Apparatus, system and method for batch measurement of radioisotope production

Abstract

Disclosed herein is a device configured to measure radioactivity emitted by a plurality of radionuclides. The device includes a gamma detector and a source holder having an outer ring defining a volume and including an orientation feature and a plurality of holes configured to receive one of the plurality of radionuclides. The device also includes a frame including an arm and a center rod, wherein the arm is configured to couple to the outer ring and includes an orientation pin. The center rod can be positioned relative to the volume when the arm is coupled to the outer ring of the source holder. The orientation feature of the source holder is configured to engage the orientation pin of the arm, and the center rod is in a predetermined position relative to the volume when the orientation pin engages the orientation feature.

Description

[0001] Cross-references to related applications

[0002] This application is a continuation-in-part of priority to U.S. non-provisional patent application No. 17 / 060,316, filed October 1, 2020, entitled “DEVICES, SYSTEMS, AND METHODS FOR MEASURING RADIOACTIVE ISOTOPE PRODUCTION IN BULK”, filed pursuant to 35 U.SC §120, the disclosure of which is incorporated herein by reference in its entirety. Technical Field

[0003] This disclosure generally relates to nuclear power generation, and more particularly, to an improved apparatus configured for the batch measurement of radioactive isotope production. Summary of the Invention

[0004] The following summary is provided to facilitate understanding of some of the innovative features characteristic of the aspects disclosed herein, and is not intended to be a complete description. A full understanding of the various aspects can be obtained by considering the entire specification, claims, and abstract as a whole.

[0005] In various aspects, an apparatus configured to measure the radioactivity emitted by a plurality of radionuclides is disclosed. The apparatus includes a gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides. The apparatus also includes a source holder comprising an outer ring defining a volume, wherein the outer ring includes a plurality of holes. Each of the plurality of holes is configured to receive one of the plurality of radionuclides. The outer ring also includes an orientation feature. The apparatus further includes a frame comprising: an arm configured to be coupled to the outer ring of the source holder, wherein the arm includes an orientation pin; and a central rod coupled to the arm. The central rod is configured to be positioned relative to the volume of the source holder when the arm is coupled to the outer ring of the source holder. The orientation feature of the source holder is configured to engage the orientation pin of the arm. When the orientation pin engages the orientation feature, the central rod is positioned relative to the volume in a predetermined position.

[0006] In various aspects, a method for measuring the radioactivity emitted by a plurality of radionuclides is disclosed. The method uses a cage source and a frame, the cage source including an outer ring defining a volume and a plurality of holes, each of the plurality of holes being configured to receive one of the plurality of radionuclides, the frame including an arm coupled to a central rod coupled to a gamma detector, the central rod being coupled to a gamma detector, the outer ring including an orientation feature, the arm including an orientation pin configured to engage the orientation feature, and the central rod being configured to be positioned relative to the volume at a predetermined location when the orientation pin engages the orientation feature. The method includes: attaching an arm to the outer ring of a source holder; arranging the arm and a central rod until the central rod is positioned relative to a predetermined volume; engaging an orientation pin of the arm with an orientation feature of the outer ring of the source holder; inserting one of a plurality of radionuclides into one of a plurality of holes in the outer ring of the source holder; performing a baseline measurement of the radioactivity emitted by the inserted radionuclide using a gamma detector; removing the radionuclide from the hole in the outer ring of the source holder; inserting each of the plurality of radionuclides into the plurality of holes in the outer ring of the source holder; performing a collective measurement of the radioactivity emitted by the plurality of radionuclides; and dividing the collective measurement by the number of radionuclides in the plurality of radionuclides to determine an average measurement of the radioactivity emitted by each of the plurality of radionuclides.

[0007] In various aspects, an apparatus is disclosed configured to measure the radioactivity emitted by a plurality of radionuclides coupled to a source holder defining a volume, wherein the source holder includes directional features. The apparatus includes: an arm configured to be coupled to the source holder, wherein the arm includes directional components corresponding to the directional features of the source holder; and a central rod coupled to the arm, wherein the central rod is configured to be coupled to a gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides, and wherein the central rod is configured to be positioned relative to the volume of the source holder when the arm is coupled to the source holder; wherein the directional features of the source holder indicate a predetermined position associated with the directional components on the source holder, and wherein the predetermined position associated with the directional components on the source holder corresponds to a predetermined position associated with the central rod relative to the volume.

[0008] These and other objects, features, and characteristics of the invention, as well as the functionality of the related elements of the methods of operation and structures, and the economy of combination and manufacture of the parts, will become more apparent upon consideration of the following description and appended claims with reference to the accompanying drawings, all of which form part of this specification, wherein the same reference numerals denote corresponding parts in the various drawings. However, it should be clearly understood that the drawings are for illustrative and descriptive purposes only and are not intended to be construed as limiting the invention. Attached Figure Description

[0009] The various features of the aspects described herein are specifically set forth in the appended claims. However, the various aspects of the organization and operation methods, and their advantages, can be understood from the following description taken in conjunction with the accompanying drawings, which are shown below:

[0010] Figure 1 The illustration shows a perspective view of a source holder of an apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides, according to at least one non-limiting aspect of the present disclosure.

[0011] Figure 2 The illustration shows a perspective view of a frame of an apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides, according to at least one non-limiting aspect of the present disclosure.

[0012] Figure 3 The illustration depicts at least one non-limiting aspect of the present disclosure, configured to be linked to Figure 2 A cross-sectional view of the gamma detector within the frame.

[0013] Figure 4 The illustration shows a perspective view of an apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides, according to at least one non-limiting aspect of the present disclosure.

[0014] Figure 5 The illustration shows a perspective view of another apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides, according to at least one non-limiting aspect of the present disclosure.

[0015] Figure 6 The illustration depicts at least one non-limiting aspect of the present disclosure, using Figure 4 and Figure 5 The flowchart depicts a method for measuring the radioactivity emitted by multiple radionuclides using a device.

[0016] Figure 7 The illustration shows a perspective view of another source holder of an apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides, according to at least one non-limiting aspect of the present disclosure.

[0017] In several views, corresponding reference numerals indicate corresponding parts. The examples set forth herein illustrate various aspects of the invention in one form, and these examples should not be construed as limiting the scope of the invention in any way. Detailed Implementation

[0018] Numerous specific details are set forth to provide a comprehensive understanding of the overall structure, function, manufacture, and use of the aspects described herein and illustrated in the accompanying drawings. Well-known operations, components, and elements are not described in detail to avoid obscuring the aspects described in the specification. The reader will understand that the aspects described and illustrated herein are non-limiting examples, and therefore should be appreciated that the specific structural and functional details disclosed herein may be representative and illustrative. Variations and modifications may be made thereto without departing from the scope of the claims. Furthermore, it should be understood that terms such as “forward,” “backward,” “left,” “right,” “upward,” and “downward” are convenient words and should not be construed as limiting terms.

[0019] In the following description, in several views of the accompanying drawings, the same reference numerals denote the same or corresponding parts. Furthermore, in the following description, it should be understood that terms such as “forward,” “backward,” “left,” “right,” “upward,” and “downward” are convenient words and should not be construed as restrictive terms.

[0020] Before explaining the various aspects of the articulated manipulator in detail, it should be noted that the illustrative examples are not limited in application or use to the details of the construction and arrangement of the parts shown in the drawings and description. The illustrative examples may be implemented or incorporated in other aspects, variations, and modifications, and may be practiced or implemented in various ways. Furthermore, unless otherwise stated, the terminology and expressions used herein are chosen for the convenience of the reader in describing the illustrative examples and are not intended to limit the invention. Moreover, it should be understood that one or more aspects, expressions, and / or examples described below may be combined with any one or more of the other aspects, expressions, and / or examples described below.

[0021] This disclosure relates to apparatus, systems, and methods for the batch production of capsules containing radioisotopes. Radionuclides (e.g., atomic variants of cobalt-60, molybdenum-99, cesium-137, iodine-131, strontium-90, technetium-99, americium-241, and / or plutonium, uranium, radium, radon, thorium, and tritium) have a wide range of useful applications. For example, radionuclides can be used to improve the safety of medical devices, assist in cancer treatment, and reduce pathogens in food and other products. However, radioisotopes emit harmful gamma rays, which, depending on the level of exposure, can be carcinogenic to humans. This complicates the production, handling, and transportation of radionuclides. Despite these inherent risks, industry continues to produce and ship large quantities of radionuclides, expanding their diverse uses and attempting to fully realize their potential.

[0022] To ensure the safe shipment of large quantities of radionuclides, manufacturers must comply with numerous government regulations and contractual obligations regarding the amount of gamma rays emitted by each radionuclide capsule in a batch and the entire batch of radionuclides. While this disclosure discusses radionuclides configured as capsules, it should be understood that the disclosed invention can be implemented (or readily modified) to measure the radioactivity emitted by any number of radionuclides in any geometric configuration, not necessarily capsule-shaped radionuclides. Therefore, the term "capsule" should not be construed as a geometric limitation on the radionuclide.

[0023] Traditionally, each radionuclide capsule is evaluated individually. However, this is both time-consuming and highly inefficient, especially for larger shipments that may contain hundreds or even thousands of radionuclide capsules. Therefore, conventional methods for shipping radionuclides are cumbersome, inefficient, and prone to human error. These problems are only amplified for radionuclides that must be submerged in water to protect or shield personnel from hazardous gamma rays. Therefore, there is a need for efficient, batch-measurement apparatus, systems, and methods for radioisotope production capsules. Such apparatus, systems, and methods will save money and time, improve safety, and enhance manufacturers' compliance with government regulations and contractual obligations.

[0024] Now for reference Figure 1 According to at least one non-limiting aspect of this disclosure, a perspective view of a source holder 100 configured to batch measure the radioactivity emitted by a plurality of radionuclides 106 is depicted. Figure 1 The source holder 100 is configured to securely store and transport large loads of radionuclides. For example, Figure 1 The source holder 100 can be used to transport 48 radionuclide capsules. However, it should be understood that... Figure 1 The capacity of the source holder 100 can be easily scaled or otherwise reconfigured to accommodate more or fewer radionuclides of any desired form, provided that the storage geometry remains symmetrical about 360 degrees with respect to its centerline. Therefore, it is advantageous to streamline the generation of radionuclides stored in [the source holder]. Figure 1 The number of measurements required to accurately measure the amount of gamma rays emitted by multiple radionuclides 106 in the source holder 100 is necessary because doing so will enable the technicians of the source holder 100 to quickly verify compliance with government regulations and contractual obligations.

[0025] Further reference Figure 1 , Figure 1 The source holder 100 may include one or more outer rings 102 defining a certain volume 104. According to... Figure 1In a non-limiting aspect, the outer ring 102 is circular, and therefore the volume 104 is cylindrical. However, this disclosure contemplates that the source holder 100 may include any number of geometric configurations and other non-limiting aspects of the volume, provided that the geometry and volume are symmetrical about 360 degrees with respect to their centerlines. Figure 1 The outer ring 104 of the source holder 100 may also include a plurality of holes 105, each of which can be configured to receive one of a plurality of radionuclides 106. However, this disclosure contemplates other means of receiving and securing the radionuclides 106. For example, Figure 1 The source retainer 100 may additionally and / or alternatively include clamping components, brackets, and / or other structural elements to assist or replace [other components]. Figure 1 The non-limiting embodiments depict a plurality of holes 105. These structural components most simply secure the radionuclide 106 to a predetermined location on the source holder 100, namely at the centerline.

[0026] It is worth noting that, Figure 1 The source holder 100 may be configured in a 360-degree shape such that each radionuclide is equidistant from the center point of a circular plane defined by the upper surface of the outer ring 102. For example, the source holder 100 of FIG. 100 may include an inner diameter D1. A plurality of holes 105 may be defined in the outer ring 106 such that when radionuclides are mounted, each of the plurality of radionuclides 106 is positioned at the same distance from the center point of the cylindrical volume 104, or in other words, the center point of the inner diameter D1. However, the radionuclides 106 may be configured to be equidistant from any reference point on the source holder 100 in any other geometric configuration. It should be understood that Figure 1 The cylindrical source holder 100 is depicted merely for illustrative purposes.

[0027] according to Figure 1 In a non-limiting aspect, the structure of the radionuclide 106 can be designed as an elongated rod. Therefore, the source holder 100 may include three outer rings 102 supported by one or more spacers 109, the spacers being configured to orient and support the outer rings 102 such that a plurality of holes 105 in the first outer ring 102 are aligned with a plurality of holes 105 in the second outer ring 102. Each of the plurality of holes 105 may include a circular bore configured to accommodate the circular cross-section of each of the radionuclides 106. This allows the rod-shaped radionuclide 106 to be properly inserted into the hole 105 and supported. Figure 1Within each outer ring 102 of the source holder 100. However, this disclosure contemplates other non-limiting aspects in which the radionuclide 106 may include different shapes and sizes. As discussed above, this disclosure contemplates other non-limiting aspects in which the source holder 106 may include components of different shapes and configurations to effectively accommodate and secure radionuclide 106 of any shape. Once the radionuclide 106 is inserted into the orifice 105, the source holder 100 may be immersed in water for testing and / or treatment.

[0028] Further reference Figure 1 The source retainer 100 may also include orientation features 107, such as notches, slots, openings, and / or the like. Figure 1 In a non-limiting aspect, the directional feature 107 includes a directional notch configured to receive the frame 200. Figure 2 ) targeted sales 209 ( Figure 2 The frame is configured to be coupled to the source retainer 100. As will be discussed in further detail, the orientation notch 107 is specifically positioned such that it is coupled to the frame 200. Figure 2 ) center rod 208 ( Figure 2 ) gamma detector 207 ( Figure 2 It is positioned at a predetermined location within a cylindrical volume of 104. Although Figure 1 The source retainer 100 may include a single orientation notch 107, but this disclosure contemplates that the source retainer 100 may include a plurality of orientation notches 107, or allow a technician to attach to the frame 200. Figure 2 ) center rod 208 ( Figure 2 ) gamma detector 207 ( Figure 2 Other non-limiting aspects of positioning other geometric features 107 at various predetermined locations within the cylindrical volume 104. This allows technicians to reorient and reposition the gamma detector 207. Figure 2 This is to accommodate error margins or improve measurement accuracy. According to some other non-limiting aspects, the source holder may include pre-existing geometric features, such as the gamma detector 207. Figure 2 The source holder can be configured to be positioned around this geometric feature. For example, in some non-limiting aspects, the source holder may include a central member that protrudes from the bottom of the source holder through the center of the cylindrical volume 104. Thus, a gamma detector—such as a self-powered detector 302—can be configured to... Figure 3 - It can be strategically positioned around the central component as needed, instead of via frame 200 ( Figure 2 ) center rod 208 ( Figure 2 Gamma detectors suspended within a cylindrical volume of 104—such as the ion chamber detector 207. Figure 2 ).

[0029] Now for reference Figure 2 According to at least one aspect of this disclosure, a method configured for batch measurement of multiple radionuclides 106 ( Figure 1 A perspective view of the frame 200 of the device for emitting radioactive activity. According to... Figure 2 In a non-limiting aspect, frame 200 may include a central bar 208, and a first arm 201, a second arm 202, a third arm 203, and a fourth arm 204. Arms 201, 202, 203, and 204 may be specifically configured to connect to the outer ring 102 of source retainer 100. For example, the first arm 201 and the fourth arm 204 may together define a frame diameter D2 larger than that of source retainer 100. Figure 1 The inner diameter D1 of ) Figure 1 Therefore, the first arm 201 and the fourth arm 204 can support the frame 200, so that the central rod 208 is suspended from the source retainer 100. Figure 1 The volume of the cylinder is 104 ( Figure 1 However, it should be understood that frame 200 may include any number of arms 201, 202, 203, 204 in different configurations to achieve the same result. For example, according to another non-limiting aspect of this disclosure, frame 200 may include a single arm 201 configured to be clamped into outer ring 102. Figure 1 And the center rod 208 is suspended from the source holder 100. Figure 1 The volume of the cylinder is 104 ( Figure 1 )Inside.

[0030] Still referencing Figure 2 Furthermore, according to some non-limiting aspects of this disclosure, once the arms 201, 202, 203, 204 of the frame 200 are installed, these arms can be configured relative to the source retainer 100. Figure 1 ) outer ring 102 ( Figure 1 ( ) movement. For example, arms 201, 202, 203, 204 may include additional structural components, such as hinges, rollers, tracks and / or the like, which can be used to angle arms 201, 202, 203, 204 relative to the plane defined by the top surface of the outer ring 102. Thus, frame 200, and more specifically arms 201, 202, 203, 204, can be articulated, thereby enabling movement within a cylindrical volume 104 ( Figure 1 The center rod 208 moves between multiple predetermined positions within the range.

[0031] Further reference Figure 2 The central rod 208 of the frame 200 can be configured to suspend the gamma detector 207 from the source holder 100. Figure 1The volume of the cylinder is 104 ( Figure 1 Within this, the gamma detector 107 will be exposed to multiple radioactive nuclides 106 ( Figure 1 Gamma rays emitted. According to Figure 2 In a non-limiting aspect, the gamma detector 207 may be integrated with and located at the end of the central rod 208. The central rod 208 may be further configured to include and / or house a signal cable 206, allowing signals to be transmitted from the gamma detector 207 to a remote data acquisition unit. This allows technicians to safely monitor the detected signals from multiple radioactive nuclides 106 (…). Figure 1 Measurements of at least one emitted gamma ray from (). It should be understood that, although Figure 2 Non-limiting aspects include a signal cable 206 that transmits signals from the gamma detector 207 to a data acquisition unit located at a distance, but other non-limiting aspects include the gamma detector 207 being configurable for wireless communication.

[0032] According to other non-limiting aspects of this disclosure, Figure 2 The central rod 208 can be further configured to be coupled to an external gamma detector 207. For example, the gamma detector 207 may include a farmerion chamber mounted on a sleeve configured to be mounted above and around the end of the central rod 208. The sleeve may include a housing specifically configured to position the gamma detector 207 at a desired orientation relative to the central rod 208, such as a centerline. According to other non-limiting embodiments of this disclosure, the gamma detector 207 may also include a self-powered detector (e.g., platinum). The self-powered detector may be configured to be wound around the end of the central rod 208 in a tightly helical configuration, such as… Figure 3 As depicted in the text.

[0033] although Figure 2 The non-limiting aspect depicts a gamma detector 207 attached to the end of the central rod 208; however, it should be understood that, according to other non-limiting aspects, depending on user preference and / or the intended application of the frame 200, any number of detectors can be attached to the central rod 208. For example, the central rod 208 is configured such that a technician can attach any number of spectrometers or non-invasive testing equipment to the central rod in a manner similar to the gamma detector 207. Therefore, the technician can utilize... Figure 2The frame 200 allows for the performance of any number of tests on a batch of radionuclides, thereby ensuring compliance with any number of government regulations and / or contractual obligations. Alternatively and / or additionally, it should be understood that, in other non-limiting respects, the central rod 208 can be configured to simultaneously accommodate any number of gamma detectors 207, spectrometers, and / or non-invasive testing equipment. This provides a degree of modularity and flexibility in use for the frame 200, enabling technicians to perform any number of tests on a batch of radionuclides using the same frame 200 by simply replacing the gamma detector with another spectrometer and / or a single testing device.

[0034] Now for reference Figure 3 According to at least one non-limiting aspect of this disclosure, a configuration for connecting to Figure 2 A cross-sectional view of the gamma detector 300 frame. According to... Figure 3 In a non-limiting aspect, the gamma detector 300 may include a self-powered detector 302 located around the inner tube 304 and a positioned outer tube 306. Center rod 208 ( Figure 2 The inner tube 304 can be formed. However, in other non-limiting aspects of this disclosure, the gamma detector 300 may include a separate tube serving as a sleeve, the sleeve being configured to be coupled to the central rod 208. Figure 2 The outer tube 306, the self-powered detector 302, and the inner tube 304 can be specifically configured to ensure that the self-powered detector 302 does not interfere with the center rod 208. Figure 2 ) moves because the self-powered detector 302 is relative to multiple radionuclides 106 ( Figure 1 The orientation of the object will affect the measurement.

[0035] Further reference Figure 3 The self-powered detector 302 can be used to measure multiple radioactive nuclides 106 ( Figure 1 The amount of gamma rays emitted. The self-powered detector 302 can measure the amount of gamma rays because a current is induced throughout the helical configuration when the self-powered detector 302 is near the radionuclide. The current induced within the self-powered detector 302 can be measured in a variety of different ways. For example, the sensitivity of the self-powered detector 302 can be calculated by testing and, based on known gamma ray exposure, will vary depending on the amount of current generated, given the length of the self-powered detector 302. This is provided that the self-powered detector 302 is correctly positioned within the source holder 100. Figure 1 The volume of the cylinder is 104 ( Figure 1 Within this range, the calculated sensitivity can be used to measure multiple radioactive nuclides 10⁶ ( Figure 1 The collective gamma rays emitted. Although Figure 3The self-powered detector 302 is configured to measure gamma rays, but according to other aspects of this disclosure, the self-powered detector 302 can be configured to measure other types of radiation. Additionally, although... Figure 3 The gamma detector 300 may include a self-powered detector 302 configured to measure gamma rays, but in some other non-limiting aspects, it is contemplated that the gamma detector 300 may include any number of radiation detectors (e.g., a Farmer ionization chamber and / or the like).

[0036] Now for reference Figure 4 According to at least one non-limiting aspect of this disclosure, a perspective view is depicted of an apparatus 400 configured for batch measurement of the radioactivity emitted by a plurality of radionuclides 404. Figure 4 In a non-limiting aspect, device 40 may include components respectively similar to Figure 1 and Figure 2 The source holder 100 and frame 200 are depicted in the image, including source holder 402 and frame 408. Generally speaking, Figure 4 The illustration shows how previously disclosed components can be integrated into a device 400 configured to batch measure the radioactivity emitted by multiple radionuclides 41. For example, a technician can use... Figure 4 The device 400 is used to store and ship large quantities of radioactive nuclide 404 (deliverables specified in the contract) to the receiving customer. Alternatively and / or additionally, technicians may use Figure 4 The device 400 internally stores and transports large quantities of radioactive nuclide 404. In any case, Figure 4 The device 400 can be used to efficiently ensure that the shipment of radionuclide 404 (and more specifically, the radioactivity emitted by radionuclide 404) complies with government regulations and / or contractual obligations.

[0037] As discussed above, the orientation and / or position of the gamma detector 414 relative to the plurality of radionuclides 404 can affect the integrity of the measurement. Therefore, the gamma detector 414 can be optimally positioned within the cylindrical volume defined by the outer ring 406, and thus can receive the desired exposure to the radioactivity emitted by the plurality of radionuclides 404. Figure 4 As can be seen from the non-limiting aspects, the arm 410 of the frame 408 is configured to rest on the outer ring 406 of the source holder 402. Therefore, the central rod 412 can suspend the gamma detector 414 within the cylindrical volume defined by the outer ring 46. It should be understood that the position of the gamma detector 414 within the cylindrical volume defined by the outer ring 406 can be adjusted by modifying the length of the central rod 46. Therefore, the present disclosure contemplates non-limiting aspects in which the central rod 412 can be telescopically configured.

[0038] Alternatively and / or additionally, the directional notch 422 of the source retainer 402 can be configured to receive and secure the directional pin 420 of the frame 408. According to Figure 4 In a non-limiting aspect, when the orientation pin 420 of the frame 408 is received by the orientation notch 422 of the source holder 402, the gamma detector 414 can be positioned in a predetermined position relative to the cylindrical volume defined by the outer ring 406. Therefore, a technician does not need to waste time arranging the frame 408 and the source holder 402 to correctly position the gamma detector 414 within the cylindrical volume. Instead, the technician can align the orientation pin 420 with the orientation notch 422. As an additional benefit, when the orientation pin 420 is received by the orientation notch 422, the frame 408 can be secured relative to the source holder 402, thereby ensuring that the desired configuration is not disturbed. Although Figure 4 Non-limiting aspects may include directional pin 420 and directional notch 422, but other non-limiting aspects of this disclosure include any number of mechanical parts and / or features configured to properly orient and secure frame 408 to source retainer 402. For example, various mating geometries, interacting parts, visual markings, and / or combinations thereof may be implemented depending on the intended application and / or the specific preferences of those skilled in the art.

[0039] According to some other non-limiting aspects of this disclosure, Figure 4 The source holder 402 may include more than one orientation notch 422, wherein each orientation notch 422, when engaged with the orientation pin 420 of the frame 408, orients the gamma detector 414 at a specific predetermined position among a plurality of predetermined positions within a volume defined by the outer ring 406. This provides technicians with the flexibility to adjust the position of the gamma detector 414 as needed, while maintaining the aforementioned ease of use and efficiency.

[0040] Still referencing Figure 4The apparatus 400 can be calibrated and / or reconfigured to optimize the integrity of measurements as needed. For example, a technician can use the apparatus frame 408 and source holder 402 to initially orient the gamma detector 414 within the internal volume defined by the outer ring 406. Once the gamma detector 414 is initially positioned, the technician can mount individual radionuclides 414 of a plurality of radionuclides 414 into the source holder 402 and perform a baseline measurement of the radioactivity emitted by the individual radionuclides 414. The technician can then proceed to mount each of the plurality of radionuclides 414 into the source holder 402 and perform a collective measurement of the radioactivity emitted by the plurality of radionuclides 414. The technician can then compare the collective measurement to the baseline measurement and determine a correction factor based at least in part on this comparison. For example, if the baseline measurement for an individual radionuclide 414 is 1 curie, the technician might expect the collective measurement to be 48 curies. However, if the collective measurements deviate significantly from the values ​​predicted based on baseline measurements, a technician can determine a correction factor that indicates an acceptable margin of error. Therefore, the technician can decide, at least in part, to reposition the gamma detector 414 within the cylindrical volume based on the determined correction factor. Figure 4 The aforementioned structural features of the device 400 can help technicians make these adjustments easily, and thus facilitate the more efficient acquisition of accurate data associated with the expected loading.

[0041] In other words, due to the symmetrical geometry of the device 400, it can improve the efficiency of radioactivity measurement. For example, in Figure 4 In a non-limiting aspect, the source holder 402 includes a 360-degree geometry symmetrical with respect to the radial centerline of the plane defined by the outer ring 406. As described above, when the source holder 402 is loaded with a certain number (“X”) of radionuclides 404, the device 400 can achieve a detection efficiency, which can be defined as the calibration efficiency (“E”) multiplied by the number of radionuclides loaded, or X*E.

[0042] Further reference Figure 4Multiple spacers 424 can support the outer ring 406 of the source holder 402. However, the spacers 424 may interfere with the radiation exposure of the gamma detector 414, resulting in a larger calibration error than expected. If such spacers 424 or any other structural feature of the device 400 generates unacceptable calibration errors, various methods can be employed to account for these errors and efficiently calibrate the device 400. For example, the accurate calibration efficiency of the spacers 424 can be determined experimentally or via simulation. Alternatively and / or additionally, the source holder 402 can be modified to include a greater number of spacers 424, each spacer 42 having a smaller diameter. Furthermore, in other non-limiting aspects, the source holder 402 can be modified to include a circumferential support plate that provides structural stability independent of the spacers 424 without interfering with the radiation exposure of the gamma detector 414.

[0043] As discussed earlier, radionuclides must always be handled with care to avoid excessive radiation exposure for workers. This caution imposes limitations on the handling of radionuclides, making not only less efficient but also more complex in batch measurements and shipments. Therefore, Figure 4 The device 400 can be further configured to be submerged in water, which can shield personnel from hazardous exposure. For example, Figure 4 The device 400 can be used for underwater and / or wet source storage models. Therefore, the device 400 may include a manipulator arm 418 having a predetermined length that allows a technician to engage the directional pin with the directional notch from a distance (e.g., above the surface of the water). It should be understood that this length can also be configured to position the technician at a predetermined distance away from multiple radionuclides. Alternatively and / or additionally, the frame 400 and specifically the arm 410 of the frame 400 may be robotically configured for autonomous repositioning relative to the source holder 402. According to some non-limiting aspects, the frame 400 may also include a position sensor that can provide real-time feedback on the position of the gamma detector 414 relative to the radionuclides 404.

[0044] Additionally, Figure 4 The gamma detector 414 can be connected to a signal cable 416, which can be integrated with or routed through the center rod 412 to the surface. For example, the signal cable 416 can transmit signals from the gamma detector 414 to a data acquisition unit located above the water and at a safe distance from the radioactive nuclide 404. It should be understood that, although Figure 4 Non-limiting aspects include a signal cable 416 that transmits signals from the gamma detector 414 to a data acquisition unit located at a distance, but other non-limiting aspects include the gamma detector 414 being configurable for wireless communication.

[0045] Now for reference Figure 5 According to at least one non-limiting aspect of this disclosure, a perspective view is depicted of another apparatus 500 configured for batch measurement of radioactivity emitted by multiple radionuclides. Figure 5 In a non-limiting aspect, device 500 can be with Figure 4 The device 400 is configured in a basically similar manner. However, Figure 5 The device 500 may also include one or more arms 510 movably configured relative to the source retainer 502. Therefore, the frame 508 can be repositioned relative to the source retainer 502. It should be understood that the arms 510 may include any number of structural components and / or features that may facilitate this function. For example, Figure 5 The device 500 may include an arm 510 configured with a locking hinge, which can be manipulated from a safe distance. Alternatively and / or additionally, the arm 510 may include rails and / or rollers to achieve the same effect. A manipulating arm 518 can be used to manipulate the arm 510 from above the water and at a safe distance. Alternatively and / or additionally, the arm 510 of the frame 500, and specifically the frame 500, may be robotically configured for autonomous repositioning relative to the source holder 502. According to some non-limiting aspects, the frame 500 may also include a position sensor that can provide real-time feedback on the position of the gamma detector 514 relative to the radionuclide 504.

[0046] Further reference Figure 5 Arm 510 can be manipulated to adjust frame 508 and more specifically center rod 512 relative to source holder 502. This can subsequently reposition gamma detector 514 relative to the cylindrical volume defined by outer ring 506, and thus reposition the orientation and / or position of gamma detector 514 relative to the plurality of radionuclides 404. For example, according to Figure 5 In a non-limiting aspect, the gamma detector 545 can be located outside the cylindrical volume defined by the outer ring 506, such that the gamma detector 545 is suspended above the outer ring 506 of the source holder 502. This is particularly useful for the source holder 502, which includes geometric features within the cylindrical volume, such as the center member, where the center rod would otherwise be located. However, it should be understood that this disclosure contemplates other non-limiting aspects in which the gamma detector 514 can be located within the cylindrical volume. In some non-limiting aspects, the center rod 512 can be telescopic or otherwise adjustable to accommodate source holders 502 of different designs and configurations, thereby allowing flexibility regarding the position of the gamma detector 514. Therefore, Figure 5Arm 510 of the frame 508 depicted can be manipulated to influence the integrity of the measurement. These features increase the customization of the device 500 configuration and thus provide greater versatility for implementation technicians. In other words, arm 510 can be used in place of directional pins and directional slot openings, or in combination with directional pins and directional slot openings, to optimize efficiency and improve compliance of bulk radionuclide loading.

[0047] Now for reference Figure 6 According to at least one non-limiting aspect of this disclosure, the use of Figure 4 and Figure 5 The flowchart depicts a method 600 for measuring the radioactivity emitted by multiple radionuclides. First, a technician can attach one or more arms of a frame to a source holder 602. As discussed earlier, this can include simply fixing a fixed frame to the outer ring of the source holder, or attaching a hinged frame via a movable component (e.g., a hinge). The technician can then position the arms and specifically the center rod until the gamma detector is in a predetermined position relative to the cylindrical volume defined by the outer ring of the source holder 604. This can include using a manipulator arm, such as... Figure 4 and Figure 5 As depicted in the description. Once the frame is correctly aligned relative to the source holder, a technician can engage the directional pins of the frame with the directional notches 606 of the source holder. Of course, as disclosed above, the device may include alternative components for initial alignment and connection. This will ensure that the gamma detector is correctly positioned and secured for testing.

[0048] Further reference Figure 6Once the gamma detector is initially positioned, technicians can install individual radionuclides from a plurality of radionuclides into the source holder 608. Once installed, technicians can perform baseline measurements of the radioactivity emitted by the individual radionuclides 610 and can continue installing each radionuclide to be shipped into the source holder 612. Technicians can then perform collective measurements of the radioactivity emitted by the entire shipment of radionuclides 614. Technicians can then compare the collective measurements to the baseline measurements and determine a correction factor, at least in part, based on this comparison. For example, if the baseline measurement for a single radionuclide is 1 curie, the technician might expect a collective measurement of 48 curies. However, if the collective measurement deviates significantly from the value expected based on the baseline measurements, the technician can determine a correction factor that indicates an acceptable margin of error. Therefore, the technician can decide, at least in part, to reposition the gamma detector within the cylindrical volume based on the determined correction factor. Without following the steps of method 600, technicians would be forced to measure each radionuclide individually, which is both costly and time-consuming. However, by following the steps described above in Method 600, technicians can easily measure and adjust the measurement method, and thus efficiently collect accurate data associated with the expected loading.

[0049] Now for reference Figure 7 According to at least one non-limiting aspect of this disclosure, a perspective view of another source holder 700 of an apparatus configured to batch measure the radioactivity emitted by a plurality of radionuclides is depicted. Figure 7 Source retainer 700 and Figure 1 The source holder 100 is configured similarly. However, according to Figure 7 In a non-limiting aspect, the source retainer 700 may also include a geometric feature 710 positioned within a volume 704 defined by the outer ring 702 of the source retainer 700. For example, Figure 7 The source holder 700 includes a base plate 703 connected to a spacer bar 709, and the geometry 710 includes a central member extending upward from the base plate 703 into the volume 704, and a central bar 208 of the frame 200 (200). Figure 2 The original location was here. Therefore, gamma detectors (such as the ion chamber detector 207) were originally positioned here. Figure 2 It can be accessed via frame 500 ( Figure 5 ) center rod 512 ( Figure 5 ) suspended above the cylindrical volume 704. Alternatively and / or additionally, depending on the intended application and / or user preference, the gamma detector (such as the self-powered detector 302) Figure 3 It can be strategically positioned around the central component 710.

[0050] The various aspects of the subject matter described herein are set forth in the following numbered clauses:

[0051] Clause 1: An apparatus configured to measure the radioactivity emitted by a plurality of radionuclides, the apparatus comprising: a gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides; a source holder including an outer ring defining a volume, wherein the outer ring includes a plurality of holes, each of the plurality of holes being configured to receive one of the plurality of radionuclides, and wherein the outer ring further includes an orientation feature; and a frame including: an arm configured to be coupled to the outer ring of the source holder, wherein the arm includes an orientation pin; and a center rod coupled to the arm, wherein the center rod is configured to be positioned relative to the volume of the source holder when the arm is coupled to the outer ring of the source holder; wherein the orientation feature of the source holder is configured to engage the orientation pin of the arm, and wherein when the orientation pin engages the orientation feature, the center rod is positioned relative to the volume at a predetermined position.

[0052] Clause 2: The apparatus according to Clause 1, wherein the gamma detector is coupled to the central rod.

[0053] Clause 3: The apparatus according to Clause 1 or 2, wherein the gamma detector further includes a gamma shield configured to reduce the amount of radioactivity emitted by the gamma detector.

[0054] Clause 4: The device according to any one of Clauses 1 to 3, wherein the frame further comprises a second arm coupled to the central rod, wherein the arm and the second arm are movably coupled to the outer ring, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, wherein when the arm and the second arm are in the first position, the central rod is positioned relative to the volume at the predetermined position, and wherein when the arm and the second arm are in the second position, the central rod is positioned relative to the volume at the second predetermined position.

[0055] Clause 5: The apparatus according to any one of Clauses 1 to 4, wherein the gamma detector comprises a Farmer-type ion chamber.

[0056] Clause 6: The apparatus according to any one of Clauses 1 to 5 further includes a housing configured to be coupled to the central rod, wherein the fammer-type ion chamber is coupled to the top side of the housing, and wherein when the housing is coupled to the central rod, the gamma detector is oriented at the center of the volume.

[0057] Clause 7: The apparatus according to any one of Clauses 1 to 6, wherein the source holder includes a geometric feature located within the volume, wherein the gamma detector is coupled to the geometric feature, and wherein the gamma detector includes a self-powered detector.

[0058] Clause 8: The apparatus according to any one of Clauses 1 to 7, wherein the gamma detector comprises a self-powered detector, and wherein the self-powered detector comprises a helix wound around the geometry of the source holder.

[0059] Clause 9: The apparatus according to any one of Clauses 1 to 8 further includes a sleeve configured to connect the gamma detector to the central rod.

[0060] Clause 10: The apparatus according to any one of Clauses 1 to 9 further includes a manipulator arm of a certain length, wherein the manipulator arm is configured to allow a technician to engage the directional pin with the directional feature, and wherein the length is specifically configured to position the technician at a predetermined distance away from the plurality of radionuclides.

[0061] Clause 11: A method for measuring the radioactivity emitted by a plurality of radionuclides using a source holder, the source holder comprising an outer ring and a frame, the outer ring defining a volume and a plurality of holes, wherein each of the plurality of holes is configured to receive one of the plurality of radionuclides, the frame including an arm coupled to a central rod, wherein the central rod is coupled to a gamma detector, wherein the outer ring includes an orientation feature, wherein the arm includes an orientation pin configured to engage the orientation feature, and wherein the central rod is configured to be positioned relative to the volume at a predetermined location when the orientation pin engages the orientation feature, the method comprising: coupling the arm to the outer ring of the source holder; arranging the arm and the central rod until the central rod is positioned relative to the volume at the predetermined location; engaging the arm... The process involves: defining the orientation characteristics of the directional pin and the outer ring of the source holder; inserting one of the plurality of radionuclides into one of the plurality of holes in the outer ring of the source holder; performing a baseline measurement of the radioactivity emitted by the inserted radionuclide using the gamma detector; removing the radionuclide from the hole in the plurality of holes in the outer ring of the source holder; inserting each of the plurality of radionuclides into the plurality of holes in the outer ring of the source holder; performing a collective measurement of the radioactivity emitted by the plurality of radionuclides; and dividing the collective measurement by the number of the plurality of radionuclides to determine an average measurement of the radioactivity emitted by each of the plurality of radionuclides.

[0062] Clause 12: The method according to Clause 11 further comprises: comparing an average measurement of the radioactivity emitted by each of the plurality of radionuclides with an estimated measurement of the radioactivity emitted by each of the plurality of radionuclides; determining a correction factor based at least in part on the comparison of the average measurement of the radioactivity emitted by each of the plurality of radionuclides with the estimated measurement of the radioactivity emitted by each of the plurality of radionuclides; and determining a second predetermined position based at least in part on the determined correction factor.

[0063] Clause 13: The method according to Clause 11 or 12 further comprises: disengaging the directional pin of the arm from the directional feature of the outer ring of the source holder; rearranging the arm and the center rod until the center rod is positioned relative to the volume at the second predetermined position; performing a corrected measurement of the radioactivity emitted by the plurality of radionuclides; and dividing the corrected measurement by the number of radionuclides among the plurality of radionuclides to determine a corrected average measurement of the radioactivity emitted by each of the plurality of radionuclides.

[0064] Clause 14: The method according to any one of Clauses 11 to 13, wherein the frame further comprises a second arm coupled to the central rod, wherein the arm and the second arm are configured to be movably coupled to the outer ring, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, the method further comprising: coupling the second arm to the outer ring of the source holder; and rearranging the arm and the second arm from the first position to the second position until the central rod is positioned relative to the volume at the second predetermined position; performing a corrected measurement of the radioactivity emitted by the plurality of radionuclides; and dividing the corrected measurement by the number of radionuclides among the plurality of radionuclides to determine a corrected average measurement of the radioactivity emitted by each of the plurality of radionuclides.

[0065] Clause 15: The method according to any one of Clauses 11 to 14 further includes immersing the source holder in a fluid, and wherein arranging the arm and the center rod further includes using a manipulator arm configured to allow a technician to engage the orientation pin with the orientation feature from a predetermined distance away from the plurality of radionuclides.

[0066] Clause 16: An apparatus configured to measure the radioactivity emitted by a plurality of radionuclides coupled to a source holder defining a volume, wherein the source holder includes an orientation feature, the apparatus comprising: an arm configured to be coupled to the source holder, wherein the arm includes an orientation member corresponding to the orientation feature of the source holder; and a central rod coupled to the arm, wherein the central rod is configured to be coupled to a gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides, and wherein the central rod is configured to be positioned relative to the volume of the source holder when the arm is coupled to the source holder; wherein the orientation feature of the source holder indicates a predetermined position associated with the orientation member on the source holder, and wherein the predetermined position associated with the orientation member on the source holder corresponds to a predetermined position associated with the central rod relative to the volume.

[0067] Clause 17: The apparatus according to Clause 16 further includes a gamma detector coupled to the central rod, wherein the gamma detector is configured to measure the radioactivity emitted by the plurality of radionuclides.

[0068] Clause 18: The apparatus according to Clause 16 or 17 further includes a second arm coupled to the central rod, wherein the arm and the second arm are movably coupled to the source holder, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, wherein when the arm and the second arm are in the first position, the central rod is positioned in a predetermined position relative to the volume, and wherein when the arm and the second arm are in the second position, the central rod is positioned in a second predetermined position relative to the volume.

[0069] Clause 19: The apparatus according to Clauses 16 to 18 further includes a manipulator arm of a certain length, wherein the manipulator arm is configured to allow a technician to align the directional component relative to the directional feature, and wherein the length is specifically configured to position the technician at a predetermined distance away from the plurality of radionuclides.

[0070] Clause 20: The method according to Clauses 16 to 19, wherein the gamma detector includes a helix wound around a tube configured to be coupled to the central rod.

[0071] All patents, patent applications, publications, or other disclosed materials mentioned herein are incorporated herein by reference in their entirety, just as each individual reference is expressly incorporated by reference separately. All references and any material or portions thereof incorporated herein by reference are said to be incorporated only to the extent that the incorporated material does not conflict with existing definitions, statements, or other disclosed material set forth in this disclosure. Therefore, to the extent necessary, the disclosures described herein supersede any conflicting material incorporated herein by reference, and the disclosures are expressly set forth in control of this application.

[0072] The invention has been described with reference to various exemplary and illustrative aspects. The aspects described herein are to be understood as providing illustrative features of different details of various aspects of the disclosed invention; therefore, unless otherwise stated, it should be understood that, to the extent possible, one or more features, elements, components, components, elements, structures, modules, and / or aspects of a disclosed aspect may be combined, separated, interchanged, and / or rearranged relative to one or more other features, elements, components, components, structures, modules, and / or aspects of a disclosed aspect without departing from the scope of the disclosed invention. Therefore, those skilled in the art will recognize that various substitutions, modifications, or combinations can be made to any exemplary aspect without departing from the scope of the invention. Furthermore, those skilled in the art, upon reading this specification, will recognize or be able to determine many equivalents of the various aspects of the invention described herein using only conventional experimentation. Therefore, the invention is not limited to the description of the various aspects but is limited by the claims.

[0073] Those skilled in the art will recognize that, in general, the terms used herein and especially in the appended claims (e.g., the body of the appended claims) are typically intended to be “open-ended” terms (e.g., the term “comprising” should be interpreted as “including but not limited to,” the term “having” should be interpreted as “at least having,” the term “comprising” should be interpreted as “including but not limited to,” etc.). Those skilled in the art will further understand that if a particular number of statements in the introduced claims is intentional, such intention will be explicitly stated in the claims, and the absence of such statements will not indicate such intention. For example, to aid understanding, the following appended claims may contain the use of the introductory phrases “at least one” and “one or more” to introduce the claims. However, the use of such a phrase should not be interpreted as implying that a claim statement introduced by the indefinite article “a (a or an)” limits any particular claim containing such an introduced claim statement to only one such claim, even when the same claim includes the introductory phrase “one or more” or “at least one” and the indefinite article such as “a (a or an)” (e.g., “a (a and / or an)” should generally be interpreted as meaning “at least one” or “one or more”); the same applies to the use of definite articles used to introduce a claim statement.

[0074] Furthermore, even if a specific number of introduced claims are explicitly stated, those skilled in the art will recognize that such a statement should generally be interpreted as referring to at least the number stated (e.g., a blank statement of "two statements" without other modifiers generally refers to at least two statements, or two or more statements). Moreover, in cases where conventions such as "at least one of A, B, and C" are used, such constructions are generally understood by those skilled in the art to be established in the sense of the convention (e.g., "a system having at least one of A, B, and C" will include, but is not limited to, systems having a single A, a single B, a single C, A and B together, A and C together, B and C together, and / or A, B, and C together). In cases where conventions such as “at least one of A, B, or C” are used, such constructions are generally understood by those skilled in the art to be established in the sense of the convention (e.g., “a system having at least one of A, B, or C” will include, but is not limited to, systems having a single A, a single B, a single C, A and B together, A and C together, B and C together, and / or A, B, and C together). Those skilled in the art will further understand that, typically, whether in the specification, claims, or drawings, separating words and / or phrases presenting two or more alternative terms should be understood to account for the possibility of including one of these terms, any of these terms, or both terms, unless the context otherwise indicates. For example, the phrase “A or B” should generally be understood to include the possibility of “A” or “B” or “A and B”.

[0075] Regarding the appended claims, those skilled in the art will appreciate that the operations recited therein can generally be performed in any order. Furthermore, although the claims are presented in one or more orders, it should be understood that the various operations may be performed in a different order than those described, or may be performed simultaneously. Examples of such alternative orders may include overlapping, interleaving, interruption, reordering, ascending, preparatory, supplementary, simultaneous, reverse, or other different orders, unless the context otherwise indicates. Moreover, unless the context otherwise specifies, terms such as “in response to,” “related,” or other past tense adjectives are generally not intended to exclude such variations.

[0076] It is worth noting that any reference to "one aspect," "one aspect," "one example," or "one example" implies that the specific feature, structure, or characteristic described in connection with that aspect is included in at least one aspect. Therefore, phrases such as "in one aspect," "in one aspect," "in one example," or "in one example" appearing in different places throughout the specification do not necessarily refer to the same aspect. Furthermore, specific features, structures, or characteristics can be combined in any suitable manner with one or more aspects.

[0077] As used in this article, the singular forms “a,” “an,” and “the” include plural references unless otherwise explicitly stated in the text.

[0078] Directional phrases used herein, such as, but not limited to, top, bottom, left, right, lower, upper, front, back, and variations thereof, should relate to the orientation of the elements shown in the accompanying drawings, and not to limitations of the claims, unless otherwise expressly stated.

[0079] Unless otherwise stated, the terms “approximately” or “about” as used in this disclosure mean an acceptable error in a particular value as determined by one of ordinary skill in the art, depending in part on how the value is measured or determined. In some aspects, the terms “approximately” or “about” mean within 1, 2, 3, or 4 standard deviations. In other aspects, the terms “approximately” or “about” mean 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.

[0080] In this specification, unless otherwise stated, all numerical parameters should be understood to begin and be modified in all cases by the term “about,” whereby the numerical parameter possesses the inherent variability of the basic measurement techniques used to determine the parameter value. At the very least, there is no intention to limit the application of the doctrine of equivalents to the scope of the claims; each numerical parameter described herein should be interpreted, at least according to the number of significant digits reported and by applying customary rounding.

[0081] Any numerical range described herein includes all subranges contained within the described range. For example, the range "1 to 100" is intended to include all subranges between the described minimum value of 1 and the described maximum value of 100 (inclusive), that is, a minimum value equal to or greater than 1 and a maximum value equal to or less than 100. Furthermore, all ranges described herein include the endpoints of the described range. For example, the range "1 to 100" includes the endpoints 1 and 100. Any maximum numerical limit described in this specification is intended to include all lower numerical limits contained therein, and any minimum numerical limit described in this specification is intended to include all higher numerical limits contained therein. Therefore, the applicant reserves the right to modify this specification (including the claims) to expressly describe any subranges contained within the expressly described range. All such ranges are described in this specification.

[0082] Any patent applications, patents, non-patent publications, or other disclosures cited in this specification and / or listed in any application data sheets are incorporated herein by reference, provided that the incorporated material does not contradict this document. Therefore, and to the extent necessary, any conflicting material incorporated herein by reference will be superseded by the disclosure expressly set forth herein. Any material, or portions thereof, allegedly incorporated herein by reference that conflicts with existing definitions, statements, or other disclosures set forth herein will be incorporated only to the extent that it will not create a contradiction between the incorporated material and existing disclosures.

[0083] The terms “comprise” (and any form of inclusion, such as “comprise” and “comprising”), “have” (and any form of having, such as “has” and “having”), “include” (and any form of inclusion, such as “includes” and “including”), and “contains” (and any form of containing, such as “contains” and “containing”) are open-ended connecting verbs. Therefore, a system that “comprises,” “has,” “includes,” or “contains” one or more elements possesses, but is not limited to, those one or more elements. Similarly, the elements of a system, apparatus, or appliance that “comprises,” “has,” “includes,” or “contains” one or more features possess those one or more features, but are not limited to, possessing only those one or more features.

Claims

1. An apparatus configured to measure the radioactivity emitted by a plurality of radionuclides, the apparatus comprising: A gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides; A source holder, the source holder including an outer ring defining a volume, wherein the outer ring includes a plurality of holes, wherein each of the plurality of holes is configured to receive one of the plurality of radionuclides, wherein the outer ring further includes orientation features; as well as The framework includes: An arm, configured to be coupled to the outer ring of the source holder, wherein the arm includes a directional pin; and A center rod, which is connected to the arm, wherein the center rod is configured to be positioned relative to the volume of the source holder when the arm is connected to the outer ring of the source holder; The directional feature of the source holder is configured to engage the directional pin of the arm, and the center rod is positioned relative to the volume in a predetermined position when the directional pin engages the directional feature; and the gamma detector is coupled to the center rod.

2. The apparatus of claim 1, wherein the gamma detector further comprises a gamma shield configured to reduce the amount of radioactivity emitted by the gamma detector.

3. The apparatus of claim 1, wherein the frame further comprises a second arm coupled to the central rod, wherein the arm and the second arm are movably coupled to the outer ring, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, wherein when the arm and the second arm are in the first position, the central rod is positioned at a predetermined position relative to the volume, and wherein when the arm and the second arm are in the second position, the central rod is positioned at a second predetermined position relative to the volume.

4. The apparatus of claim 1, wherein the gamma detector comprises a Farmer-type ion chamber.

5. The apparatus of claim 4, further comprising a housing configured to be coupled to the central rod, wherein the fammer-type ion chamber is coupled to the top side of the housing, and wherein when the housing is coupled to the central rod, the gamma detector is oriented at the center of the volume.

6. The apparatus of claim 1, wherein the source holder includes a geometric feature located within the volume, wherein the gamma detector is coupled to the geometric feature, and wherein the gamma detector includes a self-powered detector.

7. The apparatus of claim 6, wherein the gamma detector comprises a self-powered detector, and wherein the self-powered detector comprises a helix wound around the geometry of the source holder.

8. The apparatus of claim 1, further comprising a sleeve configured to connect the gamma detector to the central rod.

9. The apparatus of claim 1, further comprising a manipulator arm of a specified length, wherein the manipulator arm is configured to allow a technician to engage the directional pin with the directional feature, and wherein the length is specifically configured to position the technician at a predetermined distance from the plurality of radionuclides.

10. A method for measuring the radioactivity emitted by a plurality of radionuclides using a source holder, the source holder comprising an outer ring and a frame, the outer ring defining a volume and a plurality of holes, each of the plurality of holes being configured to receive one of the plurality of radionuclides, the frame including an arm coupled to a central rod, wherein the central rod is coupled to a gamma detector, wherein the outer ring includes an orientation feature, wherein the arm includes an orientation pin configured to engage the orientation feature, and wherein the central rod is configured to be positioned relative to the volume when the orientation pin engages the orientation feature, the method comprising: Connect the arm to the outer ring of the source holder; Arrange the arm and the center rod until the center rod is positioned relative to the volume at a predetermined position; The orientation pin of the engaging arm and the orientation feature of the outer ring of the source retainer; One of the plurality of radionuclides is inserted into one of the plurality of holes in the outer ring of the source holder; The gamma detector is used to perform baseline measurements of the radioactivity emitted by the inserted radionuclides. The radionuclide is removed from the plurality of radionuclides through the holes of the plurality of holes in the outer ring of the source holder; Each of the plurality of radionuclides is inserted into one of the plurality of holes in the outer ring of the source holder; Collectively measure the radioactivity emitted by the multiple radionuclides; as well as Divide the collective measurement by the number of radionuclides of the plurality of radionuclides to determine the average measurement of the radioactivity emitted by each radionuclide of the plurality of radionuclides.

11. The method of claim 10, further comprising: The average measurement of the radioactivity emitted by each of the plurality of radionuclides is compared with the estimated measurement of the radioactivity emitted by each of the plurality of radionuclides. The correction factor is determined at least in part based on a comparison of the average measurement of the radioactivity emitted by each of the plurality of radionuclides with the estimated measurement of the radioactivity emitted by each of the plurality of radionuclides. as well as The second predetermined position is determined at least in part based on a defined correction factor.

12. The method of claim 11, further comprising: Disengage the directional pin of the arm from the directional feature of the outer ring of the source cage; Rearrange the arm and the center rod until the center rod is positioned relative to the volume at the second predetermined position; The radioactivity emitted by the plurality of radionuclides is calibrated and measured; as well as The corrected measurement is divided by the number of radionuclides among the plurality of radionuclides to determine the corrected average measurement of the radioactivity emitted by each of the plurality of radionuclides.

13. The method of claim 11, wherein the frame further comprises a second arm coupled to the central rod, wherein the arm and the second arm are configured to be movably coupled to the outer ring, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, the method further comprising: The second arm is connected to the outer ring of the source holder; as well as Reposition the arm and the second arm from the first position to the second position until the center rod is positioned relative to the volume at the second predetermined position; The radioactivity emitted by the plurality of radionuclides is calibrated and measured; as well as The corrected measurement is divided by the number of radionuclides among the plurality of radionuclides to determine the corrected average measurement of the radioactivity emitted by each of the plurality of radionuclides.

14. The method of claim 10, further comprising immersing the source holder in a fluid, and wherein arranging the arm and the center rod further comprises using a manipulator arm configured to allow a technician to engage the orientation pin with the orientation feature from a predetermined distance away from the plurality of radionuclides.

15. An apparatus configured to measure the radioactivity emitted by a plurality of radionuclides coupled to a source holder, the source holder defining a volume, wherein the source holder includes orientation features. The device includes: An arm configured to be coupled to the source holder, wherein the arm includes an orientation member corresponding to the orientation feature of the source holder; and A central rod, connected to the arm, wherein the central rod is configured to be connected to a gamma detector configured to measure the radioactivity emitted by the plurality of radionuclides, and wherein the central rod is configured to be positioned relative to the volume of the source holder when the arm is connected to the source holder. The orientation feature of the source holder indicates a predetermined position associated with the orientation component on the source holder, and the predetermined position associated with the orientation component on the source holder corresponds to a predetermined position associated with the center rod relative to the volume. The device further includes a gamma detector connected to the central rod, wherein the gamma detector is configured to measure the radioactivity emitted by the plurality of radionuclides.

16. The apparatus of claim 15, further comprising a second arm coupled to the central rod, wherein the arm and the second arm are movably coupled to the source holder, wherein the arm and the second arm are movable between a first position relative to the source holder and a second position relative to the source holder, wherein when the arm and the second arm are in the first position, the central rod is positioned at a predetermined position relative to the volume, and wherein when the arm and the second arm are in the second position, the central rod is positioned at a second predetermined position relative to the volume.

17. The apparatus of claim 15, further comprising a manipulator arm of a certain length, wherein the manipulator arm is configured to allow a technician to align the directional component relative to the directional feature, and wherein the length is specifically configured to position the technician at a predetermined distance away from the plurality of radionuclides.

18. The apparatus of claim 15, wherein the gamma detector includes a helix wound around a tube configured to be coupled to the central rod.

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