Support with integrated sensor for nuclear reactor steam generator and related system and method - Patents.com

Abstract

A support with integrated sensor for a nuclear reactor steam generator and associated systems and methods are disclosed. An exemplary method of forming a nuclear power steam generator includes forming an instrumentation support, the instrumentation support including a carrier portion and a retainer portion, at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process. The method may further include coupling the sensor to a communication link, supporting a helical steam conduit on the instrumentation support, and installing the helical steam conduit and the instrumentation support in the nuclear reactor. The helical steam conduit is positioned along a primary flowpath. The primary flowpath is positioned to circulate a heated primary flow in thermal communication with the helical steam conduit.

Description

[Technical field]

[0001] CROSS-REFERENCE TO RELATED APPLICATIONS This application is a continuation of U.S. Patent Application No. 17 / 168,118, filed February 4, 2021, and incorporated herein by reference in its entirety.

[0002] STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH This invention was made with Government support under Contract No. DE-NE0008928 awarded by the Department of Energy. The Government has certain rights in this invention.

[0003] TECHNICAL FIELD The present technology relates generally to supports with integrated sensors for nuclear reactor steam generators and associated systems and methods. [Background technology]

[0004] Nuclear power plants have been used for many years to generate steam, which is then converted into electricity via steam turbines. Large power plants may be used to provide electricity to correspondingly large geographic areas, while relatively small power plants may be used to provide power to smaller geographic areas, submarines, spacecraft, and / or other systems and subsystems requiring power. In addition to providing electricity, nuclear reactors may be used for one or more other purposes, including, but not limited to, desalinizing seawater and producing nuclear isotopes for medical purposes.

[0005] Nuclear reactors typically include a significant amount of instrumentation for monitoring the state of the system and responding, if necessary, by altering the parameters under which the reactor operates. While existing sensor systems have been adequate, there remains a need to improve the accuracy and manufacturability of such sensors in a manner that does not significantly increase the complexity and / or cost of the overall system. [Brief description of the drawings]

[0006] Many aspects of the present technology can be better understood with reference to the following drawings, in which the components are not necessarily to scale, emphasis instead being placed upon clearly illustrating the principles of the present technology.

[0007] [Figure 1] FIG. 1 is a partially schematic cross-sectional view of an exemplary system constructed in accordance with embodiments of the present technology. [Figure 2A] FIG. 2A is a partially schematic diagram of a portion of a steam generator including a conduit support constructed in accordance with embodiments of the present technique. [Figure 2B] FIG. 2B is a close-up view of a conduit support and associated conduits arranged in accordance with embodiments of the present technology. [Figure 2C] FIG. 2C is a partially schematic diagram of an array of rails aligning and supporting multiple conduit supports in accordance with embodiments of the present technology. [Diagram 3] FIG. 3 is a partially schematic isometric view of a conduit support having one or more sensors integrally fabricated via additive manufacturing techniques, in accordance with embodiments of the present technology. [Figure 4] FIG. 4 is a partially schematic diagram of an exemplary sensor suitable for being integrally formed with a conduit support according to embodiments of the present technology. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS

[0008] Aspects of the present disclosure generally relate to a support having integrated sensors for operation in a nuclear reactor steam generator. In certain embodiments, the support carries a helical array of steam generator conduits that receive heat from a nuclear reactor core to generate steam. The steam is then used to generate electrical power. The support may include integrally formed sensors that can accurately identify parameters associated with the operation of the steam generator in a manner that increases robustness and / or reliability. For example, the sensors may include additively manufactured optical strain gauges that are formed directly into the support that maintains the conduits in place within the reactor. By integrally forming the sensors with the support, the sensors can more accurately identify changes in properties of the support (and associated conduits), such as vibration or rocking, and may be protected by being embedded within the support.

[0009] Certain illustrative details are set forth in the following description and in Figures 1-4 to provide a thorough understanding of various embodiments of the present technology. In other instances, well-known structures, materials, operations, and / or systems often associated with nuclear reactors, steam generators, and / or sensors are not shown or described in detail in the following disclosure to avoid unnecessarily obscuring the description of various embodiments of the present technology. However, one skilled in the art will recognize that the present technology may be practiced without one or more of the illustrative details set forth herein and / or with other structures, methods, components, etc.

[0010] The terms used below should be interpreted in the broadest reasonable manner, even when used in conjunction with the detailed description of certain examples of embodiments of the present technology. Indeed, even if certain terms are emphasized below, any terms that are intended to be interpreted in any limited manner are expressly and specifically defined as such in this detailed description section.

[0011] The accompanying drawings depict several embodiments of the present technology and are not intended to limit its scope unless expressly indicated. The sizes of the various depicted elements are not necessarily drawn to scale, and these various elements may be enlarged to improve legibility. Details of components may be abstracted in the drawings to exclude details such as the location of components and / or the predetermined precise connections between the components, if such details are not necessary for a complete understanding of how to make and use the present technology. Many of the details, dimensions, angles, and other features shown in the drawings are merely illustrative of certain embodiments of the present disclosure. Thus, other embodiments may have other details, dimensions, angles, and features without departing from the present technology. In addition, those skilled in the art will appreciate that further embodiments of the present technology may be practiced without some of the details described below.

[0012] The general arrangement of a representative system is detailed below with reference to FIG. 1. Thereafter, the specific elements of the steam generator and associated sensors are further detailed below with reference to FIGS. 2A-4.

[0013] 1 is a partially schematic, partial cross-sectional view of a nuclear reactor system 100. The system 100 includes a power module 115 having a core 101 in which a controlled nuclear reaction occurs. The core 101 may therefore include one or more fuel assemblies 116. The fuel assemblies 116 may include fissile and / or other suitable materials. Heat from the reaction generates steam in a steam generator 120, which directs the steam to a power conversion system 170. The power conversion system 170 generates electrical power and / or provides other useful output. A sensor system 150 is used to monitor the operation of the power module 115 and / or other system components. Data obtained from the sensor system 150 may be used in real time to control the power module 115 and / or may also be used to update the design of the power module 115 and / or other system components.

[0014] The power modules 115 include a containment vessel 102, which houses / encloses a reactor pressure vessel 106. The reactor pressure vessel 106 houses the reactor core 101. The containment vessel 102 may be housed in a power module bay 103. The power module bay 103 houses a cooling pool 104 filled with water and / or other suitable cooling fluid. A majority of the power modules 115 are disposed below a surface 105 of the cooling pool 104. Thus, the cooling pool 104 may act as a thermal sink, for example, in the event of a system malfunction.

[0015] The volume between the reactor pressure vessel 106 and the containment vessel 102 may be partially or completely evacuated to reduce heat transfer from the reactor pressure vessel 106 to the surrounding environment (e.g., to the cooling pool 104). However, in other embodiments, the volume between the reactor pressure vessel 106 and the containment vessel 102 may be at least partially filled with gas and / or liquid to increase heat transfer between the reactor pressure vessel 106 and the containment vessel 102.

[0016] Within the reactor pressure vessel 106, a primary coolant 109 transfers heat from the core 101 to a steam generator 120. The primary coolant 109 is heated in the core 101 and directed toward the bottom of the reactor pressure vessel 106, for example, as indicated by arrows disposed within the pressure vessel 106. The heated primary coolant (e.g., water, with or without additives) rises from the core 101 through the core shroud 107 and into the riser pipe 108. The hot, buoyant primary coolant 109 continues to rise through the riser pipe 108 before exiting the riser pipe 108 and descending through the steam generator 120. The steam generator 120 includes multiple conduits 122 arranged circumferentially around the riser pipe 108, for example, in a helical pattern, as shown diagrammatically in FIG. 1. The descending primary coolant 109 transfers heat to the secondary coolant (e.g., water) in conduit 122 and descends to the bottom of the reactor pressure vessel 106 where the cycle begins again. The cycle can be driven by changes in buoyancy of the primary coolant 109, thereby reducing or eliminating the need for pumps to move the primary coolant 109.

[0017] Steam generator 120 includes a feedwater header 121. Incoming secondary coolant enters steam generator conduit 122 via feedwater header 121. The secondary coolant rises through conduit 122, is converted to steam (e.g., water vapor), and is collected in steam header 123. The water vapor exits steam header 123 and is directed to power conversion system 170.

[0018] Power conversion system 170 may include one or more steam valves 172 that regulate the passage of high pressure, high temperature steam from steam generator 120 to steam turbine 173. Steam turbine 173 converts the thermal energy of the steam into electricity via generator 174. The low pressure steam exiting turbine 173 is condensed in condenser 175 and then directed (e.g., via pump 176) to one or more feedwater valves 171. Feedwater valve 171 controls the rate at which feedwater re-enters steam generator 120 via feedwater header 121.

[0019] The power module 115 includes a number of control systems and associated sensors. For example, the power module 115 may include a hollow cylindrical reflector 110 that reflects neutrons back into the reactor core 101 to drive the nuclear reaction therein. Control rods 111 are used to regulate the nuclear reaction and are driven via fuel rod drivers 112. The pressure within the reactor pressure vessel 106 may be controlled by controlling the pressure in a pressurized volume 114 positioned above the pressurizer plate 113 (which may also serve to direct the primary coolant 109 downward through the steam generators 120) via a pressurizer plate 113.

[0020] Sensor system 150 may include one or more sensors 151 positioned at various locations within power module 115 and / or elsewhere to identify, for example, operational parameter values ​​and / or changes in parameter values. Data collected by sensor system 150 may then be used to control operation of system 100 and / or effect design changes for system 100. For sensors positioned within containment vessel 102, sensor links 152 route data from the sensors to flange 153 (where sensor link 152 exits containment vessel 102) and route the data to sensor junction box 154. From there, the sensor data is routed via data bus 155 to one or more controllers and / or other data systems.

[0021] One challenge associated with nuclear reactors, and particularly steam generators therein, is that the process of converting water to steam may not occur uniformly or smoothly within the steam generator. In particular, density waves may form within the steam generator conduits, resulting in density wave vibrations that cause vibrations and stresses in the steam generator conduits and / or other components. As described in more detail below with reference to Figures 2A-4, aspects of the present technology relate to improved sensors and related technology for detecting properties of a steam generator, including strains caused by density wave vibrations.

[0022] FIG. 2A is a partially schematic isometric view of an exemplary steam generator 120 having multiple conduits 122 arranged around a central opening 125. The central opening 125 houses the riser pipe 108 described above with reference to FIG. 1. The conduits 122 may be arranged in one or more conduit bundles 124 that orbit the central opening 125 in a helical manner to provide extensive thermal and fluid contact between the outer walls of the conduits 122 and the surrounding primary coolant. Water enters the conduits 122 from a feedwater header 121 and exits through a steam header 123. The conduits 122 may be supported by multiple conduit supports 130. The individual conduit supports 130 may be arranged into a conduit support stack 131 that extends radially outward from the central opening 125. Each conduit support 130 may include an upper support rail aperture 132 and a lower support rail aperture 133 that are aligned with corresponding rails, described below with reference to FIG. 2C. In the illustrated embodiment, four conduits 122 are shown, however, it will be understood that the above is merely an example, without limitation to the disclosed subject matter.

[0023] FIG. 2B is an enlarged view of a portion of an exemplary conduit support stack 131. A number of conduit supports 130 and corresponding conduits 122 are shown. Each conduit support 130 may include a carrier portion 134 and one or more retainer portions 135. For example, as shown in FIG. 2B, the retainer portions 135 may include protrusions extending below and / or above each conduit 122 to support the conduits 122 in place. Generally, the conduits 122 are not rigidly attached to the retainer portions 135 to accommodate dimensional changes due to, for example, thermal expansion. As shown in FIG. 2B, the conduit support stack 131 includes a number of spaced apart conduit supports 130. A "layer" of conduits 122 is supported between adjacent pairs of conduit supports 130.

[0024] Figure 2C shows upper support rails 136 and lower support rails 137 positioned to align corresponding conduit supports 130. For purposes of illustration, two pairs of conduit supports 130 are shown aligned with corresponding pairs of upper support rails 136 and lower support rails 137. A number of additional conduit supports 130 are then aligned in the radial direction R along the rails 136, 137. This is shown in Figures 2A and 2B.

[0025] FIG. 3 is a partially schematic cross-sectional view of an exemplary conduit support 130 configured in accordance with embodiments of the present technology. The conduit support 130 may include a carrier portion 134, multiple retainer portions 135, and one or more sensors 151, all integrally formed as a unit. Thus, the conduit support 130 may be referred to herein as an instrumentation support or an instrumentation conduit support. For example, the sensors 151, the retainer portions 135, and the carrier portion 134 may be integrally formed via additive manufacturing techniques. Suitable techniques include the use of laser powder bed or direct energy application 3D printers. However, such techniques may be limited to applications where the embedded sensors 151 can withstand the high temperatures typically associated with such 3D printing techniques. For sensors that cannot withstand such temperatures, ultrasonic additive manufacturing (UAM) techniques may be used instead. For example, UAM techniques can be used to additively manufacture structures that include both metallic and non-metallic components without melting either. This allows for the bonding of dissimilar metals and facilitates the stacking of clad materials, metal matrix composites, and / or "smart" or reactive structures. As a result, the sensor electronics can be embedded (under the exterior surface of the support structure) in a tamper-proof and / or tamper-resistant protective structure (e.g., that of the conduit support 130). In other words, the sensor is protected from the harsh environment in the steam generator by being fully or at least partially encapsulated / enclosed in a non-destructive manner within the structure with which it is built. In addition, the structure can include complex internal geometries that can be easily built via additive manufacturing techniques but that may be difficult and impractical to build using traditional subtractive techniques. For example, the conduit support 130 can include openings 138. The openings 138 reduce the amount of used material used to form the support and reduce heat transfer away from the water vapor in the conduit. Furthermore, the fidelity of the additive manufacturing process can reduce or eliminate the need for post-manufacturing processing (e.g., machining).

[0026] In the exemplary embodiment shown in FIG. 3, the sensor 151 includes a fiber optic strain gauge 156 and an associated communication link 152. The communication link 152 may also include a fiber optic element. In one such embodiment, the strain gauge 156 is integrally formed with the retainer portion 135, and the conduit carried by the retainer portion 135 allows the strain gauge 156 to accurately record changes in strain on the retainer portion 135. The conduits (shown in FIGS. 2A-2C) extend from one conduit support 130 to the next along corresponding conduit axes 126. In various embodiments, because the strain gauge 156 is integrally formed with the retainer portion 135, the material of the retainer portion 135 may help shield the strain gauge from, for example, gamma radiation emanating from the reactor core. Such radiation may discolor the optics of the strain gauge 156 and / or the communication link 152, thereby reducing or eliminating operability of the sensor. By embedding the optical strain gauges 156, for example in a metallic material, the possibility of such degradation can be reduced, delayed, and / or eliminated, thereby enabling the ability to measure strain characteristics in the steam generator. For example, as shown in FIGURE 3, the strain gauges 156 are integrated with the retainer portion 135 and the communication link 152 is integrated with the carrier portion 134 as well as the retainer portion 135. The material forming the conduit support (e.g., the carrier portion 134 and / or the retainer portion 135) may include stainless steel in some embodiments and other suitable materials in other embodiments.

[0027] FIG. 4 shows a representative fiber optic strain gauge 156, which has a typical conventional structure, but is integrally formed with a corresponding support using UAM techniques. One possible representative device for such pseudo-scanning includes the SonicLayer® 7200 automated system available from Aniwaa (www.aniwaa.com). It will be understood that this is merely an example to which the disclosed subject matter is not limited. The UAM system may form a silica core 157 through which a light beam 158 is transmitted. The silica core 157 is surrounded by a cladding 159 for protection and to prevent light from escaping the core 157. The core 157 may include a number of Bragg grating elements 160. The Bragg grating elements 160 refract and / or reflect light differently depending on whether the strain gauge 156 is under strain and, if so, the value of the strain. The UAM process may also include forming communication links 152 (FIG. 3) simultaneously with the strain gauges 156 and surrounding conduit support 130. Multiple communication links 152 may be routed through corresponding conduit supports to appropriate junction boxes or other connection structures. Data collected by the sensors is then routed out of the reactor via flanges 153, described above with reference to FIG. 1. Notably, because at least one material forming the strain gauges 156 and / or other types of sensors is different from at least one material forming the conduit support 130, the additive manufacturing process is selected to operate successfully despite such differences.

[0028] The data obtained from the sensors can be used for one or more purposes related to increasing reactor efficiency and / or providing other benefits to the corresponding reactor. For example, during operation, the sensors can accurately detect distortions that may correspond to density wave oscillations and / or other flow phenomena so that operators can adjust system operating parameters to prevent such phenomena from occurring. In other applications, the data can be used to design or redesign reactor components to reduce the likelihood of density wave oscillations and / or other flow phenomena occurring. Or, in other exemplary embodiments, components may be designed or redesigned to provide target vibration frequency and / or amplitude values, e.g., target values ​​acceptable for reactor operation.

[0029] For purposes of illustration, the representative sensors shown in Figures 3 and 4 are optical strain sensors. In other embodiments, the sensors may have other configurations and / or may be used to measure other parameter values. For example, the sensors may include thermal sensors (e.g., thermocouples) configured to measure local temperatures within the steam generator or other system component in which the sensor is positioned. Data obtained from the thermal sensors, along with data obtained from the strain sensors, may be used to further quantify and / or understand characteristics of density wave oscillations and / or other flow phenomena. In other embodiments, the thermal sensors (and / or other sensors) may also be used independently to assess any of a variety of suitable flow, thermal and / or structural parameters.

[0030] In any of the above described embodiments, the ability to additively manufacture sensors simultaneously with the structure on which they are located can be used to efficiently produce arrays of sensors (e.g., three-dimensional arrays) that can capture phenomena in a multi-dimensional environment more accurately than a small, scattered set of sensors. This ability can further improve the accuracy of the data and the effectiveness of steps taken based on that data. Data collected by the above-described sensors can generally be static and / or dynamic depending on the application. For example, density wave vibrations generally have a frequency of about 0.1 Hz to 0.3 Hz in the boiling region within the steam generator conduit 122. Thus, the strain sensor can be configured to measure strain changes at a frequency high enough to capture the periodicity described above.

[0031] In addition to the applications mentioned above (e.g., improving steam generator reliability for future designs and / or providing early indication or prediction of steam generator conduit fatigue), the data may also be used for other purposes, such as to narrow or focus inspections of steam generators and / or other components of a reactor to areas most likely to require such inspections, thereby reducing the need for and associated costs of structural inspections that may not be required. In other applications, thermal data obtained from an array or network of thermal sensors may be used to accurately predict heat transfer characteristics within a steam generator, which may impact the design of the steam generator, resulting in more efficient, robust and / or less expensive steam generators.

[0032] From the above, it can be seen that although specific embodiments of the disclosed technology have been described herein for purposes of illustration, various modifications may be made without departing from the technology. For example, the sensors may detect parameters other than strain and / or temperature. The sensors may be non-optical and / or communicate data via non-optical communication links. Although the exemplary embodiment shows sensors positioned on the steam generator conduit support, sensors according to other embodiments may be positioned on other system elements. The sensors positioned on the steam generator may be incorporated into the retainer portion of the conduit support and / or may be incorporated into other portions of the conduit support, such as the carrier portion.

[0033] Certain aspects of the technology described in the context of particular embodiments may be combined or eliminated in other embodiments. Furthermore, although advantages associated with certain embodiments of the disclosed technology have been described in the context of those embodiments, other embodiments may also exhibit such advantages, and not all embodiments necessarily exhibit such advantages falling within the scope of the technology. Thus, the present disclosure and related technology may encompass other embodiments not explicitly shown or described herein.

[0034] As used herein, the term "and / or" in "A and / or B" refers to A alone, B alone, and both A and B.

[0035] Representative examples of this technique are given below.

[0036] example

[0037] [Example 1] 1. A method comprising: forming an instrumentation conduit support; the instrumentation conduit support includes a carrier portion and a retainer portion; The method, wherein forming the instrumentation conduit support includes integrally forming and embedding (a) a fiber optic strain sensor comprising a conduit support and (b) a fiber optic link comprising the carrier portion via an additive manufacturing process. [Example 2] supporting a helical steam conduit with said instrumentation conduit support; and installing the helical steam conduit and the instrumentation conduit support in a nuclear reactor along a primary flow path positioned to circulate a heated primary flow in thermal communication with the helical steam conduit. [Example 3] The method of any one of Examples 1-2, wherein the instrumentation conduit support is one of a plurality of instrumentation conduit supports that carry the helical steam conduit. [Example 4] The method of any one of Examples 1 to 3, wherein the sensor includes at least one material not included in the conduit support. [Example 5] The method of any one of Examples 1-4, wherein the instrumentation conduit support is formed from stainless steel. [Example 6] The method of any one of Examples 1 to 5, wherein the additive manufacturing process comprises an ultrasonic additive manufacturing process. [Example 7] 1. A method comprising: forming an instrumentation conduit support, the instrumentation conduit support including a carrier portion and a retainer portion, at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process; coupling said sensor to a communication link; A method comprising: [Example 8] supporting a helical steam conduit with said instrumentation conduit support; 8. The method of Example 7, further comprising: installing the helical steam conduit and the instrumentation conduit support in a nuclear reactor along a primary flow path positioned to circulate a heated primary flow in thermal communication with the helical steam conduit. [Example 9] The method of any one of Examples 7 to 8, wherein the communication link includes an optical link. [Example 10] 10. The method of Example 9, further comprising forming at least a portion of the optical link in an outer surface of the at least one of the carrier portion or the retainer portion. [Example 11] The method of any one of Examples 7 to 10, wherein the sensor is formed in an outer surface of the at least one of the carrier portion or the retainer portion. [Example 12] The method of any one of Examples 7 to 11, wherein the sensor comprises a strain sensor. [Example 13] The method of any one of Examples 7 to 12, wherein the sensor comprises a thermal sensor. [Example 14] The method of any one of Examples 7 to 13, wherein the additive manufacturing process comprises an ultrasonic additive manufacturing process. [Example 15] The method of any one of Examples 7 to 14, wherein the process of forming the instrumentation support includes forming the sensor in an outer surface of the at least one of the retainer portion or the carrier portion. [Example 16] 1. A method for sensing a characteristic of a nuclear reactor, comprising: receiving at least one of (a) thermal data or (b) strain data from a sensor integrally formed with a conduit support, the conduit support carrying a helical steam generator conduit in a nuclear reactor; assessing a vibration characteristic of the helical steam generator based on the received data; and A method comprising: [Example 17] Example 17. The method of Example 16, further comprising altering an operating characteristic of the reactor based at least in part on the received data. [Example 18] 18. The method of any one of Examples 16-17, further comprising altering a design of the helical steam generator based at least in part on the received data. [Example 19] The method of any one of Examples 16 to 18, wherein the vibration characteristic is a frequency of the vibratory motion to which the helical steam generator is subjected. [Example 20] The method of any one of Examples 16 to 19, wherein the vibration characteristic is an amplitude of the vibratory motion experienced by the helical steam generator. [Example 21] A device, comprising: an instrumentation conduit support; The instrumentation conduit support comprises: A carrier portion; a retainer portion carried by the carrier portion; and Including, (a) the carrier portion is integrally formed with the sensor via an additive manufacturing process; (b) the retainer portion is integrally formed with the sensor via an additive manufacturing process; or (c) A device that is both (a) and (b). [Example 22] A pressure vessel; a reactor core positioned within the pressure vessel and configured to carry fissile material; and a containment vessel positioned around the pressure vessel; a riser pipe in fluid communication with the reactor core and positioned to direct a flow of a primary fluid upwardly from the reactor core along a primary flow path, the primary flow path also passing downwardly in an annulus between the riser pipe and the pressure vessel to circulate the flow of the primary fluid; a steam generator positioned within the annulus; and Further comprising: 22. The device of example 21, wherein the steam generator includes a helical steam conduit carried by the instrumentation conduit support. [Example 23] 23. The system of any one of Examples 21 to 22, wherein the sensor is embedded in the carrier portion and / or in at least one of the plurality of retainer portions. [Example 24] The system of any one of Examples 21 to 23, wherein the sensor includes an optical sensor, and the system further includes an optical communication link coupled to the optical sensor and positioned within at least one of the carrier portion or the retainer portion.

Claims

1. 1. A method comprising: forming an instrumentation conduit support; the instrumentation conduit support includes a carrier portion and a retainer portion; forming the instrumentation conduit support comprises:

1. A method comprising: integrally forming and embedding (a) a fiber optic strain sensor comprising a conduit support; and (b) a fiber optic link comprising the carrier portion via an additive manufacturing process.

2. supporting a helical steam conduit with said instrumentation conduit support; installing said helical steam conduit and said instrumentation conduit support in a reactor along a primary flow path positioned to circulate a heated primary flow in thermal communication with said helical steam conduit; The method of claim 1 further comprising:

3. The method of claim 2 , wherein the instrumentation conduit support is one of a plurality of instrumentation conduit supports carrying the helical steam conduit.

4. The method of claim 1 , wherein the sensor includes at least one material not included in the conduit support.

5. The method of claim 1 , wherein the instrumentation conduit support is formed from stainless steel.

6. The method of claim 1 , wherein the additive manufacturing process comprises an ultrasonic additive manufacturing process.

7. 1. A method comprising: forming an instrumentation conduit support, the instrumentation conduit support including a carrier portion and a retainer portion, at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process; coupling said sensor to a communication link; A method comprising:

8. supporting a helical steam conduit with said instrumentation conduit support; installing said helical steam conduit and said instrumentation conduit support in a reactor along a primary flow path positioned to circulate a heated primary flow in thermal communication with said helical steam conduit; The method of claim 7, further comprising:

9. The method of claim 7 , wherein the communication link comprises an optical link.

10. The method of claim 9 , further comprising forming at least a portion of the optical link in an outer surface of the at least one of the carrier portion or the retainer portion.

11. The method of claim 7 , wherein the sensor is formed in an exterior surface of the at least one of the carrier portion or the retainer portion.

12. The method of claim 7 , wherein the sensor comprises a strain sensor.

13. The method of claim 7 , wherein the sensor comprises a thermal sensor.

14. The method of claim 7 , wherein the additive manufacturing process comprises an ultrasonic additive manufacturing process.

15. The method of claim 7 , wherein the process of forming the instrumentation conduit support includes forming the sensor in an exterior surface of the at least one of the retainer portion or the carrier portion.

16. 1. A method for sensing a characteristic of a nuclear reactor, comprising: receiving at least one of (a) thermal data or (b) strain data from a sensor integrally formed with a conduit support, the conduit support carrying a helical steam generator conduit in a nuclear reactor; assessing vibration characteristics of the helical steam generator conduit based on the received data; and A method comprising:

17. The method of claim 16 , further comprising altering an operating characteristic of the reactor based at least in part on the received data.

18. The method of claim 16 , further comprising altering a design of the helical steam generator conduit based at least in part on the received data.

19. The method of claim 16 , wherein the vibration characteristic is a frequency of the vibratory motion experienced by the helical steam generator conduit.

20. The method of claim 16 , wherein the vibration characteristic is an amplitude of the vibratory motion experienced by the helical steam generator conduit.

21. A device, comprising: an instrumentation conduit support; The instrumentation conduit support comprises: A carrier portion; a retainer portion carried by the carrier portion; and Including, (a) the carrier portion is integrally formed with the sensor via an additive manufacturing process; (b) the retainer portion is integrally formed with the sensor via an additive manufacturing process; or (c) A device that is both (a) and (b).

22. A pressure vessel; a reactor core positioned within the pressure vessel and configured to carry fissile material; and a containment vessel positioned around the pressure vessel; a riser pipe in fluid communication with the reactor core and positioned to direct a flow of a primary fluid upwardly from the reactor core along a primary flow path, the primary flow path also passing downwardly in an annulus between the riser pipe and the pressure vessel to circulate the flow of the primary fluid; a steam generator positioned within the annulus; and Further comprising:

22. The device of claim 21, wherein the steam generator includes a helical steam conduit carried by the instrumentation conduit support.

23. The device of claim 21 , wherein the sensor is embedded in the carrier portion and / or the retainer portion.

24. the sensor includes an optical sensor; 24. The device of claim 23, further comprising an optical communication link coupled to the optical sensor, the optical communication link being positioned within at least one of the carrier portion or the holder portion.

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