Apparatus, system, and method for measuring radioisotope production in bulk

Abstract

Disclosed herein is an apparatus configured to measure radioactivity emitted by multiple radionuclides. The apparatus includes a gamma ray detector and a source cage defining a volume and having an outer ring including an orientation feature and multiple holes configured to receive certain radionuclides from the multiple radionuclides. The apparatus also includes a frame including arms and a central rod, the arms configured to be coupled to the outer ring and including an orientation pin. The central rod can be positioned relative to the volume when the arms are coupled to the outer ring of the source cage. The orientation feature of the source cage is configured to engage with the orientation pin of the arms, and when the orientation pin engages with the orientation feature, the central rod is in a predetermined position relative to the volume.

Description

[Technical Field]

[0001] cross reference This application is a continuation-in-part application claiming priority under 35 U.S.C. § 120 to U.S. Nonprovisional Patent Application No. 17 / 060,316, filed October 1, 2020, entitled "DEVICES, SYSTEMS, AND METHODS FOR MEASURING RADIOACTIVE ISOTOPE PRODUCTION IN BULK."

[0002] The present disclosure relates generally to nuclear power generation and, more particularly, to an improved apparatus configured to measure radioisotope production in bulk. Summary of the Invention

[0003] The following summary is provided to facilitate an understanding of some of the innovative features unique to the embodiments disclosed herein and is not intended to be a complete description, with a full understanding of the various embodiments being gained by taking the specification, claims, and abstract, all of which are taken as a whole.

[0004] In various aspects, an apparatus configured to measure radioactivity emitted by a plurality of radionuclides is disclosed. The apparatus includes a gamma ray detector configured to measure radioactivity emitted by the plurality of radionuclides. The apparatus further includes a source cage including an outer ring defining a volume, the outer ring including a plurality of holes. Each of the plurality of holes is configured to receive a radionuclide from the plurality of radionuclides. The outer ring further includes an orientation feature. The apparatus further includes a frame configured to be coupled to the outer ring of the source cage, the frame including an arm including 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 cage when the arm is coupled to the outer ring of the source cage. The orientation feature of the source cage is configured to engage with the orientation pin of the arm. The central rod is positioned at a predetermined location relative to the volume when the orientation pin engages with the orientation feature.

[0005] In various aspects, a method for measuring radioactivity emitted by a plurality of radionuclides is disclosed, using a source cage including an outer ring defining a volume and a plurality of apertures, each configured to receive a radionuclide of the plurality of radionuclides, and a frame including arms coupled to a central rod, the central rod coupled to a gamma ray detector, the outer ring including an orientation feature, the arms including an orientation pin configured to engage the orientation feature, and the central rod configured to be positioned at a predetermined location relative to the volume when the orientation pin and the orientation feature are engaged. The method includes coupling an arm to an outer ring of a source cage; positioning the arm and central rod until the central rod is positioned at a predetermined location relative to the volume; engaging an orientation pin of the arm with an orientation feature of the outer ring of the source cage; inserting a radionuclide of a plurality of radionuclides into a hole of a plurality of holes in the outer ring of the source cage; obtaining a baseline measurement of radioactivity emitted by the inserted radionuclide using a gamma ray detector; removing the radionuclide of the plurality of radionuclides from the hole of the plurality of holes in the outer ring of the source cage; inserting each radionuclide of the plurality of radionuclides into the plurality of holes in the outer ring of the source cage; obtaining a collective measurement of radioactivity emitted by the plurality of radionuclides; and dividing the collective measurement by the number of radionuclides of the plurality of radionuclides to determine an average measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides.

[0006] In various aspects, an apparatus configured to measure radioactivity emitted by a plurality of radionuclides coupled to a source cage defining a volume, the source cage including an orientation feature, is disclosed, the apparatus including: an arm configured to be coupled to the source cage and including an orientation component corresponding to the orientation feature of the source cage; and a central rod configured to be coupled to the arm and coupled to a gamma ray detector configured to measure the radioactivity emitted by the plurality of radionuclides, the central rod configured to be positioned relative to the volume of the source cage when the arm is coupled to the source cage, the orientation feature of the source cage indicating a predetermined location relative to the orientation component of the source cage, the predetermined location of the source cage relative to the orientation component corresponding to a predetermined location relative to the volume and the central rod.

[0007] These and other objects, features and characteristics of the present invention, together with the method of operation and function of the elements involved and the combination of parts and economy of manufacture, will become more apparent from a consideration of the following description and appended claims, all of which form a part of this specification, when taken in conjunction with the accompanying drawings in which like reference numerals indicate corresponding parts in the various views. It is to be expressly understood, however, that the drawings are for the purpose of illustration and description only and are not intended as a definition of the limits of the invention. [Brief explanation of the drawings]

[0008] The various features of the aspects described herein are set forth with particularity in the appended claims. However, the various aspects, both as to organization and method of operation, together with their advantages may be understood by reference to the following description taken in conjunction with the accompanying drawings, in which:

[0009] [Figure 1] FIG. 1 illustrates a perspective view of a source cage of an apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, according to at least one non-limiting embodiment of the present disclosure. [Figure 2]FIG. 1 illustrates a perspective view of a frame of an apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, according to at least one non-limiting embodiment of the present disclosure. [Figure 3] 3 illustrates a cross-sectional view of a gamma ray detector configured to be coupled to the frame of FIG. 2 in accordance with at least one non-limiting embodiment of the present disclosure. [Figure 4] FIG. 1 illustrates a perspective view of an apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, according to at least one non-limiting embodiment of the present disclosure. [Figure 5] FIG. 1 illustrates a perspective view of another apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, according to at least one non-limiting embodiment of the present disclosure. [Figure 6] 6 illustrates a flow diagram of a method for measuring radioactivity emitted by multiple radionuclides using the apparatus illustrated in FIGS. 4 and 5, according to at least one non-limiting embodiment of the present disclosure. [Figure 7] FIG. 10 illustrates a perspective view of another source cage of an apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, according to at least one non-limiting embodiment of the present disclosure.

[0010] Corresponding reference characters indicate corresponding parts throughout the several views. The exemplifications set forth herein illustrate various aspects of the invention in one form, and such exemplifications should not be construed as limiting the scope of the invention in any manner. DETAILED DESCRIPTION OF THE INVENTION

[0011] Numerous specific details are set forth to provide a thorough understanding of the overall structure, function, manufacture, and use of the embodiments described in this disclosure and illustrated in the accompanying drawings. Well-known operations, components, and elements have not been described in detail so as not to obscure the embodiments described herein. The reader will understand that the embodiments described and illustrated herein are non-limiting examples, and therefore, it will be understood that specific structural and functional details disclosed herein may be representative and exemplary. Modifications and variations thereto may be made without departing from the scope of the claims. Furthermore, it should be understood that terms such as "forward," "rear," "left," "right," "upward," "downward," etc. are terms of convenience and should not be construed as limiting terms. Furthermore, it should be understood that terms such as "forward," "rear," "left," "right," "upward," "downward," etc. are terms of convenience and should not be construed as limiting terms.

[0012] In the following description, like reference numerals designate like or corresponding parts throughout the several views of the drawings. It should also be understood that in the following description, terms such as "front," "rear," "left," "right," "upward," "downward," etc. are used for convenience and should not be construed as limiting terms.

[0013] Before describing various aspects of the articulated manipulator in detail, it should be noted that the examples are not limited in application or use to the details of construction and arrangement of parts illustrated in the accompanying drawings and description. The examples may be implemented or incorporated in other aspects, variations, and modifications, and may be practiced or carried out in various ways. Furthermore, unless otherwise indicated, the terms and phrases used herein have been chosen for the convenience of the reader for the purpose of describing the examples, and not for the purpose of limiting them. It will also be understood that one or more of the following described aspects, aspect expressions, and / or examples may be combined with any one or more of the other following described aspects, aspect expressions, and / or examples.

[0014] The present disclosure is directed to devices, systems, and methods for bulk measurement of radioisotope production capsules. Radionuclides (e.g., Cobalt-60, Molybdenum-99, Cesium-137, Iodine-131, Strontium-90, Technetium-99, Americium-241, and / or atomic variants of 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, aid in cancer treatment, and reduce pathogens in food and other products. However, radioisotopes emit harmful gamma rays that can be carcinogenic to humans, depending on the level of exposure. This can complicate the production, processing, and handling of radionuclides. Despite these inherent risks, industry continues to produce and ship large quantities of radionuclides and expand their many applications in an attempt to maximize their potential.

[0015] To ensure the safe shipment of large quantities of radionuclides, manufacturers must comply with several government regulations and contractual obligations regarding the amount of gamma radiation emitted by each radionuclide capsule in the shipment, as well as the entire shipment of radionuclide capsules. 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 radionuclides in any number of geometric configurations that are not necessarily encapsulated radionuclides. As such, the term "capsule" should not be construed as limiting the geometric form of the radionuclide.

[0016] Traditionally, each radionuclide capsule was assessed individually. However, this is time-consuming and highly inefficient, especially for larger shipments, which may contain hundreds or even thousands of radionuclide capsules. Thus, traditional methods of shipping radionuclides are tedious, inefficient, and prone to human error. These problems only increase for radionuclides that must be submerged in water to protect or shield personnel from dangerous gamma radiation. Therefore, a need exists for devices, systems, and methods for efficiently measuring radioisotope production capsules in bulk. Such devices, systems, and methods would save money and time, increase safety, and improve manufacturers' compliance with government regulations and contractual obligations.

[0017] Referring now to FIG. 1 , a perspective view of a source cage 100 of an apparatus configured to measure the radioactivity emitted by a plurality of radionuclides 106 in bulk is illustrated, in accordance with at least one non-limiting embodiment of the present disclosure. The source cage 100 of FIG. 1 is configured to safely store and ship large shipments of radionuclides. For example, the source cage 100 of FIG. 1 may be used to ship 48 radionuclide capsules. However, it should be understood that the capacity of the source cage 100 of FIG. 1 can be easily scaled or otherwise reconfigured to accommodate more or fewer radionuclides in any desired configuration, so long as the storage geometry remains 360-degree symmetric about its centerline. As such, it is advantageous to streamline the number of measurements required to generate accurate amounts of gamma radiation emitted by the plurality of radionuclides 106 stored in the source cage 100 of FIG. 1 because doing so allows source cage 100 technicians to quickly verify compliance with government regulations and contractual obligations.

[0018] With further reference to FIG. 1 , the source cage 100 of FIG. 1 may include one or more outer rings 102 that define a volume 104. According to the non-limiting embodiment of FIG. 1 , the outer ring 102 is circular, and therefore the volume 104 is cylindrical. However, the present disclosure contemplates other non-limiting embodiments in which the source cage 100 may include any number of geometries and volumes, so long as the geometries and volumes remain 360-degree symmetric about their centerlines. The outer ring 104 of the source cage 100 of FIG. 1 may further include a plurality of holes 105, and each hole 105 of the plurality of holes 105 may be configured to receive a radionuclide 106 of the plurality of radionuclides 106. However, the present disclosure contemplates other means of receiving and securing the radionuclides 106. For example, the source cage 100 of Figure 1 may additionally and / or alternatively include gripping components, cradles, and / or other structural elements to supplement or replace the plurality of holes 105 illustrated in the non-limiting embodiment of Figure 1. These structural elements most simply secure the radionuclide 106 in a predetermined location, i.e., at the centerline, of the source cage 100.

[0019] In particular, the source cage 100 of FIG. 1 may include a 360-degree configuration such that each radionuclide is equidistant from the center point of a circular plane defined by the top surface of the outer ring 102. For example, the source cage 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 installed, each of the plurality of radionuclides 106 is positioned the same distance from the center point of the cylindrical volume 104, i.e., the center point of the inner diameter D1. However, the radionuclides 106 may be configured to be the same distance from any reference point even in source cages 100 of any other geometric configuration. It should be understood that the cylindrical source cage 100 of FIG. 1 is illustrated merely for ease of illustration.

[0020] According to a non-limiting embodiment of FIG. 1 , the radionuclides 106 can be configured as elongated rods. Accordingly, the source cage 100 can include three outer rings 102 supported by one or more standoff rods 109 configured to orient and support the outer rings 102 such that the plurality of holes 105 in a first outer ring 102 aligns with the plurality of holes 105 in a second outer ring 102. Each of the plurality of holes 105 can include a circular hole configured to accommodate the circular cross-section of each of the radionuclides 106. This allows rod-shaped radionuclides 106 to be properly inserted into the holes 105 and supported within each outer ring 102 of the source cage 100 of FIG. 1 . However, the present disclosure contemplates other non-limiting embodiments, and the radionuclides 106 can include various shapes and sizes. As noted above, the present disclosure contemplates other non-limiting embodiments in which source cage 106 may include components of various shapes and configurations to effectively contain and secure any shaped radionuclide 106. Once the radionuclide 106 is inserted into bore 105, source cage 100 may be submerged in water for testing and / or processing.

[0021] 1 , source cage 100 may further include an orientation feature 107, such as a notch, slot, opening, and / or the like. In the non-limiting embodiment of FIG. 1 , orientation feature 107 comprises an orientation notch configured to receive an orientation pin 209 ( FIG. 2 ) of a frame 200 ( FIG. 2 ) configured to be coupled to source cage 100. As discussed in more detail, orientation notch 107 is precisely positioned such that a gamma ray detector 207 ( FIG. 2 ) coupled to a central rod 208 ( FIG. 2 ) of frame 200 ( FIG. 2 ) is positioned at a predetermined location within cylindrical volume 104. While the source cage 100 of FIG. 1 may include a single orientation notch 107, the present disclosure contemplates other non-limiting embodiments in which the source cage 100 may include several orientation notches 107, or any combination of other geometric features 107, allowing a technician to position a gamma ray detector 207 ( FIG. 2 ) coupled to a central rod 208 ( FIG. 2 ) of a frame 200 ( FIG. 2 ) at various predetermined locations within the cylindrical volume 104. This allows a technician to reorient and reposition the gamma ray detector 207 ( FIG. 2 ) to adjust tolerances or improve measurement accuracy. According to yet other non-limiting embodiments, the source cage may include a pre-existing geometric feature upon which the gamma ray detector 207 ( FIG. 2 ) may be configured to be positioned. For example, in some non-limiting embodiments, the source cage may include a centerpiece that protrudes from the bottom of the source cage through the center of the cylindrical volume 104. Thus, if desired, a gamma ray detector such as self-powered detector 302 (FIG. 3) may be strategically positioned around the centerpiece in place of a gamma ray detector such as ion chamber detector 207 (FIG. 2) that is suspended within cylindrical volume 104 via central rod 208 (FIG. 2) of frame 200 (FIG. 2).

[0022] Referring now to FIG. 2, there is illustrated a perspective view of a frame 200 of an apparatus configured to measure radioactivity emitted by a plurality of radionuclides 106 (FIG. 1) in bulk, according to at least one non-limiting embodiment of the present disclosure. According to the non-limiting embodiment of FIG. 2, the frame 200 may include a central rod 208 and a first arm 201, a second arm 202, a third arm 203, and a fourth arm 204. The arms 201, 202, 203, 204 may be specifically configured to couple to the outer ring 102 of the source cage 100. For example, the first arm 201 and the fourth arm 204 may collectively define a frame diameter D2 that is larger than the inner diameter D1 (FIG. 1) of the source cage 100 (FIG. 1). Thus, first arm 201 and fourth arm 204 may support frame 200 such that central rod 208 is suspended within cylindrical volume 104 ( FIG. 1 ) of source cage 100 ( FIG. 1 ). However, it should be understood that frame 200 may include any number of arms 201, 202, 203, 204 in various configurations to achieve the same result. For example, according to another non-limiting aspect of the present disclosure, frame 200 may include a single arm 201 clamped to outer ring 102 ( FIG. 1 ) and configured to suspend central rod 208 within cylindrical volume 104 ( FIG. 1 ) of source cage 100 ( FIG. 1 ).

[0023] 2 , according to some non-limiting aspects of the present disclosure, the arms 201, 202, 203, 204 of the frame 200 may be configured to move relative to the outer ring 102 ( FIG. 1 ) of the source cage 100 ( FIG. 1 ) when they are installed. For example, the arms 201, 202, 203, 204 may include additional structural components such as hinges, rollers, tracks, and / or the like that may be used to angle the arms 201, 202, 203, 204 relative to a plane defined by the top surface of the outer ring 102. Thus, the frame 200, and more specifically the arms 201, 202, 203, 204, may be articulated, thereby allowing the central rod 208 to move between several predetermined locations within the cylindrical volume 104 ( FIG. 1 ).

[0024] 2, the central rod 208 of the frame 200 may be configured to suspend a gamma ray detector 207 within the cylindrical volume 104 (FIG. 1) of the source cage 100 (FIG. 1), such that the gamma ray detector 107 is exposed to gamma rays emitted by the plurality of radionuclides 106 (FIG. 1). According to a non-limiting embodiment of FIG. 2, the gamma ray detector 207 may be integral to the central rod 208 and positioned 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 such that a signal may be routed from the gamma ray detector 207 to a remotely located data acquisition unit. This may allow a technician to safely monitor measurements of the detected gamma rays emitted by at least one of the plurality of radionuclides 106 (FIG. 1). While the non-limiting embodiment of FIG. 2 includes a signal cable 206 that routes signals from the gamma ray detector 207 to a remotely located data acquisition unit, it should be understood that other non-limiting embodiments include a gamma ray detector 207 that may be configured for wireless communication.

[0025] According to other non-limiting aspects of the present disclosure, the central rod 208 of FIG. 2 can be further configured to be coupled to an external gamma ray detector 207. For example, the gamma ray detector 207 can include a pharmaceutical ion chamber mounted on a sleeve configured to be mounted on and around the end of the central rod 208. The sleeve can include a housing precisely configured to position the gamma ray detector 207 in a desired orientation relative to the central rod 208, such as a centerline. According to yet other non-limiting embodiments of the present disclosure, the gamma ray detector 207 can further include a self-powered detector (e.g., platinum). The self-powered detector can be configured to be wrapped around the end of the central rod 208, forming a tight spiral configuration, as illustrated in FIG.

[0026] While the non-limiting embodiment of FIG. 2 illustrates a gamma ray detector 207 coupled to the end of the central rod 208, it should be understood that according to other non-limiting embodiments, any number of detectors may be coupled to the central rod 208 depending on the user preference and / or intended use of the frame 200. For example, the central rod 208 is configured so that a technician may couple any number of spectrometers or non-invasive testing instruments in a manner similar to the gamma ray detector 207. Thus, a technician may utilize the frame 200 of FIG. 2 to perform any number of tests on a bulk shipment of radionuclides, thereby ensuring compliance with any number of government regulations and / or contractual obligations. Alternatively and / or additionally, in still other non-limiting embodiments, it should be understood that the central rod 208 may be configured to accommodate any number of gamma ray detectors 207, spectrometers, and / or non-invasive testing instruments simultaneously. This provides frame 200 with a degree of modularity and flexibility of use, allowing a technician to perform any number of tests on a bulk cargo of radionuclides using the same frame 200 by simply swapping out the gamma ray detector for another spectrometer and / or piece of testing equipment.

[0027] Referring now to FIG. 3 , a cross-sectional view of a gamma ray detector 300 configured to be coupled to the frame of FIG. 2 is illustrated, in accordance with at least one non-limiting embodiment of the present disclosure. According to the non-limiting embodiment of FIG. 3 , the gamma ray detector 300 may include a self-powered detector 302 positioned around an inner tube 304 and an outer tube 306 positioned therearound. A central rod 208 ( FIG. 2 ) may frame the inner tube 304. However, in yet another non-limiting embodiment of the present disclosure, the gamma ray detector 300 may include a separate tube that functions as a sleeve configured to be coupled to the central rod 208 ( FIG. 2 ). The outer tube 306, the self-powered detector 302, and the inner tube 304 may be precisely configured to ensure that the self-powered detector 302 does not move relative to the central rod 208 ( FIG. 2 ), as the orientation of the self-powered detector 302 relative to the plurality of radionuclides 106 ( FIG. 1 ) may affect measurements.

[0028] 3 , the self-powered detector 302 can be used to measure the amount of gamma rays emitted by multiple radionuclides 106 ( FIG. 1 ). The self-powered detector 302 can measure the amount of gamma rays because a current is induced throughout the spiral configuration when the self-powered detector 302 is in proximity to the radionuclides. The current induced in the self-powered detector 302 can be measured in several different ways. For example, the sensitivity of the self-powered detector 302 can be calculated through testing and will vary depending on the amount of current generated based on a known amount of gamma ray exposure and the length of the self-powered detector 302. As long as the self-powered detector 302 is properly positioned within the cylindrical volume 104 ( FIG. 1 ) of the source cage 100 ( FIG. 1 ), the calculated sensitivity can be used to measure the collective gamma rays emitted by the multiple radionuclides 106 ( FIG. 1 ). 3 is configured to measure gamma rays, according to other aspects of the present disclosure, the self-powered detector 302 may be configured to measure other types of radiation. Additionally, while the gamma ray detector 300 of FIG. 3 may include a self-powered detector 302 configured to measure gamma rays, in yet other non-limiting aspects, it is contemplated that the gamma ray detector 300 may include any number of radiation detectors (e.g., pharma ion chambers and / or the like).

[0029] Referring now to FIG. 4 , a perspective view of an apparatus 400 configured to measure radioactivity emitted by a plurality of radionuclides 404 in bulk is illustrated, in accordance with at least one non-limiting embodiment of the present disclosure. According to the non-limiting embodiment of FIG. 4 , the apparatus 40 may include a source cage 402 and a frame 408 similar to the source cage 100 and frame 200 illustrated in FIGS. 1 and 2 , respectively. Generally, FIG. 4 illustrates how previously disclosed elements may be incorporated into an apparatus 400 configured to measure radioactivity emitted by a plurality of radionuclides 41 in bulk. For example, a technician may use the apparatus 400 of FIG. 4 to store and ship bulk quantities of radionuclides 404, i.e., contractual deliverables, to a customer who will receive them. Alternatively and / or additionally, a technician may use the apparatus 400 of FIG. 4 to store and ship bulk quantities of radionuclides 404 internally. In any event, the apparatus 400 of FIG. 4 may be used to efficiently ensure that a shipment of radionuclides 404, or more specifically, the radioactivity emitted by the radionuclides 404, complies with government regulations and / or contractual obligations.

[0030] As discussed above, the orientation and / or position of the gamma ray detector 414 relative to the plurality of radionuclides 404 can affect the integrity of the measurement. Accordingly, the gamma ray detector 414 can be optimally positioned within the cylindrical volume defined by the outer ring 406 and therefore receive the desired exposure to the radioactivity emitted by the plurality of radionuclides 404. As seen in the non-limiting embodiment of FIG. 4 , the arm 410 of the frame 408 is configured to rest on the outer ring 406 of the source cage 402. In this manner, the central rod 412 can suspend the gamma ray detector 414 within the cylindrical volume defined by the outer ring 406. It should be understood that the position of the gamma ray detector 414 within the cylindrical volume defined by the outer ring 406 can be adjusted by modifying the length of the central rod 46. Accordingly, the present disclosure contemplates a non-limiting embodiment in which the central rod 412 can be configured to be extendable.

[0031] Alternatively and / or additionally, the orienting notches 422 of the source cage 402 can be configured to receive and secure the orienting pins 420 of the frame 408. According to the non-limiting embodiment of FIG. 4 , the gamma ray detector 414 can be positioned in a predetermined location relative to the cylindrical volume defined by the outer ring 406 when the orienting pins 420 of the frame 408 are received by the orienting notches 422 of the source cage 402. Thus, a technician does not have to waste time positioning the frame 408 and the source cage 402 to properly position the gamma ray detector 414 within the cylindrical volume. Instead, the technician can align the orienting pins 420 with the orienting notches 422. As an added bonus, the frame 408 can be secured relative to the source cage 402 when the orienting pins 420 are received by the orienting notches 422, thereby ensuring that the desired configuration will not be disturbed. 4 may include orientation pin 420 and orientation notch 422, other non-limiting embodiments of the present disclosure include any number of mechanical components and / or features configured to properly orient and secure frame 408 to source cage 402. For example, various mating geometries, interacting components, visual markings, and / or combinations thereof may be implemented depending on the intended application and / or the preferences of a particular engineer.

[0032] 4 may include two or more orientation notches 422, each of which, when engaged with an orientation pin 420 of the frame 408, will orient the gamma ray detector 414 to a particular predetermined position of a plurality of predetermined positions within the volume defined by the outer ring 406. This may provide a technician with the flexibility to adjust the desired position of the gamma ray detector 414 while maintaining the ease of use and efficiency described above.

[0033] 4 , the device 400 may be calibrated and / or reconfigured, if desired, to optimize measurement integrity. For example, a technician may utilize the device's frame 408 and source cage 402 to initially orient the gamma ray detector 414 within the interior volume defined by the outer ring 406. Once the gamma ray detector 414 is initially positioned, the technician may install a single radionuclide 414 of the multiple radionuclides 414 within the source cage 402 and obtain a baseline measurement of the radioactivity emitted by the single radionuclide 414. The technician may then proceed to install each radionuclide 414 of the multiple radionuclides 414 within the source cage 402 and obtain a collective measurement of the radioactivity emitted by the multiple radionuclides 414. The technician may then compare the collective measurement to the baseline measurement and determine a correction factor based at least in part on the comparison. For example, if the baseline measurement of a single radionuclide 414 was 1 curie, a technician may expect the collective measurement to be 48 curies. However, if the collective measurement deviates significantly from what is expected based on the baseline measurement, the technician may determine a correction factor that may account for the tolerance. Thus, the technician may decide to reposition the gamma ray detector 414 within the cylindrical volume based at least in part on the determined correction factor. The above-described structural features of the device 400 of FIG. 4 may assist the technician in easily making these adjustments, and therefore, facilitate more efficient acquisition of accurate data associated with the expected load.

[0034] In other words, device 400 may be able to improve the efficiency of radiation measurements due to its symmetrical geometry. For example, in the non-limiting embodiment of FIG. 4, source cage 402 includes a 360-degree geometry that is symmetrical about the radial centerline of a plane defined by outer ring 406. As explained above, when source cage 402 is loaded with a number (X) of radionuclides 404, device 400 may achieve a detection efficiency that may be defined as the calibrated efficiency (E) multiplied by the number of installed radionuclides, i.e., X*E.

[0035] With further reference to FIG. 4 , several standoff rods 424 may support the outer ring 406 of the source cage 402. However, the standoff rods 424 may interfere with the radiation exposure of the gamma ray detector 414, thereby imposing a larger than desired calibration error. If such standoff rods 424, or any other structural feature of the apparatus 400, create an unacceptable calibration error, several approaches may take the error into account and efficiently calibrate the apparatus 400. For example, the exact calibration efficiency accounting for the standoffs 424 may be determined either experimentally or via simulation. Alternatively and / or additionally, the source cage 402 may be modified to include a greater number of standoffs 424, each with a smaller diameter. Furthermore, in another non-limiting embodiment, the source cage 402 may be modified to include a circumferential support plate that provides structural stability independent of the standoff rods 424 without interfering with the radiation exposure of the gamma ray detector 414.

[0036] As mentioned above, radionuclides must always be carefully controlled to avoid worker overexposure to radiation. Such caution can result in constraints on radionuclide handling that can only increase inefficiencies and complicate bulk measurement and shipping. Accordingly, the apparatus 400 of FIG. 4 can be further configured to be submerged in water, which can shield personnel from hazardous exposure. For example, the apparatus 400 of FIG. 4 can be utilized in both underwater and / or wet source storage models. Thus, the apparatus 400 includes a maneuvering arm 418 that includes a predetermined length that can enable a technician to engage the orientation pin and orientation notch from a distance (e.g., above the water surface). It should be understood that the length can be further configured to position the technician a predetermined distance away from the plurality of radionuclides. Alternatively and / or additionally, the frame 400, and specifically the arm 410 of the frame 400, can be robotically configured to autonomously reposition the source cage 402. According to some non-limiting embodiments, the frame 400 may further include a position sensor that may provide real-time feedback regarding the position of the gamma ray detector 414 relative to the radionuclide 404 .

[0037] Additionally, the gamma ray detector 414 of Figure 4 may be coupled to a signal cable 416 that may be integral to the surface or routed to the surface via the central rod 412. For example, the signal cable 416 may communicate signals from the gamma ray detector 414 to a data acquisition unit located above the water and a safe distance away from the radionuclides 404. While the non-limiting embodiment of Figure 4 includes a signal cable 416 that routes signals from the gamma ray detector 414 to a remotely located data acquisition unit, it should be understood that other non-limiting embodiments include a gamma ray detector 414 that may be configured for wireless communication.

[0038] Referring now to FIG. 5 , a perspective view of another apparatus 500 configured to measure radioactivity emitted by multiple radionuclides in bulk is illustrated, in accordance with at least one non-limiting embodiment of the present disclosure. According to the non-limiting embodiment of FIG. 5 , apparatus 500 may be configured substantially similar to apparatus 400 of FIG. 4 . However, apparatus 500 of FIG. 5 may further include one or more arms 510 configured to be movable relative to source cage 502. Accordingly, frame 508 may be repositioned relative to source cage 502. Arm 510 may include any number of structural components and / or features that may facilitate this functionality. For example, apparatus 500 of FIG. 5 may include arm 510 configured with a locking hinge that allows it to be manipulated from a safe distance. Alternatively and / or additionally, arm 510 may include a sliding track and / or rollers to achieve the same effect. Maneuvering arm 518 may be used to manipulate arm 510 from above water at a safe distance. Alternatively and / or additionally, frame 500, and more specifically, arm 510 of frame 500, may be robotically configured for autonomous repositioning relative to source cage 502. According to some non-limiting embodiments, frame 500 may further include a position sensor that may provide real-time feedback regarding the position of gamma ray detector 514 relative to radionuclide 504.

[0039] 5 , the arm 510 can be manipulated to adjust the frame 508, and specifically the central rod 512, relative to the source cage 502. This can then reposition the gamma ray detector 514, and thus the gamma ray detector 514, relative to the cylindrical volume defined by the outer ring 506, and thus the plurality of radionuclides 404. For example, according to the non-limiting embodiment of FIG. 5 , the gamma ray detector 545 can be positioned outside the cylindrical volume defined by the outer ring 506 such that the gamma ray detector 545 is suspended above the outer ring 506 of the source cage 502. This can be particularly useful for source cages 502 that include geometric features within the cylindrical volume, such as a centerpiece where the central rod would otherwise be positioned. However, it should be understood that the present disclosure contemplates other non-limiting embodiments in which the gamma ray detector 514 can be positioned within the cylindrical volume. In some non-limiting embodiments, the central rod 512 may be telescoping or otherwise adjustable to accommodate source cages 502 of various designs and configurations, thus allowing flexibility regarding the position of the gamma ray detector 514. In this manner, the arms 510 of the frame 508 illustrated in FIG. 5 may be manipulated to affect the integrity of the measurement. Such a feature enhances customization of the configuration of the device 500 and therefore provides more versatility for implementation by the engineer. In other words, the arms 510 may be used in place of or in conjunction with orientation pins and orientation slot openings to optimize efficiency and improve regulatory compliance of bulk radionuclide loads.

[0040] Referring now to FIG. 6 , a flow diagram of a method 600 for measuring radioactivity emitted by multiple radionuclides using the apparatus illustrated in FIGS. 4 and 5 is illustrated, according to at least one non-limiting embodiment of the present disclosure. First, a technician may couple one or more arms of the frame to the source cage 602. As described above, this may involve simply rigidly mounting the frame fixed to the outer ring of the source cage, or attaching an articulating frame via a movable component (e.g., a hinge). The technician may then position the arms, and specifically the central rod, until the gamma ray detector is in place relative to the cylindrical volume defined by the outer ring of the source cage 604. This may involve the use of a steering arm, as illustrated in FIGS. 4 and 5 . Once the frame is properly aligned relative to the source cage, the technician may engage the orientation pin of the frame and the orientation notch of the source cage 606. Of course, the apparatus may include alternative components for initial alignment and coupling, as disclosed above. This will ensure that the gamma ray detector is properly positioned and secured for testing.

[0041] With further reference to FIG. 6 , once the gamma detector is initially positioned, a technician may install a single radionuclide of the multiple radionuclides within source cage 608. Once installed, the technician may obtain a baseline measurement of the radioactivity emitted by single radionuclide 610 and proceed to install each radionuclide to be shipped within source cage 612. The technician may then obtain an aggregate measurement of the radioactivity emitted by the entire shipment of radionuclides 614. The technician may then compare the aggregate measurement to the baseline measurement and determine a correction factor based at least in part on the comparison. For example, if the baseline measurement of a single radionuclide was 1 curie, the technician may expect the aggregate measurement to be 48 curies. However, if the aggregate measurement deviates significantly from what is expected based on the baseline measurement, the technician may determine a correction factor that may account for tolerances. Accordingly, the technician may decide to reposition the gamma detector within the cylindrical volume based at least in part on the determined correction factor. Without following the steps of the above-described method 600, a technician would be forced to measure each radionuclide one by one, which would be time consuming as well as expensive. However, by following the steps of the above-described method 600, a technician can easily measure and adjust the method of measurement, thus efficiently obtaining accurate data associated with the expected shipment.

[0042] Referring now to FIG. 7 , there is illustrated a perspective view of another source cage 700 of an apparatus configured to measure radioactivity emitted by multiple radionuclides in bulk, in accordance with at least one non-limiting embodiment of the present disclosure. The source cage 700 of FIG. 7 is configured similarly to the source cage 100 of FIG. 1 . However, according to the non-limiting embodiment of FIG. 7 , the source cage 700 may further include a geometric feature 710 positioned within a volume 704 defined by an outer ring 702 of the source cage 700. For example, the source cage 700 of FIG. 7 includes a base plate 703 coupled to standoff rods 709 of the source cage 700, and the geometric feature 710 includes a centerpiece extending from the base plate 703 into the volume 704, where the central rod 208 of the frame 200 ( FIG. 2 ) may be positioned differently. Thus, a gamma ray detector such as ion chamber detector 207 (FIG. 2) may be suspended above cylindrical volume 704 via central rod 512 (FIG. 5) of frame 500 (FIG. 5). Alternatively and / or additionally, gamma ray detectors such as self-powered detector 302 (FIG. 3) may be strategically positioned around centerpiece 710 according to intended application and / or user preference.

[0043] Various aspects of the subject matter described herein are set forth in the following numbered clauses: Item 1: An apparatus configured to measure radioactivity emitted by a plurality of radionuclides, the apparatus comprising: a gamma ray detector configured to measure radioactivity emitted by the plurality of radionuclides; a source cage including an outer ring defining a volume, the outer ring including a plurality of holes, each of the plurality of holes configured to receive a radionuclide from the plurality of radionuclides, the outer ring further including an orientation feature; and a frame, the frame including: an arm coupled to the outer ring of the source cage, the arm including an orientation pin; and a central rod coupled to the arm, the central rod configured to be positioned relative to the volume of the source cage when the arm is coupled to the outer ring of the source cage, the orientation feature of the source cage configured to engage with the orientation pin of the arm, and the central rod being positioned at a predetermined location relative to the volume when the orientation pin engages with the orientation feature. Item 2: The apparatus of item 1, wherein the gamma ray detector is coupled to the central rod. Clause 3: The apparatus of clause 1 or 2, wherein the gamma ray detector further comprises a gamma ray shield configured to reduce the amount of radioactivity emitted by the gamma ray detector. Clause 4: An apparatus described in any of clauses 1 to 3, wherein the frame further includes a second arm connected to the central rod, the arm and the second arm are movably connected to the outer ring, the arm and the second arm are movable between a first position relative to the source cage and a second position relative to the source cage, and the central rod is positioned at a predetermined location relative to the volume when the arm and the second arm are in the first position, and the central rod is positioned at a second predetermined location relative to the volume when the arm and the second arm are in the second position. Item 5: An apparatus according to any one of items 1 to 4, wherein the gamma ray detector comprises a pharmaceutical ion chamber. Clause 6: An apparatus described in any of clauses 1 to 5, further comprising a housing configured to be coupled to the central rod, the pharmaceutical ion chamber being coupled to the top surface of the housing, and the gamma ray detector being oriented toward the center of the volume when the housing is coupled to the central rod. Clause 7: An apparatus described in any of clauses 1 to 6, wherein the source cage comprises a geometric feature positioned within the volume, the gamma ray detector is coupled to the geometric feature, and the gamma ray detector comprises a self-powered detector. Item 8: An apparatus described in any of items 1 to 7, wherein the gamma ray detector includes a self-powered detector, the self-powered detector comprising a spiral wound around a geometric feature of the source cage. Clause 9: The apparatus of any of clauses 1 to 8, further comprising a sleeve configured to couple the gamma ray detector to the central rod. Clause 10: An apparatus described in any of clauses 1-9, further comprising a maneuvering arm including a length, the maneuvering arm configured to enable a technician to engage the orientation pin with the orientation feature, the length precisely configured to position the technician a predetermined distance away from the plurality of radionuclides. Clause 11: A method for measuring radioactivity emitted by a plurality of radionuclides, using a source cage including an outer ring defining a volume and a plurality of holes, each of the plurality of holes configured to receive a radionuclide from the plurality of radionuclides, and a frame including arms coupled to a central rod, the central rod being coupled to a gamma ray detector, the outer ring including an orientation feature, the arms including orientation pins configured to engage with the orientation feature, the central rod being configured to be positioned at a predetermined location relative to the volume when the orientation pins and the orientation feature are engaged, the method comprising: coupling the arms to the outer ring of the source cage; positioning the arms and the central rod until the central rod is positioned at a predetermined location relative to the volume; and connecting the orientation pins of the arms and the source cage to the outer ring of the source cage until the central rod is positioned at a predetermined location relative to the volume. and inserting a radionuclide of the plurality of radionuclides into a hole of the plurality of holes in the outer ring of the source cage; obtaining a baseline measurement of radioactivity emitted by the inserted radionuclide using a gamma ray detector; removing the radionuclide of the plurality of radionuclides from the hole of the plurality of holes in the outer ring of the source cage; inserting each radionuclide of the plurality of radionuclides into the plurality of holes in the outer ring of the source cage; obtaining a collective measurement of radioactivity emitted by the plurality of radionuclides; and dividing the collective measurement by the number of radionuclides of the plurality of radionuclides to determine an average measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides. Clause 12: The method of clause 11, further comprising: comparing an average measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides to an estimated measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides; determining a correction factor based at least in part on the comparison of the average measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides to the estimated measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides; and determining a second predetermined location based at least in part on the determined correction factor. Clause 13: The method of clause 11 or 12, further comprising: disengaging the orientation pin of the arm from the orientation feature of the outer ring of the source cage; repositioning the arm and the central rod until the central rod is positioned at a second predetermined location relative to the volume; obtaining corrected measurements of radioactivity emitted by the plurality of radionuclides; and dividing the corrected measurements by the number of radionuclides among the plurality of radionuclides to determine an average corrected measurement of radioactivity emitted by each radionuclides of the plurality of radionuclides. Clause 14: The method of any of clauses 11 to 13, wherein the frame further comprises a second arm coupled to the central rod, the arm and the second arm configured to be movably coupled to the outer ring, the arm and the second arm movable between a first position relative to the source cage and a second position relative to the source cage, the method further comprising: coupling the second arm to the outer ring of the source cage; repositioning the arm and the second arm from the first position to the second position until the central rod is positioned at a second predetermined location relative to the volume; obtaining corrected measurements of radioactivity emitted by the plurality of radionuclides; and dividing the corrected measurements by the number of radionuclides among the plurality of radionuclides to determine an average corrected measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides. Item 15: The method of any of items 11 to 14, further comprising submerging the source cage in a fluid, and wherein positioning the arm and central rod further comprises using a maneuvering arm configured to enable a technician to engage the orientation pin with the orientation feature at a predetermined distance from the plurality of radionuclides. Clause 16: An apparatus configured to measure radioactivity emitted by a plurality of radionuclides coupled to a source cage defining a volume, the source cage including an orientation feature, the apparatus comprising: an arm configured to be coupled to the source cage and including an orientation component corresponding to the orientation feature of the source cage; and a central rod coupled to the arm and configured to be coupled to a gamma ray detector configured to measure radioactivity emitted by the plurality of radionuclides, the central rod configured to be positioned relative to the volume of the source cage when the arm is coupled to the source cage, wherein the orientation feature of the source cage indicates a predetermined location relative to the orientation component of the source cage, and the predetermined location of the source cage relative to the orientation component corresponds to a predetermined location relative to the central rod with respect to the volume. Clause 17: The apparatus of clause 16, further comprising a gamma ray detector coupled to the central rod, the gamma ray detector configured to measure radioactivity emitted by the plurality of radionuclides. Clause 18: The device described in clause 16 or 17, further comprising a second arm connected to the central rod, the arm and second arm being movably connected to the source cage, the arm and second arm being movable between a first position relative to the source cage and a second position relative to the source cage, the central rod being positioned at a predetermined location relative to the volume when the arm and second arm are in the first position, and the central rod being positioned at a second predetermined location relative to the volume when the arm and second arm are in the second position. Clause 19: The apparatus of clauses 16-18, further comprising a steering arm including a length, the steering arm configured to enable a technician to align the orientation component relative to the orientation feature, the length precisely configured to position the technician a predetermined distance away from the plurality of radionuclides. Clause 20: The method of clauses 16-19, wherein the gamma ray detector comprises a spiral wound around a tube configured to be coupled to a central rod.

[0044] All patents, patent applications, publications, or other disclosure materials mentioned herein are incorporated by reference in their entirety, just as if each individual reference were expressly incorporated by reference. All documents and any material, or portions thereof, mentioned as being incorporated herein by reference are incorporated herein to the extent that the incorporated material does not contradict existing definitions, descriptions, or other disclosure material set forth in this disclosure. Therefore, to the extent necessary, the disclosure set forth herein supersedes any conflicting material incorporated herein by reference, and the disclosure expressly set forth in this application takes precedence.

[0045] The present invention has been described with reference to various exemplary and illustrative embodiments. The embodiments described herein are understood to provide illustrative features of various details of various embodiments of the disclosed invention, and therefore, unless otherwise indicated, it should be understood that, to the extent possible, one or more features, elements, components, ingredients, materials, structures, modules, and / or aspects of the disclosed embodiments can be combined, separated, substituted, and / or rearranged with one or more other features, elements, components, ingredients, materials, structures, modules, and / or aspects of the disclosed embodiments without departing from the scope of the disclosed invention. Accordingly, those skilled in the art will recognize that various substitutions, modifications, or combinations are possible in any of the exemplary embodiments without departing from the scope of the invention. Moreover, those skilled in the art will recognize, or be able to ascertain using no more than routine experimentation, upon review of this specification, many equivalents to the various embodiments of the invention described herein. Accordingly, the present invention is limited not by the description of the various embodiments, but by the scope of the claims.

[0046] Those skilled in the art will recognize that the terms used in this specification, generally, and in the appended claims in particular (e.g., the body of the appended claims), are generally intended as "open" terms (e.g., the term "comprising" should be interpreted as "including, but not limited to," the term "having" should be interpreted as "having at least," the term "including" should be interpreted as "including, but not limited to," etc.). Where a specific number of claims to be introduced is intended, such intention will be expressly recited in the claims; it will further be understood by those skilled in the art that, in the absence of such recitation, no such intention exists. For example, as an aid to understanding, the following appended claims may contain the use of the introductory phrases "at least one" and "one or more" to introduce the recitation of claims. However, the use of such phrases should not be construed as implying that introducing a claim recitation with the indefinite article "a" or "an" limits any particular claim containing such an introduced claim recitation to claims containing only one such recitation, even when that same claim includes the introductory phrase "one or more" or "at least one" and an indefinite article such as "a" or "an" (e.g., "a" and / or "an" should typically be construed to mean "at least one" or "one or more"), nor should the use of a particular article be used to introduce a claim recitation.

[0047] Additionally, even if a specific number of enumerations in an introduced claim are explicitly recited, those skilled in the art will understand that such enumeration should typically be interpreted to mean at least the recited number (e.g., the literal recitation of "two enumerations," without other modifiers, means at least two enumerations, or more than two enumerations). Furthermore, in such cases where a convention similar to "at least one of A, B, and C, etc." is used, such structure is generally intended in the sense that those skilled in the art would understand the convention (e.g., "a system having at least one of A, B, and C" would include, but not be limited to, systems having A alone, B alone, C alone, A and B together, A and C together, B and C together, and / or A, B, and C together, etc.). In those cases where a convention similar to "at least one of A, B, or C, etc." is used, such construction is generally intended in the sense that one of ordinary skill in the art would understand the convention (e.g., "a system having at least one of A, B, or C" would include, but is not limited to, systems having A alone, B alone, C alone, A and B together, A and C together, B and C together, and / or A, B, and C together, etc.). It will be further understood by those of ordinary skill in the art that typical disjunctive words and / or phrases presenting two or more alternative terms, whether in the description, claims, or drawings, should be understood to contemplate the possibility of including one of the terms, either of the terms, or both terms, unless the context dictates otherwise. For example, the phrase "A or B" would typically be understood to include the possibilities of "A" or "B" or "A and B."

[0048] With respect to the appended claims, those skilled in the art will understand that the actions recited therein may generally be performed in any order. Also, while the claim recitations are presented sequentially, it should be understood that various actions may be performed in other orders than those described, or may be performed simultaneously. Examples of such alternative orderings may include overlapping, interleaved, interrupted, reordered, incremental, preliminary, supplemental, simultaneous, reverse, or various other orderings, unless the context dictates otherwise. Furthermore, unless the context dictates otherwise, terms such as "responsive," "related," or other past tense adjectives are generally not intended to exclude such variations.

[0049] It should be noted that any reference to "one embodiment," "one embodiment," "one exemplary embodiment," "one example," etc. means that a particular feature, structure, or characteristic described in connection with an embodiment is included in at least one embodiment. Thus, the appearances of the phrases "in one embodiment," "in one embodiment," "in one exemplary embodiment," and "in one exemplary embodiment" in various places throughout this specification do not necessarily all refer to the same embodiment. Furthermore, particular features, structures, or characteristics may be combined in any suitable manner in one or more embodiments.

[0050] As used herein, the singular forms "a," "an," and "the" include plural references unless the context clearly dictates otherwise.

[0051] Directional expressions used herein, such as, but not limited to, top, bottom, left, right, below, above, front, back, and variations thereof, relate to the orientation of the elements as shown in the accompanying drawings and do not limit the scope of the claims unless expressly stated otherwise.

[0052] The term "about" or "approximately," as used in this disclosure, unless otherwise specified, refers to an acceptable error for a particular value as determined by one of ordinary skill in the art, which depends in part on how the value is measured or determined. In certain aspects, the term "about" or "approximately" means within 1, 2, 3, or 4 standard deviations. In certain aspects, the term "about" or "approximately" means within 50%, 200%, 105%, 100%, 9%, 8%, 7%, 6%, 5%, 4%, 3%, 2%, 1%, 0.5%, or 0.05% of a given value or range.

[0053] As used herein, unless otherwise indicated, all numerical parameters should be understood in all instances to be prefaced and modified by the term "about," which takes into account the inherent variability of the underlying measurement techniques used to determine the numerical value of the parameter. At the very least, and not as an attempt to limit the application of the doctrine of equivalents to the scope of the claims, each numerical parameter set forth herein should at least be construed in light of the number of reported significant digits and by applying ordinary rounding techniques.

[0054] Any numerical range recited herein includes all subranges subsumed within the recited range. For example, a range of "1 to 100" includes all subranges between the recited minimum of 1 and the recited maximum of 100 (inclusive), i.e., all subranges with a minimum of 1 or more and a maximum of 100 or less. Also, all ranges recited herein include the recited endpoints. For example, a range of "1 to 100" includes the endpoints 1 and 100. Any maximum numerical limitation recited herein is intended to include all lower numerical limitations subsumed within the range, and any minimum numerical limitation recited herein is intended to include all higher numerical limitations subsumed within the range. Accordingly, applicants reserve the right to amend this specification, including the claims, to explicitly recite any subranges subsumed within an expressly recited range. All such ranges are inherently set forth herein.

[0055] Any patent application, patent, non-patent publication, or other disclosure material referenced herein and / or listed in any Application Data Sheet is incorporated herein by reference and, to the extent that it does not conflict with the material incorporated herein. Accordingly, the disclosure set forth herein supersedes, to the extent necessary, any conflicting material incorporated herein by reference. All material, or portions thereof, that is referred to as being incorporated herein by reference that conflicts with existing definitions, descriptions, or other disclosure material set forth herein will be incorporated only to the extent that there is no conflict between the incorporated material and the existing disclosure material.

[0056] The terms "comprise" (and any form of comprise, such as "comprises" and "comprising"), "have" (and any form of have, such as "has" and "having"), "include" (and any form of include, such as "includes" and "including"), and "contain" (and any form of contain, such as "contains" and "containing") are open-ended linking verbs. Consequently, a system that "comprises," "has," "includes," or "contains" one or more elements possesses those one or more elements, but is not limited to possessing only those one or more elements. Similarly, a system, device, or device element that "includes," "has," "includes," or "contains" one or more features possesses those one or more features, but is not limited to possessing only those one or more features.

Claims

1. An apparatus configured to measure radioactivity emitted by a plurality of radionuclides, said apparatus comprising: a gamma ray detector configured to measure the radioactivity emitted by the plurality of radionuclides; a source cage comprising an outer ring defining a volume, the outer ring comprising a plurality of apertures, each aperture configured to receive a radionuclide from the plurality of radionuclides, the outer ring further comprising an orientation feature; a frame, the frame comprising: an arm configured to be coupled to the outer ring of the source cage, the arm including an orientation pin; a central rod coupled to the arm, the central rod configured to be positioned relative to the volume of the source cage when the arm is coupled to the outer ring of the source cage; the orientation feature of the source cage is configured to engage with an orientation pin of the arm, and the central rod is positioned at a predetermined location relative to the volume when the orientation pin engages with the orientation feature; the gamma ray detector is coupled to the central rod.

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

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

4. The apparatus of claim 1 , wherein the gamma ray detector comprises a pharmaceutical ion chamber.

5. 5. The device of claim 4, further comprising a housing configured to be coupled to the central rod, the pharmaceutical ion chamber coupled to a top surface of the housing, and the gamma ray detector oriented toward the center of the volume when the housing is coupled to the central rod.

6. 10. The apparatus of claim 1, wherein the source cage comprises a geometric feature positioned within the volume, the gamma ray detector is coupled to the geometric feature, and the gamma ray detector comprises a self-powered detector.

7. 7. The apparatus of claim 6, wherein the gamma ray detector comprises a self-powered detector, the self-powered detector comprising a spiral wound around the geometric feature of the source cage.

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

9. 10. The apparatus of claim 1, further comprising a steering arm including a length configured to allow a technician to engage the orientation pin with the orientation feature, the length precisely configured to position the technician a predetermined distance away from the plurality of radionuclides.

10. 1. A method for measuring radioactivity emitted by a plurality of radionuclides, comprising: a source cage including an outer ring defining a volume and a plurality of holes, each of the plurality of holes configured to receive a radionuclide of the plurality of radionuclides; and a frame including arms coupled to a central rod, the central rod being coupled to a gamma ray detector, the outer ring including an orientation feature, the arms including orientation pins configured to engage with the orientation feature, the central rod configured to be positioned at a predetermined location relative to the volume when the orientation pins and the orientation feature are engaged; coupling the arms to the outer ring of the source cage; positioning the arms and the central rod until the central rod is positioned at the predetermined location relative to the volume; engaging the orientation pin of the arm with the orientation feature of the outer ring of the source cage; inserting a radionuclide from the plurality of radionuclides into a hole from the plurality of holes in the outer ring of the source cage; obtaining a baseline measurement of radioactivity emitted by the inserted radionuclide using the gamma ray detector; removing the radionuclides from the plurality of radionuclides through the holes from the plurality of holes in the outer ring of the source cage; inserting each radionuclide of the plurality of radionuclides into the plurality of holes in the outer ring of the source cage; obtaining collective measurements of radioactivity emitted by said plurality of radionuclides; and dividing the collective measurement by the number of said radionuclides in said plurality of radionuclides to determine an average measurement of radioactivity emitted by each radionuclide in said plurality of radionuclides.

11. comparing the average measure of radioactivity emitted by each radionuclide of the plurality of radionuclides to an estimated measure of radioactivity emitted by each radionuclide of the plurality of radionuclides; determining a correction factor based at least in part on a comparison of the estimated measure of radioactivity emitted by each radionuclide of the plurality of radionuclides to the average measure of radioactivity emitted by each radionuclide of the plurality of radionuclides; The method of claim 10 , further comprising: determining a second predetermined location based at least in part on the determined correction factor.

12. disengaging the orientation pin of the arm from the orientation feature of the outer ring of the source cage; repositioning the arms and the central rod until the central rod is positioned at the second predetermined location relative to the volume; obtaining corrected measurements of radioactivity emitted by said plurality of radionuclides; 12. The method of claim 11, further comprising: dividing the corrected measurement by the number of radionuclides in the plurality of radionuclides to determine an average corrected measurement of radioactivity emitted by each radionuclide in the plurality of radionuclides.

13. the frame further comprises a second arm coupled to the central rod, the arm and the second arm configured to be movably coupled to the outer ring, the arm and the second arm movable between a first position relative to the source cage and a second position relative to the source cage, and the method further comprises: coupling the second arm to the outer ring of the source cage; repositioning the arm and the second arm from the first position to the second position until the central rod is positioned at the second predetermined location relative to the volume; obtaining corrected measurements of radioactivity emitted by said plurality of radionuclides; 12. The method of claim 11, further comprising: dividing the corrected measurement by the number of radionuclides in the plurality of radionuclides to determine an average corrected measurement of radioactivity emitted by each radionuclide in the plurality of radionuclides.

14. 11. The method of claim 10, further comprising submerging the source cage in a fluid, and wherein positioning the arm and the central rod further comprises using a maneuvering arm configured to enable a technician to engage the orientation pin with the orientation feature at a predetermined distance from the plurality of radionuclides.

15. An apparatus configured to measure radioactivity emitted by a plurality of radionuclides coupled to a source cage defining a volume, the source cage comprising an orienting feature, the apparatus comprising: an arm configured to be coupled to the source cage, the arm including an orientation component corresponding to the orientation feature of the source cage; a central rod coupled to the arms and configured to be coupled to a gamma ray detector configured to measure the radioactivity emitted by the plurality of radionuclides, the central rod configured to be positioned relative to the volume of the source cage when the arms are coupled to the source cage; the orientation feature of the source cage indicates a predetermined location of the source cage relative to the orientation component, the predetermined location of the source cage relative to the orientation component corresponding to a predetermined location of the source cage relative to the volume and the central rod; The apparatus further comprises a gamma ray detector coupled to the central rod, the gamma ray detector configured to measure the radioactivity emitted by the plurality of radionuclides.

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

17. 16. The apparatus of claim 15, further comprising a steering arm including a length configured to allow a technician to align the orienting component with respect to the orienting feature, the length precisely configured to position the technician a predetermined distance away from the plurality of radionuclides.

18. 16. The apparatus of claim 15, wherein the gamma ray detector comprises a spiral wound around a tube configured to be coupled to the central rod.

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