Nuclear reactor core support system providing radial and axial support

A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.

FIELD

The present disclosure is generally related to nuclear power generation and, more particularly, is directed to an improved device configured to mechanically support a core of a nuclear reactor.

SUMMARY

The following summary is provided to facilitate an understanding of some of the innovative features unique to the aspects disclosed herein, and is not intended to be a full description. A full appreciation of the various aspects of the present disclosure can be gained by taking the entire specification, claims, and abstract as a whole.

In one aspect, the present disclosure provides a nuclear reactor core mechanical support bracket. The support bracket comprises a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to a canister of a nuclear reactor. The shaft further comprises an inset configured to interface with a nuclear reactor core component.

In another aspect, the present disclosure provides a nuclear reactor. The nuclear reactor comprises a reactor core; a canister to contain and seal the reactor core within the canister; and a core mechanical support system configured to mount to the canister. The core mechanical support system comprises: a radial core mechanical support system to support the reactor core in a radial direction; and an axial core mechanical support system to support the reactor core in an axial direction.

In yet another aspect, the present disclosure provides a nuclear reactor. The nuclear reactor comprises: a reactor core; a canister to contain and seal the reactor core within the canister; and a core mechanical support system configured to mount to the canister; a radial reflector disposed within the canister; a support beam disposed between an inner wall of the canister and the radial reflector; a plate disposed on each end of the reactor core, wherein the axial core mechanical support system is configured to interface with the plate. The radial support bracket and the axial support bracket each comprises: a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, the shaft further comprising an inset configured to interface with the support beam or the plate; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to the canister. The core mechanical support system comprises: a radial core mechanical support system to support the reactor core in a radial direction; and an axial core mechanical support system to support the reactor core in an axial direction. The support beam is disposed axially along the length of the reactor core. The radial core mechanical support system comprises a radial support bracket configured to interface with the support beam.

Further, it is understood that any one or more of the following-described forms, expressions of forms, examples, can be combined with any one or more of the other following-described forms, expressions of forms, and examples.

Corresponding reference characters indicate corresponding parts throughout the several views. The examples set out herein illustrate various aspects of the claimed subject matter, in one form, and such examples are not to be construed as limiting the scope of the claimed subject matter in any manner.

DETAILED DESCRIPTION

Applicant of the present application owns the following U.S. Provisional Patent Applications, filed on the same date, the disclosure of each of which is herein incorporated by reference in its respective entirety:U.S. patent application Ser. No. 17/080,241, titled ENHANCED GRAPHITE NEUTRON REFLECTOR WITH BERYLLIUM OXIDE INCLUSIONS, filed Oct. 26, 2020;U.S. patent application Ser. No. 17/084,365, titled DEVICES, SYSTEMS, AND METHODS FOR ADJUSTING THE OUTPUT OF A REACTOR CORE, filed Oct. 29, 2020; andU.S. patent application Ser. No. 17/084,403, titled DEVICES, SYSTEMS, AND METHODS FOR CONFIGURING THE LAYOUT OF UNIT CELL OF A REACTOR CORE, filed Oct. 29, 2020.

Before explaining various aspects of a nuclear reactor comprising a core mechanical support system, it should be noted that the illustrative examples are not limited in application or use to the details of construction and arrangement of parts illustrated in the accompanying drawings and description. The illustrative examples may be implemented or incorporated in other aspects, variations, and modifications, and may be practiced or carried out in various ways. Further, unless otherwise indicated, the terms and expressions employed herein have been chosen for the purpose of describing the illustrative examples for the convenience of the reader and are not for the purpose of limitation thereof. Also, it will be appreciated that one or more of the following-described aspects, expressions of aspects, and/or examples, can be combined with any one or more of the other following-described aspects, expressions of aspects, and/or examples, without limitation.

In various aspects, the present disclosure is directed to a nuclear reactor comprising a core mechanical support system to support the reactor core and maintain the reactor core in a predetermined position. In one aspect, the nuclear reactor is a solid state micro-reactor comprising an active core, a reflector, and the core mechanical support system. The reactor core provides nuclear, thermal, and mechanical interfaces to fuel, heat removal systems, shutdown systems, reactivity control systems, and instrumentation, for example, among others. The reactor core is located inside a pressure tight canister. The core mechanical support system is configured to mechanically support and maintain the reactor core, and corresponding components, in a predetermined position and configuration during all anticipated events including shipping and handling, operation, accident, and beyond design accident conditions, without limitation. In an effort to avoid over constraint and overstress of the reactor core components, the thermo-mechanical design of the core mechanical support system may accommodate various static and dynamic loading, differential thermal expansion and changes in core component geometry during irradiation (swelling, shrinking, etc.).

Turning now to the figures,FIG.1is a perspective view of a nuclear reactor10comprising a core mechanical support system, in accordance with at least one non-limiting aspect of the present disclosure. In one aspect, the nuclear reactor10is a solid state micro-reactor. The nuclear reactor10comprises a core100(FIGS.2-4and7), a reflector106(FIGS.2-4and7), and a core mechanical support system contained within a pressurized canister120. Front and rear canister closure bulkheads122,124mechanically seal the core100, reflector106, and other components inside the canister120.

FIG.2is a longitudinal sectional view of the nuclear reactor10shown inFIG.1, in accordance with at least one non-limiting aspect of the present disclosure. With reference toFIGS.1and2, the reactor core100is contained within the canister120. The core100comprises a plurality of reactivity control cells104configured to accommodate a plurality of reactivity control rods115. Shut down rods can collectively work to control the fission occurring within the core100and therefore, prevent the core100from achieving a critical temperature in the event of a reactor10power failure and/or criticality accident. According to various non-limiting aspects, the amount of fission can be reduced or completely eliminated within the core100, the latter of which can shut down the core100. The reactivity control rods115contemplated by the present disclosure can include a neutron absorbing material and be configured to be inserted into the reactivity control cells104to slow and/or stop the nuclear reactions in the case of an emergency. The reactivity control configuration of the core100represents a feature of modern micro-reactors, which are transportable and have a broader range of commercial applications. Accordingly, the emergence of micro-reactors can increase the prevalence of nuclear technology and the risk of any significant adverse events from the increase can be minimized.

The core100comprises a graphite core block130and a radial reflector106that surrounds the graphite core block130, among other components described herein. According to the non-limiting aspect ofFIG.2, the reflector106can include stationary and movable parts. The movable parts could be a control drum including a reflector material (e.g., Beryllium Oxide [BeO]) and a sector of absorber material (e.g., Boron Carbide [B4C]). The drum acts as a reflector or as an absorber depending on its rotation relative to the graphite core block. In one aspect, the reflector106includes one or more plates composed of a thick, neutron moderating material configured to substantially surround the graphite core block130. The core100provides nuclear, thermal, and mechanical interfaces to fuel, heat removal system, shutdown and reactivity control systems, instrumentation, etc. The core100is located inside the pressure tight canister120and is surrounded by the reflector106. The core100and corresponding components are mechanically supported by the mechanical support system during all anticipated conditions including shipping and handling, operation, accident and beyond design accident conditions.

A core mechanical support system comprising a radial support system125and an axial support system127supports and maintains the core100in a predetermined position and configuration during a variety of anticipated events including shipping and handling, operation, accident, and beyond design accident conditions, without limitation. In an effort to avoid over constraint and overstress of the reactor core100and associated components, the thermo-mechanical design of the core mechanical support system may accommodate various static and dynamic loading, differential thermal expansion and changes in core component geometry during irradiation (swelling, shrinking, etc.). The core support system separates (as practically as possible) support for axial and radial direction of the cylindrical core100located horizontally. In this aspect, the dimensional changes of the core100components in the radial direction do not significantly affect the reaction forces in the axial direction and vice versa.

The radial support system125comprises a number of radial support brackets126surrounding the core100and the axial support system127comprises a number of axial support brackets128located at both ends of the core100. The radial support brackets126and the axial support brackets128support and maintain the core100in a predetermined radial and axial position during shipping and handling, operation, accident and beyond design accident conditions. The radial support brackets126interface with support beams132, which engage the radial reflector106, to uniformly distribute the load of the core100, as discussed in more detail hereinbelow. The support beams132are disposed between an inner wall of the canister120and the reflector106. The support beams132are disposed axially along the length of the core100. The axial supports brackets128interface with plates148to uniformly distribute the load of the core100, as discussed in more detail hereinbelow. With reference now also toFIGS.5and6, each radial/axial support bracket126,128comprises at least one spring134that is compressed by a shaft136that travels in and out of the radial/axial support bracket126,128housing138. The radial/axial support bracket126,128interface with the support beams132and/or plates148at the connection inset140of the radial/axial support bracket126,128. In the illustrated aspect, each radial/axial support bracket126,128comprises four springs134and each spring134comprises a number of washers146.

FIG.3is a cross sectional view of the nuclear reactor10shown inFIGS.1and2, in accordance with at least one non-limiting aspect of the present disclosure.FIG.4is a perspective longitudinal and cross sectional view of the nuclear reactor10shown inFIGS.1-3, in accordance with at least one non-limiting aspect of the present disclosure. With reference now toFIGS.1-4, according to one non-limiting aspect, the core100includes a plurality of unit cells102, which collectively form hexagonal core boundaries. Each unit cell102can be configured to accommodate a heat pipe113and an amount of fuel (e.g. in the form of a rod111and/or stack configuration), which can collectively generate nuclear power and manage thermal energy throughout the core100. According to some non-limiting aspects, one or more unit cells102can further include a moderator configuration, which can slow down neutrons emitted from the fuel. The unit cells102can be arranged such that the core100includes a hexagonal geometry. However, in other non-limiting aspects, the unit cells102can be arranged such that the core100may include any of a number of different geometrical configurations, depending on intended application and/or user preference.

With reference toFIGS.3and4, the reflector106can further include a plurality of control drums108configured to house a neutron absorptive and reflective materials. In the event of a reactor and/or power failure, the control drums108can turn inward towards the core100such that the absorptive material can shut down the reactor. According to some non-limiting aspects, the reflector106can additionally include a gamma shield configured to provide gamma and neutron shielding. The reflector can be configured to substantially surround the neutron shield, the core100, and its internal components102,104,111,113,115to further mitigate radiation. As depicted in the non-limiting aspect ofFIGS.3and4, the reflector106can be arranged in a circular configuration that surrounds the hexagonally arranged plurality of unit cells102. However, in other non-limiting aspects, the reflector106can be arranged to form any of a number of different geometrical configurations about the plurality of unit cells102, depending on intended application and/or user preference.

Still referring toFIGS.3and4, the reflector106can be sectioned to ensure that a gap exists between the unit cells102and the reflector106as a means of controlling and promoting a desired amount of heat transfer. For example, the reflector106can be formed from a plurality of modular plates integrated to create the aforementioned gap. In other non-limiting aspects, however, the reflector106can be integrally formed. Additionally, the reflector106can be further configured to extend along an axial direction, which defines a length of the core100. The plurality of unit cells102can also be configured to span the length of the core100.

Some compact reactors function as a “nuclear battery” which uses energy from the fission of nuclear materials (e.g. uranium in an oxide, metallic and/or silicide form, amongst others) to generate electricity. Since the unit cells are configured to accommodate fuel, in any form, including such radioactive isotopes, the magnitude of the length L of the core100can correspond to a desired output of the nuclear reactor and the fuel mass necessary to maintain criticality. Additionally and/or alternatively, the increased versatility of micro-reactors mean the core100must be configurable for a wide variety of applications, many of which might have size and/or weight constraints. Therefore, the design of core100allows for the length L to be specifically configurable to accommodate for the output, size, and/or weight requirements of the nuclear reactor.

Still with reference toFIGS.3and4, the plurality of unit cells102and the plurality of reactivity control cells104can be particularly arranged to establish the hexagonal configuration of the non-limiting aspect of the core100. It is also evident that each unit cell102of the plurality of unit cells102and each reactivity control cell104of the plurality of reactivity control cells104include a hexagonal configuration as well. However, it shall be appreciated that the hexagonal configuration is exclusively depicted for illustrative purposes. Accordingly, the present disclosure contemplates other non-limiting aspects in which the unit cells102and reactivity control cells104include any number of geometrical configurations (e.g. square, circular, triangular, rectangular, pentagonal, octagonal) and arranged such that the core100can include any number of geometrical configurations.

In further reference ofFIGS.3and4, the plurality of unit cells102and the plurality of reactivity control cells104can be arranged along a radial direction, thereby defining a radial dimension of the core100. Specifically, the core100shown inFIGS.3and4comprises 48 unit cells102and13reactivity control cells104. The present disclosure, however, contemplates other non-limiting aspects wherein the core100may include any number of unit cells102and reactivity control cells104. It will be appreciated that the ability to easily add or subtract the number of unit cells102or reactivity control cells104to the core100without dramatically altering its design allows the core100to be easily scaled depending on the intended application and/or user preference. As such, the output of the core100design can also be easily adjusted for a multitude of applications and requirements. For example, a user can change the radial and/or axial dimension of the core100by adding or subtracting unit cells102or reactivity control cells104to the core100. Since the unit cells are configured to accommodate fuel including radioactive isotopes, increasing or decreasing the magnitude of the radial dimension can alter the output of the core100. Accordingly, the radial dimension of the core100can correspond to a desired output of the nuclear reactor depending on the intended application and/or user preference. Additionally and/or alternatively, the radial dimension of the core100can be specifically configured to comply with a multitude of size and/or weight requirements, which can vary by application. Accordingly, the core mechanical support system can be modified by adding or removing radial/axial support brackets126,128of the radial support system125and the axial support system127to accommodate changes in the radial and/or axial dimensions of the core100.

It shall be appreciated that the term “radial”, as used in the present disclosure, describes any direction extending from the center of the core100when viewed from the top. Accordingly, the use of the term “radial” shall not be limited to circular or circular-like configurations and shall not be construed to imply that the core100ofFIGS.1-4is limited to circular, or circular-like, configurations. For example, the present disclosure contemplates non-limiting aspects in which the core100includes a rectangular cross-section configuration. According to such aspects, the core100can include one or more radial dimensions of varying lengths. With reference toFIGS.2and4, the plurality of unit cells102and the plurality of reactivity control cells104can be integrally formed from a solid block130of material (e.g. graphite). Thus, the internal features of each of the unit cells102, such as heat pipe channels, fuel channels, moderator channels, and/or the like, can be bored out of—and integrally formed from—the solid block of material. However, according to other non-limiting aspects, each unit cell102of the plurality of unit cells102and each reactivity control cell104can be modularly formed and integrated into the core block130to promote the adjustability of the core100design.

Regardless, the core100can be easily manufactured to include any number of unit cells102and/or reactivity control cells104. This can allow the core100design to be easily scalable, an obvious improvement over known reactors. For example, altering the number of unit cells102and reactivity control cells104allows the user to alter the radial dimension R and axial length L (FIG.1) of the core100, thereby altering its output and flexibility for applications with unique output and/or space constraints. The core100design, however, essentially remains the same, which allows for predictability in production and performance regardless of the difference in output and size. These features also reduce the amount of non-recurring engineering required to design for a new application and facilitates manufacturing consistency and the standardization of parts. Although the core100can be scaled as a means of adjusting its output, the scaling should further consider the power rating of the implemented heat pipes, the appropriate number of reactivity control rods required for the adjusted output, and the effectiveness of the control drums.

According to other non-limiting aspects, the unit cell102can further include a moderator channel configured to accommodate a moderator (e.g. a hydride-based moderator, BeO, etc.) of the core100, wherein the moderator can be configured to retard and the propagation of neutrons emitted by fuel inserted in the plurality of fuel channels110. Alternatively and/or additionally, the unit cell102can include additional features, configured to accommodate other instrumentation of the core100.

Still referring toFIGS.3and4, the unit cell102also can include features configured to accommodate a neutron absorbing materials that can slow the nuclear reactions occurring in the fuel channels110of the unit cells102. Accordingly, the power distribution and radial power peaking of the unit cells102—and consequentially, the core100itself—can be further adjusted via the influence of neutron absorbers. According to some non-limiting aspects, the core100can be designed for an application that does not impose a strict transportation requirement on the core100. Alternatively and/or additionally, the core100can use a high-density fuel. According to such aspects, the axial power peaking factor and axial power distribution of the unit cells102and core100can be otherwise managed by varying the fuel enrichment level within the fuel channels110of the unit cells102or by adding burnable absorbers.

Similarly, the reflector106configuration may include a plurality of reflectors106including control drums108, wherein the reflectors106are configured to extend along at least a portion of the length L of the core100. Of course, according to some non-limiting aspects, the reflectors too can be integrally formed. Again, the reflectors can be specifically configured to create advantageous gaps to promote and enhance heat transfer throughout the core100.

According to non-limiting aspects ofFIGS.1-4, the core100can be assembled to include a fuel111(e.g. rods and/or stacks), heat pipes113, and reactivity control rods115dispositioned throughout the plurality of unit cells102and reactivity control cells104. Specifically, the fuel111can be dispositioned throughout the fuel channels110of one or more unit cells102, the heat pipes113can be dispositioned throughout the heat pipe channels112(FIG.3) of one or more unit cells102, and the reactivity control rods115can be dispositioned through a reactivity control channel (not shown) of one or more reactivity control cells104. According to some non-limiting aspects, the fuel111and heat pipes113are configured to extend the predetermined length L of the core100. In other non-limiting aspects, the fuel111and heat pipes113are configured to extend an additional length beyond the predetermined length L of the core, to facilitate downstream ex-core connections and/or equipment (e.g. power systems, condensers, structural supports). This design allows the core100to be customized for any intended application and/or user preference, which enables it to be versatile in response to customer needs. These alterations, however, can be evaluated using the underlying nuclear physics and/or manufacturability of the core100design, which preserves reliability and predictability in core100production and operation. In other words, the assembled core100allows the fuel111and heat pipes113to be specifically configured to accommodate for any specific power requirement and/or structural configuration without having to reinvent the basic core100design and assume the inherent development risks.

Still referring toFIGS.1-4, the core100can further include a plurality of reactivity control rods115configured to be dispositioned through one or more reactivity control cell104of the plurality of reactivity control cells104. For example, the reactivity control cells104can include a reactivity control rod or reactivity control channel similar to the fuel channels110and/or heat pipe channels112, but specifically configured to accommodate a reactivity control rod115. As previously discussed, each reactivity control rod115can include a neutron absorbing material configured to slow and/or stop the nuclear reactions within the core100in the case of an emergency. The reactivity control rods115can collectively work to prevent the core100from achieving a critical temperature or prompt criticality in the event of a reactor and/or power failure. Accordingly, the emergence of micro-reactor can increase the prevalence of nuclear technology, making safety a higher priority.

FIG.5is a perspective view of a radial and axial support bracket126,128, in accordance with at least one non-limiting aspect of the present disclosure. The main component of the core support system is a radial/axial support bracket126,128comprising a preloaded spring block. Each spring block of the radial/axial support bracket126,128comprises various number of springs134as shown in more detail inFIG.6. Each radial/axial support bracket126,128comprises a number of springs134located internal to the bracket housing138. Each spring134is preloaded or compressed by a shaft136that is slidingly disposed within the bracket housing138and interfaces with a support beam132(FIGS.2-4) at the connection inset140. The shaft136is configured to engage the spring134to compress and decompress the spring134as the shaft136travels in and out of the bracket housing138. The travel of each bracket shaft136is controlled by a shaft travel pin142, which also prevents rotation of the bracket shaft136. The radial/axial support bracket126,128can be mounted to the external canister120(FIGS.1,2,4) by the support bracket flange144. A number of radial support brackets126are located around the core100(FIGS.1-4) and a number of axial support brackets128are located at either end of the core100to create a desirable support for the core100in a radial and axial direction. The reaction forces corresponding to the preloaded spring block radial/axial support bracket126,128act against internal walls of the pressure tight canister120. In one aspect, the and the bracket body comprising the housing138, bracket flange144, shaft136, and shaft travel pin142may be made of 304 stainless steel. The materials of construction can also be modified depending on environmental conditions.

FIG.6is a perspective view of Belleville washer springs134, in accordance with at least one non-limiting aspect of the present disclosure. In one aspect, the spring in the preloaded spring block radial/axial support bracket126,128may be a disc spring such as a Belleville washer spring134, for example. The Belleville washer spring134may be made of high-strength, corrosion-resistant age-hardenable alloy such as nickel chromium material that can be readily fabricated into complex parts. In one aspect, the Belleville washer spring134is made of Alloy 718 material. With reference toFIGS.5and6, the radial/axial support bracket126,128should not be limited in the disclosed context as a variety of other configurations may be employed. Other aspects of the bracket housing138or body is configured to house the Belleville washer springs134in a compressed state via the shaft136with the shaft travel pin142. The number of Belleville washer springs134and the number of Belleville washers146in the spring can vary. The Belleville washer146has frusto-conical shape that gives the washer146its characteristic spring. The dimensions of any individual component also can be varied. The materials of construction can also be modified depending on environmental conditions. In various aspects, The Belleville washer146is a type of spring shaped like a washer. The Belleville washer spring134may be referred to as a coned-disc spring, conical spring washer, disc spring, Belleville spring, or cupped spring washer, comprise a conical shell which can be loaded along its axis either statically or dynamically.

It will be appreciated that the number of radial/axial support brackets126,128and preloaded spring134characteristics may be selected to ensure that the “as-built” preload force is in a range of forces corresponding from 1 g to 10 g acceleration. In one aspect, the deflection of the spring134pack is sufficient to compensate for a differential expansion between components of the core100, canister120, and the radial/axial core the support systems125,127taking into account thermal expansion and irradiation induced geometry and dimensional changes.

FIG.7is a perspective longitudinal sectional view of the nuclear reactor core100shown inFIGS.1-4, in accordance with at least one non-limiting aspect of the present disclosure. The reactor core100comprises a core mechanical support system comprising radial/axial core the support systems125,127comprising radial/axial support brackets126,128acting in axial (L) and radial (R) directions as described herein. In this configuration, the core100is assembled with graphite core blocks130, fuel rods (not shown), heat pipes (not shown) and a stationary radial reflector106located inside the pressurized canister120. The radial core support system125comprising a series of preloaded spring radial support brackets126interface with the core components using beams132to uniformly distribute the load radially. The axial core support system127comprising a series of preloaded spring axial support brackets128interface with plates148to uniformly distribute the load axially. The axial support brackets128can engage with the plates148via the shaft136and/or the inset140.

With reference now toFIGS.5-7, the radial core support system125comprises a series of the preloaded spring radial support brackets126which interface with the core100component using beams132to uniformly distribute the load. The radial support brackets126are located along the core100and uniformly distributed over the canister120wall in the axial and hoop direction. The radial support brackets126are attached to the canister120wall at one side by the flange144. The other side of the radial support bracket126interfaces with the beam132located along the axial (L) length of the core100inside the canister120. The beam132slidingly interfaces to the core100to allow a differential expansion between the graphite core block130components, the canister120, and the radial support bracket126and spring134pack. The number and characteristic of the spring134pack located in the housing138of the radial bracket126is selected based on required preload, anticipated external load, and combined dimensional changes due to differential thermal expansion and irradiation induced effects in the radial direction.

Still with reference toFIGS.5-7, the axial support brackets128are attached to the canister bulkhead122,124and provides force to the core graphite block130over the plates148. A sliding interface between the axial support bracket128and the plates148allow for a differential expansion between the core graphite block130and the canister120. The number and characteristic of the spring134pack located in the housing138of the axial support bracket128is selected based on the required preload, anticipated external load and combined dimensional changes due to differential thermal expansion and irradiation induce effects in the axial direction.

Various aspects of the subject matter described herein are set out in the following numbered examples:

Example 1: A nuclear reactor core mechanical support bracket, comprising: a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, the shaft further comprising an inset configured to interface with a nuclear reactor core component; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to a canister of a nuclear reactor.

Example 2: The nuclear reactor core mechanical support bracket of Example 1, wherein the inset is configured to connect to a support beam axially disposed along the length a nuclear reactor core.

Example 3. The nuclear reactor core mechanical support bracket of any one or more of Examples 1-2, wherein the inset is configured to connect to a plate disposed at either end of a nuclear reactor core.

Example 4. The nuclear reactor core mechanical support bracket of any one or more of Examples 1-3, wherein the spring is a disc spring comprising a disc washer spring.

Example 5. The nuclear reactor core mechanical support bracket of Example 4, comprising a plurality of disc springs, wherein each one of the plurality of disc springs comprises a plurality of stacked disc washer springs.

Example 6. The nuclear reactor core mechanical support bracket of any one of Examples 1-5, wherein the housing is made of stainless steel.

Example 7. The nuclear reactor core mechanical support bracket of any one or more of Examples 1-6, wherein the spring is made of Alloy 718.

Example 8. A nuclear reactor, comprising: a reactor core; a canister to contain and seal the reactor core within the canister; and a core mechanical support system configured to mount to the canister, wherein the core mechanical support system comprises: a radial core mechanical support system to support the reactor core in a radial direction; and an axial core mechanical support system to support the reactor core in an axial direction.

Example 9. The nuclear reactor of Example 8, further comprising: a radial reflector disposed within the canister; and a support beam disposed between an inner wall of the canister and the radial reflector, wherein the support beam is disposed axially along the length of the reactor core; wherein the radial core mechanical support system comprises a radial support bracket configured to interface with the support beam.

Example 10. The nuclear reactor of Example 9, wherein the radial support bracket comprises: a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, the shaft further comprising an inset configured to interface with the support beam; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to the canister.

Example 11. The nuclear reactor of any one or more of Examples 8-10, further comprising a plate disposed on each end of the reactor core, wherein the axial core mechanical support system is configured to interface with the plate.

Example 12. The nuclear reactor of Example 11, wherein the axial core mechanical support system comprises: a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, the shaft further comprising a shaft configured to interface with the plate; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to the canister.

Example 13. The nuclear reactor of Example 12, wherein the shaft comprises an inset configured to engages the plate.

Example 14. The nuclear reactor of any one or more of Examples 8-13, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the reactor core in an axial direction provide a preload force in a range of forces corresponding from 1 g to 10 g acceleration.

Example 15. A nuclear reactor, comprising: a reactor core; a canister to contain and seal the reactor core within the canister; and a core mechanical support system configured to mount to the canister, wherein the core mechanical support system comprises: a radial core mechanical support system to support the reactor core in a radial direction; and an axial core mechanical support system to support the reactor core in an axial direction; a radial reflector disposed within the canister; a support beam disposed between an inner wall of the canister and the radial reflector, wherein the support beam is disposed axially along the length of the reactor core, wherein the radial core mechanical support system comprises a radial support bracket configured to interface with the support beam; a plate disposed on each end of the reactor core, wherein the axial core mechanical support system is configured to interface with the plate; wherein the radial support bracket and the axial support bracket each comprises: a housing; a spring disposed internally within the housing; a shaft slidingly disposed within the housing and to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing, the shaft further comprising an inset configured to interface with the support beam or the plate; a shaft travel pin to control the travel of the shaft; and a flange to mount the support bracket to the canister.

Example 16. The nuclear reactor of Example 15, wherein the shaft comprises an inset configured to engages the support beam or the plate.

Example 17. The nuclear reactor of any one or more of Examples 15-16, wherein the radial core mechanical support system and the axial core mechanical support system are configured to support the reactor core in an axial direction provide a preload force in a range of forces corresponding from 1 g to 10 g acceleration.

Numerous specific details are set forth to provide a thorough understanding of the overall structure, function, manufacture, and use of the aspects as described in the present disclosure and illustrated in the accompanying drawings. Well-known operations, components, and elements have not been described in detail so as not to obscure the aspects described in the present disclosure. The reader will understand that the aspects described and illustrated herein are non-limiting examples, and thus it can be appreciated that the specific structural and functional details disclosed herein may be representative and illustrative. Variations and changes thereto may be made without departing from the scope of the claims. Furthermore, it is to be understood that such terms as “forward”, “rearward”, “left”, “right”, “upwardly”, “downwardly”, and the like are words of convenience and are not to be construed as limiting terms.

In the present disclosure, like reference characters designate like or corresponding parts throughout the several views of the drawings.

All patents, patent applications, publications, or other disclosure material mentioned herein, are hereby incorporated by reference in their entirety as if each individual reference was expressly incorporated by reference respectively. All references, and any material, or portion thereof, that are said to be incorporated by reference herein are incorporated herein only to the extent that the incorporated material does not conflict with existing definitions, statements, or other disclosure material set forth in this disclosure. As such, and to the extent necessary, the disclosure as set forth herein supersedes any conflicting material incorporated herein by reference and the disclosure expressly set forth in the present application controls.

The present disclosure has been described with reference to various examples and illustrative aspects. The aspects described herein are understood as providing illustrative features of varying detail of various aspects of the disclosed invention; and therefore, unless otherwise specified, it is to be understood that, to the extent possible, one or more features, elements, components, constituents, ingredients, structures, modules, and/or aspects of the disclosed aspects may be combined, separated, interchanged, and/or rearranged with or relative to one or more other features, elements, components, constituents, ingredients, structures, modules, and/or aspects of the disclosed aspects without departing from the scope of the disclosed invention. Accordingly, it will be recognized by persons having ordinary skill in the art that various substitutions, modifications or combinations of any of the example aspects may be made without departing from the scope of the invention. In addition, persons skilled in the art will recognize, or be able to ascertain using no more than routine experimentation, many equivalents to the various aspects of the invention described herein upon review of the present disclosure. Thus, the present disclosure is not limited by the description of the various aspects, but rather by the claims.

As used herein, the singular form of “a”, “an”, and “the” include the plural references unless the context clearly dictates otherwise.

Directional phrases used herein, such as, for example and without limitation, top, bottom, left, right, lower, upper, front, back, and variations thereof, shall relate to the orientation of the elements shown in the accompanying drawing and are not limiting upon the claims unless otherwise expressly stated.

The terms “about” or “approximately” as used in the present disclosure, unless otherwise specified, means an acceptable error for a particular value as determined by one of ordinary skill in the art, which depends in part on how the value is measured or determined. In certain aspects, the term “about” or “approximately” means within 1, 2, 3, or 4 standard deviations. In certain aspects, the term “about” or “approximately” means within 50%, 200%, 105%, 100%, 9%, 8%, 7%, 6%, 5%, 4%, 3%, 2%, 1%, 0.5%, or 0.05% of a given value or range.

Any numerical range recited herein includes all sub-ranges subsumed within the recited range. For example, a range of “1 to 100” includes all sub-ranges between (and including) the recited minimum value of 1 and the recited maximum value of 100, that is, having a minimum value equal to or greater than 1 and a maximum value equal to or less than 100. Also, all ranges recited herein are inclusive of the end points of the recited ranges. For example, a range of “1 to 100” includes the end points 1 and 100. Any maximum numerical limitation recited in the present disclosure is intended to include all lower numerical limitations subsumed therein, and any minimum numerical limitation recited in the present disclosure is intended to include all higher numerical limitations subsumed therein. Accordingly, Applicant reserves the right to amend the present disclosure, including the claims, to expressly recite any sub-range subsumed within the ranges expressly recited. All such ranges are inherently described in the present disclosure.