled separately by changing the fuel enrichment in the fuel channel 110 of the unit cell 102 or by adding a flammable absorber.

[0037] Similarly, the reflector 106 may include a plurality of reflectors 106, including a control drum 108, and may be configured to extend along at least a portion of the length L of the core 100. Of course, in some non-limiting embodiments, the reflectors may also be formed integrally. In this case as well, the reflectors may be specifically configured to form gaps that are advantageous for promoting and enhancing heat transfer throughout the core 100.

[0038] According to non-limiting embodiments shown in Figures 1-4, the reactor core 100 can be assembled to include fuel 111 (e.g., rods and / or stacks), heat pipes 113, and reactivity control rods 115 arranged throughout a plurality of unit cells 102 and reactivity control cells 104. Specifically, the fuel 111 can be arranged throughout the fuel channels 110 of one or more unit cells 102, the heat pipes 113 can be arranged throughout the heat pipe channels 112 (Figure 3) of one or more unit cells 102, and the reactivity control rods 115 can be arranged throughout the reactivity control channels (not shown) of one or more reactivity control cells 104. According to some non-limiting embodiments, the fuel 111 and heat pipes 113 are configured to extend over a predetermined length L of the reactor core 100. In other non-limiting embodiments, the fuel 111 and heat pipes 113 are configured to extend further beyond a predetermined length L of the reactor core to facilitate the installation of downstream external connections and / or equipment (e.g., power systems, condensers, structural supports). This design allows the core 100 to be customized according to its intended application and user preferences, thus achieving versatility to meet customer needs. However, reliability and predictability in the manufacture and operation of the core 100 can be maintained by evaluating such modifications based on the manufacturability of the underlying nuclear physics and / or core 100 design. In other words, by making the core 100 modular, the fuel 111 and heat pipes 113 can be specially configured to meet specific power requirements and / or structural configurations without reinventing the basic core 100 design and incurring inherent development risks.

[0039] Continuing to refer to Figures 1-4, the reactor core 100 may further include a plurality of reactivity control rods 115 configured to be positioned across one or more of a plurality of reactivity control cells 104. For example, a reactivity control cell 104 may include reactivity control rods or reactivity control channels similar to the fuel channels 110 and / or heat pipe channels 112, but specifically configured to accommodate the reactivity control rods 115. As already described, each reactivity control rod 115 may be configured to include a neutron absorber to slow and / or stop nuclear reactions within the reactor core 100 in an emergency. The collective function of the reactivity control rods 115 can prevent the reactor core 100 from reaching critical temperature or prompt criticality in the event of a reactor and / or power supply failure. Thus, the rise of microreactors will accelerate the spread of nuclear technology and increase the priority of safety.

[0040] Figure 5 is a perspective view of radial and axial support brackets 126, 128 based on at least one non-limiting aspect of the present disclosure. The main components of the core support system are radial / axial support brackets 126, 128, which include preloaded spring blocks. Each spring block of the radial / axial support brackets 126, 128 includes a number of springs 134, as detailed in Figure 6. Each radial / axial support bracket 126, 128 includes a number of springs 134 located within a bracket housing 138. Each spring 134 is preloaded (compressed) by a shaft 136, which is slidably positioned within the bracket housing 138 and connected to a support beam 132 (Figures 2-4) at a connecting insert 140. The shaft 136 engages with the springs 134 and is configured to compress and release the springs 134 as the shaft 136 moves in and out of the bracket housing 138. The shaft travel pins 142, which restrict the movement of each bracket shaft 136, also prevent the rotation of the bracket shafts 136. The radial / axial support brackets 126, 128 can be attached to the external canister 120 (Figures 1, 2, and 4) by the support bracket flanges 144. A number of radial support brackets 126 are arranged around the core 100 (Figures 1-4), and a number of axial support brackets 128 are arranged at both ends of the core 100 to create the desired radial and axial support of the core 100. The reaction forces corresponding to the preload of the spring blocks of the radial / axial support brackets 126, 128 act against the inner wall of the pressure canister 120. In one embodiment, the bracket body, including the housing 138, bracket flanges 144, shafts 136, and shaft travel pins 142, may be made of 304 stainless steel. The structural material may also be changed depending on environmental conditions.

[0041] Figure 6 is a perspective view of a Belleville washer spring 134 based on at least one non-limiting aspect of the present disclosure. In one aspect, the spring in the radial / axial support brackets 126, 128 of the preloaded spring block may be a disc spring, such as the Belleville washer spring 134. The Belleville washer spring 134 can be made of a high-strength, corrosion-resistant age-hardening alloy such as nickel-chromium, which can be easily machined into complex parts. In one aspect, the Belleville washer spring 134 is made of alloy 718. Referring to Figures 5 and 6, the radial / axial support brackets 126, 128 may employ a variety of other configurations and should not be limited to the disclosed circumstances. Other aspects of the bracket housing 138 or bracket body are configured to house a compressed Belleville washer spring 134 via a shaft 136 having a shaft travel pin 142. The number of Belleville washer springs 134 and the number of Belleville washers 146 that make up the spring vary. The Belleville washers 146 are conical in shape, which gives the washer the characteristics of a spring. The dimensions of the individual parts can also be changed. The structural materials can also be changed depending on the environmental conditions. In various embodiments, the Belleville washer 146 is a type of washer-shaped spring. The Belleville washer spring 134 may be called a coned-disc spring, conical spring washer, disc spring, Belleville spring, or cupped spring washer, and has a conical shell to which a static or dynamic load can be applied along its axis.

[0042] It will be understood that the number of radial / axial support brackets 126, 128 and the characteristics of the preload springs 134 can be selected so that the “manufactured” preload force ranges from 1g to 10g of acceleration. In one embodiment, taking into account the geometric and dimensional changes induced by thermal expansion and irradiation, the deflection of the spring pack 134 is sufficient to compensate for the expansion differences between the core 100, the canister 120, and the components of the radial / axial core support systems 125, 127.

[0043] Figure 7 is a perspective longitudinal cross-sectional view of the reactor core 100 shown in Figures 1-4, based on at least one non-limiting aspect of the present disclosure. The core 100 includes a core mechanical support system, which includes radial / axial core support systems 125, 127, including radial / axial support brackets 126, 128 acting in the axial (L) and radial (R) directions, as shown in the figure. In this configuration, the core 100 is assembled from a graphite core block 130, fuel rods (not shown), heat pipes (not shown), and stationary radial reflectors 106, which are located within a pressurized canister 120. The load is uniformly distributed radially by connecting a radial core support system 125, which includes a series of radial support brackets 126 equipped with preloading springs, to the core components via beams 132. The load is uniformly distributed axially by connecting an axial core support system 127, which includes a series of axial support brackets 128 equipped with preload springs, to the plate 148. The axial support brackets 128 are engageable with the plate 148 via shafts 136 and / or inserts 140.

[0044] Referring to Figures 5-7, the radial core support system 125 includes a series of radial support brackets 126 equipped with preloaded springs, and the load is uniformly distributed by connecting the radial support brackets 126 to the core 100 components using beams 132. The radial support brackets 126 are positioned along the core 100 and are uniformly distributed axially and circumferentially on the wall surface of the canister 120. One side of the radial support bracket 126 is attached to the wall of the canister 120 by a flange 144. The other side of the radial support bracket 126 connects to beams 132 positioned along the axial length (L) of the core 100 within the canister 120. By being slidably connected to the core 100, beams 132 are able to accommodate the expansion difference between the graphite core block 130 components, the canister 120, and the radial support brackets 126 and the spring packs 134. The number and characteristics of the spring packs 134, which are placed within the housing 138 of the radial bracket 126, are selected based on the required preload, the expected external load, and the combined dimensional changes due to radial thermal expansion differences and irradiation-induced effects.

[0045] Continuing to refer to Figures 5-7, the axial support bracket 128 is attached to the canister bulkheads 122 and 124 and exerts force on the core graphite block 130 across the plate 148. The sliding interface between the axial support bracket 128 and the plate 148 accommodates the expansion difference between the core graphite block 130 and the canister 120. The number and characteristics of the spring packs 134, which are located within the housing 138 of the axial bracket 128, are selected based on the required preload, the expected external load, and the combined dimensional changes due to the axial thermal expansion difference and irradiation-induced effects.

[0046] Various aspects of the subject matter described in this application are described in the following numbered embodiments.

[0047] [Example 1] A reactor core mechanical support bracket comprising a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when moving in and out of the housing, the shaft further having a socket configured to connect to a reactor core component, a shaft travel pin to restrict the movement of the shaft, and a flange for attaching the support bracket to a reactor canister.

[0048] [Example 2] The reactor core mechanical support bracket according to Example 1, wherein the insertion portion is configured to connect to a support beam arranged axially along the length of the reactor core.

[0049] [Example 3] A reactor core mechanical support bracket according to any one or more of Examples 1 to 2, wherein the insertion portion is configured to connect to a plate located at any end of the reactor core.

[0050] [Example 4] A reactor core mechanical support bracket according to one or more of Examples 1 to 3, wherein the spring is a disc spring including a disc spring washer.

[0051] [Example 5] The reactor core mechanical support bracket according to Example 4, comprising a plurality of disc springs, each of which includes a plurality of stacked disc spring washers.

[0052] [Example 6] The reactor core mechanical support bracket according to any one of Examples 1 to 5, wherein the housing is made of stainless steel.

[0053] [Example 7] A reactor core mechanical support bracket according to one or more of Examples 1 to 6, wherein the spring is made of alloy 718.

[0054] [Example 8] A nuclear reactor comprising a core, a canister for containing the core, and a core mechanical support system configured to be attached to the canister, wherein the core mechanical support system comprises a radial core mechanical support system for supporting the core radially and an axial core mechanical support system for supporting the core axially.

[0055] [Example 9] A reactor according to Example 8, comprising a radial reflector disposed within the canister, and a support beam disposed between the inner wall of the canister and the radial reflector, the support beam being axially oriented along the length of the core, wherein the radial core mechanical support system comprises a radial support bracket configured to connect to the support beam.

[0056] [Example 10] A reactor according to Example 9, wherein the radial support bracket comprises a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when entering and leaving the housing, and further having an insertion portion configured to connect to the support beam, a shaft travel pin to restrict the movement of the shaft, and a flange for attaching the support bracket to the canister.

[0057] [Example 11] A reactor according to any one or more of Examples 8 to 10, further comprising plates positioned at each end of the core, wherein the axial core mechanical support system is configured to connect to the plates.

[0058] [Example 12] A reactor according to Example 11, wherein the axial core mechanical support system comprises a housing, a spring disposed within the housing, a shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when moving in and out of the housing, and further configured to connect to the plate, a shaft travel pin to restrict the movement of the shaft, and a flange for attaching the support bracket to the canister.

[0059] [Example 13] The reactor according to Example 12, wherein the shaft comprises an insert portion configured to engage with the plate.

[0060] [Example 14] The reactor according to one or more of Examples 8 to 13, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the core in the axial direction by applying a force in advance that corresponds to an acceleration of 1g to 10g.

[0061] [Example 15] A nuclear reactor comprising a core, a canister for containing the core therein, and a core mechanical support system configured to be attached to the canister, wherein the core mechanical support system comprises a radial core mechanical support system for supporting the core radially and an axial core mechanical support system for supporting the core axially, the core further comprising a radial reflector disposed within the canister and a support beam disposed between the inner wall of the canister and the radial reflector and axially oriented along the length of the core, wherein the radial core mechanical support system comprises a radial support bracket configured to connect with the support beam. A reactor comprising a beam and plates positioned at each end of the core, wherein the axial core mechanical support system is configured to connect to the plates, and the radial support bracket and the axial support bracket each comprise a housing, a spring positioned within the housing, a shaft slidably positioned within the housing and engaging with the spring to compress and release it when moving in and out of the housing, the shaft further comprising a socket configured to connect to the support beam or the plate, a shaft travel pin to restrict the movement of the shaft, and a flange for attaching the support bracket to the canister.

[0062] [Example 16] The reactor according to Example 15, wherein the shaft comprises an insert portion configured to engage with the support beam or the plate.

[0063] [Example 17] The reactor according to any one or more of Examples 15 to 16, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the core in the axial direction by applying a force in advance that corresponds to an acceleration of 1g to 10g.

[0064] Numerous specific details are provided to enable a deep understanding of the overall structure, function, manufacture, and use of the embodiments described in this disclosure and illustrated in the accompanying drawings. To avoid obscuring the embodiments described in this disclosure, well-known operations, components, and elements are not described in detail. Readers should understand that the embodiments described and illustrated in this application are non-limiting examples, and therefore, the specific structural and functional details disclosed in this application may be representative and illustrative. These embodiments may be modified and altered without departing from the claims of this application. Furthermore, terms such as forward, backward, left, right, upward, and downward are used for convenience only and should not be interpreted restrictively.

[0065] In this disclosure, the same reference numeral refers to the same or corresponding part across several drawings.

[0066] All patents, patent applications, publications, or other disclosures referenced herein are incorporated by reference in their entirety, just as each reference is expressly incorporated by reference herein. All references and any materials, or any part thereof, described herein as being incorporated by reference are incorporated only to the extent that they do not conflict with existing definitions, statements, or other disclosures contained herein. Accordingly, disclosures contained herein supersede any materials incorporated by reference that conflict with such disclosures, to the extent necessary, and disclosures expressly contained herein take precedence.

[0067] This disclosure has been described with reference to various embodiments and exemplary aspects. The embodiments described herein should be understood as exemplary features of various aspects of the disclosed invention at various degrees of detail. Accordingly, unless otherwise specified, to the extent possible, one or more features, elements, components, constituents, parts, structures, modules and / or aspects in the disclosed embodiments can be combined, divided, substituted and / or reconfigured with one or more other features, elements, components, constituents, parts, structures, modules and / or aspects in the disclosed embodiments without departing from the scope of the disclosed invention. Accordingly, those skilled in the art will understand that various substitutions, modifications or combinations are possible in any of the exemplary embodiments without departing from the scope of the invention. Those skilled in the art will also recognize many equivalents to the various aspects of the invention described herein when considering this disclosure, or they can simply confirm such equivalents by routine experimentation. Accordingly, this disclosure is limited by the claims and not by the descriptions of the various embodiments.

[0068] A person skilled in the art will understand that, generally, the terms used in this application, particularly in the attached claims (e.g., the main body of the attached claims), are intended to be "open" terms (for example, the term "including" should be interpreted as "including but not limited to," the term "having" as "having at least," and the term "includes" as "including but not limited to"). Furthermore, a person skilled in the art will understand that if a specific number is intended to be stated in an introduced claim, such intention is explicitly stated in that claim, and if such statement is not present, such intention does not exist. For example, to aid understanding, the attached claims may use the introductory phrases "at least one" and "one or more" to introduce the subject matter of the claims. However, the use of such phrases should not be interpreted as suggesting that any particular claim containing such introduced claims is limited to claims containing only one such item, even if the indefinite article "a" or "an" is included in the same claim along with an introductory phrase such as "one or more" or "at least one" (for example, "a" and / or "an" should generally be interpreted as meaning "at least one" or "one or more"). The same applies when a definite article is used to introduce a claim.

[0069] Furthermore, even if a specific number is explicitly stated in the description of the introduced claim, it will be understood by those skilled in the art that such a description should generally be interpreted as meaning "at least the number described" (for example, when "two recitations" is described without other modifiers, it usually means at least two recitations, or two or more recitations). In addition, in cases where a conventional expression similar to "at least one of A, B, and C" is used, such a construction is usually intended in a sense that those skilled in the art would understand (for example, "a system having at least one of A, B, and C" includes, but is not limited to, systems having only A, only B, only C, both A and B, both A and C, both B and C, and / or all of A, B and C). Furthermore, in instances where a conventional expression similar to "at least one of A, B, or C" is used, such construction is usually intended in a sense that a person skilled in the art would understand the conventional expression to be (for example, "a system having at least one of A, B, or C" includes, but is not limited to, systems having only A, only B, only C, both A and B, both A and C, both B and C, and / or all of A, B and C). In general, a person skilled in the art will also understand that disjunctive words and / or phrases representing two or more selective terms, wherever they appear in the specification, claims, or drawings, should be understood to intend the possibility of including one of those terms, either of those terms, or both of those terms, unless the context should dictate otherwise. For example, the phrase "A or B" will generally be understood to include the possibilities of "A," "B," or "A and B."

[0070] Those skilled in the art will understand that, with respect to the attached claims, the actions described herein may generally be performed in any order. Furthermore, while the claims are presented in sequence, it will be understood that the various actions may be performed in a different order than described, or simultaneously. Examples of such alternative orderings may include repetition, interruption, suspension, reordering, augmentation, preliminary, additional, simultaneous, reverse, or other orderings, unless the context requires otherwise. Moreover, terms such as "responsive to," "related to," and other past tense adjectives are not intended to exclude the general forms of these expressions, unless the context requires otherwise.

[0071] It is worth noting that references to “one aspect,” “an aspect,” “an exemplification,” and “one exemplification” mean that the specific features, structures, or properties described in relation to that aspect are included in at least one aspect. Therefore, the phrases “in one aspect,” “in an aspect,” “in an exemplification,” and “in one exemplification,” found in various places throughout this disclosure, do not necessarily all refer to the same aspect. Furthermore, specific features, structures, or properties can be combined in any suitable manner in one or more aspects.

[0072] In this application, singular nouns preceded by "a," "an," and "the" also include plural nouns unless it is clear from the context otherwise.

[0073] As a non-limiting example, the terms used in this application that suggest direction, such as top, bottom, left, right, down, up, front, back, and variations thereof, relate to the geometric arrangement of the elements shown in the accompanying drawings and, unless otherwise stated, do not limit the scope of the claims of this application.

[0074] As used in this disclosure, the terms “about” or “approximately” mean, unless otherwise specified, a tolerance for a particular value as determined by those skilled in the art, which depends to some extent on how the value is measured or determined. In certain embodiments, the terms “about” or “approximately” mean within a range of 1, 2, 3, or 4 times the standard deviation. In certain embodiments, the terms “about” or “approximately” mean within a range of 50%, 200%, 105%, 100%, 9%, 8%, 7%, 6%, 5%, 4%, 3%, 2%, 1%, 0.5%, or 0.05% from a given value.

[0075] In this disclosure, unless otherwise specified, all numerical parameters should be understood to be prefixed and modified in all cases with the term "approximately." Herein, the numerical parameters have variability characteristics inherent to the basic measurement techniques used to determine the numerical values ​​of the parameters. As a minimum, and without the intention of limiting the application of the doctrine of equivalents to the claims, each numerical parameter described herein should be interpreted using at least the number of significant figures reported and with the application of common rounding methods.

[0076] Any numerical range described in this application shall include all fragmentary parts contained within the described range. For example, the range "1 to 100" includes all fragmentary parts between the stated minimum value of 1 and the stated maximum value of 100 (encompassing both the minimum and maximum values). That is, the minimum value is 1 or greater, and the maximum value is 100 or less. Furthermore, all ranges described in this application shall include the endpoints of the described range. For example, the range "1 to 100" includes the endpoints 1 and 100. The maximum limit value described in this disclosure is intended to include all lower limit values ​​contained therein, and the minimum limit value described in this disclosure is intended to include all higher limit values ​​contained therein. Accordingly, the applicant has the right to modify this disclosure, including the claims, to explicitly describe any partial ranges contained within the explicitly described ranges. All such ranges are inherently described in this disclosure.

[0077] Any patent application, patent, non-patent publication, or other disclosure material referenced in this disclosure and / or listed in any application data sheet is incorporated by reference to the extent that the incorporated material does not contradict this application. To that extent, disclosures expressly stated in this application shall take precedence over any material incorporated by reference that contradicts them. Any existing definitions, views, or other disclosures contained herein that contradict them or any part thereof are incorporated by reference, but only to the extent that the incorporated material does not contradict the existing disclosures.

[0078] The words "comprise" and its derivatives (e.g., "comprises," "comprising"), "have" and its derivatives (e.g., "has," "having"), "include" and its derivatives (e.g., "includes," "including"), and "contain" and its derivatives (e.g., "contains," "containing") are non-restrictive linking verbs. That is, a system that "comprises," "has," "includes," or "contains" one or more elements has, but is not limited to having only, those one or more elements. Similarly, an element of a system, device, or apparatus that "comprises," "has," "includes," or "contains" one or more features has, but is not limited to having only, those one or more features.

[0079] In summary, we have described the many advantages that can be obtained by adopting the concepts described herein. The above descriptions relating to one or more forms are presented for illustrative and explanatory purposes and are not intended to exhaustively or restrictively represent the exact forms disclosed. Modifications or alterations are possible in light of the above teachings. The one or more forms are selected and described to illustrate the principle and practical applications, thereby making various forms, along with various modifications, available to those skilled in the art for use in specific conceivable applications. The overall scope is intended to be defined by the claims presented with this application.

Claims

1. A reactor core mechanical support bracket, Housing and A spring placed inside the housing, A shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when entering and leaving the housing, the shaft further comprising an insertion portion configured to connect to a reactor core component, A shaft travel pin that restricts the movement of the shaft, A reactor core mechanical support bracket, including a flange for attaching the support bracket to the reactor canister.

2. The reactor core mechanical support bracket according to claim 1, wherein the insertion portion is configured to connect to a support beam arranged axially along the length of the reactor core.

3. The reactor core mechanical support bracket according to claim 1, wherein the insertion portion is configured to connect to a plate located at any end of the reactor core.

4. The reactor core mechanical support bracket according to claim 1, wherein the spring is a disc spring including a disc spring washer.

5. The reactor core mechanical support bracket according to claim 4, comprising a plurality of disc springs, each of which includes a plurality of stacked disc spring washers.

6. The reactor core mechanical support bracket according to claim 1, wherein the housing is made of stainless steel.

7. The reactor core mechanical support bracket according to claim 1, wherein the spring is made of alloy 718.

8. A nuclear reactor, The reactor core and A canister to contain the reactor core inside, A radial reflector placed inside the canister, A support beam positioned between the inner wall of the canister and the radial reflector, comprising a support beam positioned axially along the length of the reactor core, The core mechanical support system is configured to be attached to the canister, and the core mechanical support system is A radial core mechanical support system for supporting the core in the radial direction, comprising a radial support bracket configured to be connected to a support beam, A nuclear reactor characterized by including an axial core mechanical support system that supports the reactor core in the axial direction.

9. A reactor according to claim 8, wherein the radial support bracket is Housing and A spring placed inside the housing, A shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when entering and exiting the housing, the shaft further comprising an insertion portion configured to connect to the support beam, A shaft travel pin that restricts the movement of the shaft, A nuclear reactor characterized by including a flange for attaching the radial support bracket to the canister.

10. A nuclear reactor, The reactor core and A canister to contain the reactor core inside, Plates positioned at each end of the reactor core, The core mechanical support system is configured to be attached to the canister, and the core mechanical support system is A radial core mechanical support system that supports the core in the radial direction, A reactor characterized by comprising an axial core mechanical support system for supporting the core in the axial direction, the axial core mechanical support system including an axial support bracket configured to be connected to the plate.

11. A nuclear reactor according to claim 10, wherein the axial support bracket is Housing and A spring placed inside the housing, A shaft including a shaft slidably positioned within the housing and engaging with the spring to compress and release the spring when it moves in and out of the housing, and further configured to connect to the plate, A shaft travel pin that restricts the movement of the shaft, A nuclear reactor characterized by including a flange for attaching the axial support bracket to the canister.

12. The reactor according to claim 11, wherein the shaft comprises an insertion portion configured to engage with the plate.

13. The reactor according to claim 8 or 10, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the core in the axial direction by applying a force in advance that corresponds to an acceleration of 1 g to 10 g.

14. It is a nuclear reactor, The reactor core and A canister to contain the reactor core inside, The core mechanical support system is configured to be attached to the canister, and the core mechanical support system is A radial core mechanical support system that supports the core in the radial direction, The reactor core includes an axial core mechanical support system that supports the core in the axial direction, and the reactor core further includes A radial reflector placed inside the canister, A support beam positioned between the inner wall of the canister and the radial reflector, and axially oriented along the length of the core, wherein the radial core mechanical support system comprises a radial support bracket configured to connect to the support beam, The axial core mechanical support system includes plates positioned at each end of the core, and includes axial support brackets configured to connect to the plates. The radial support bracket and the axial support bracket are, respectively, Housing and A spring placed inside the housing, A shaft slidably disposed within the housing and engaging with the spring to compress and release the spring when entering and exiting the housing, the shaft further comprising an insertion portion configured to connect to the support beam or the plate, A shaft travel pin that restricts the movement of the shaft, A reactor characterized by including a flange for attaching the radial support bracket or the axial support bracket to the canister.

15. The reactor according to claim 14, wherein the shaft comprises an insert portion configured to engage with the support beam or the plate.

16. The reactor according to claim 14, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the core in the axial direction by applying a force in advance that corresponds to an acceleration of 1 g to 10 g.

Images