Patent Description:
The present disclosure is generally related to nuclear power generation and, more particularly, is directed to an improved device configured to measure radioactive isotope production in bulk.

<CIT> discloses a radioactivity measuring apparatus, comprising a storage support having means to hold a plurality of samples disposed in an arcuate array-about a centre, a radiation detector mounted at the centre of the arc on which the samples are disposed, and means for transferring the samples one at a time from the support to the detector for measurement and back, the background radiation received by the detector from stored samples remaining substantially constant. <CIT> discloses a radioactive sample processing apparatus comprising storage for delivering radioactive samples in a predetermined fixed order in sequence to an access point; a detector adapted to measure the disintegration rate of radioactive samples, disposed above and in horizontally displaced relationship with respect to the storage; transport means adapted to individually withdraw one of the samples from the fixed order and to transport it both vertically and horizontally from the access point to the detector and back to the fixed order at the access point prior to transporting the next sequential sample.

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

In various aspects, a device configured to measure radioactivity emitted by a plurality of radionuclides according to claim <NUM>, and a method of measuring radioactivity emitted by a plurality of radionuclides according to claim <NUM> is disclosed.

Various features of the aspects described herein are set forth with particularity in the appended claims. The various aspects, however, both as to organization and methods of operation, together with advantages thereof, may be understood in accordance with the following description taken in conjunction with the accompanying drawings as follows:.

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

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

In the following description, like reference characters designate like or corresponding parts throughout the several views of the drawings. Also in the following description, it is to be understood that such terms as "forward", "rearward", "left", "right", "upwardly", "downwardly", and the like are words of convenience and are not to be construed as limiting terms.

Before explaining 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 construction and arrangement of parts illustrated in the accompanying drawings and description. The illustrative examples may be implemented or incorporated in other aspects, variations, and modifications, and may be practiced or carried out in various ways. Further, unless otherwise indicated, the terms and expressions employed herein have been chosen for the purpose of describing the illustrative examples for the convenience of the reader and are not for the purpose of limitation thereof. Also, it will be appreciated that one or more of the following-described aspects, expressions of aspects, and/or examples, can be combined with any one or more of the other following-described aspects, expressions of aspects, and/or examples.

The present disclosure is directed to devices, systems, and methods to measure radioactive isotope production capsules in bulk. Radionuclides (e.g. Cobalt <NUM>, Molybdenum-<NUM>, Cesium-<NUM>, lodirie-<NUM><NUM>, Strontium-<NUM>, Technetium-<NUM>, Americium-<NUM>, and/or atomic variations of Plutonium, Uranium, Radium, Radon, Thorium, Tritium) possess a wide-variety of useful applications. For example, radionuclides can be used to improve the safety of medical devices, assist in the treatment of cancer, and reduce pathogens in foods and other products. However, radioactive isotopes emit harmful gamma rays that can be carcinogenic to humans depending on the degree of exposure. This can complicate the production, processing, and handling of radionuclides. In spite of these inherent risks, industry continues to produce and ship large quantities of radionuclides, expanding their many uses in an attempt to realize their full potential.

In order to ensure the safe shipment of large quantities of radionuclides, manufacturers must comply with a number of governmental regulations and contractual obligations regarding the amount of gamma rays emitted by each radionuclide capsule of a shipment, as well as the entire shipment of radionuclide capsules. Although the present disclosure discusses radionuclides configured as capsules, it shall be appreciated that the disclosed inventions can be implemented or easily modified-to measure the radioactivity emitted by radionuclides in any number of geometric configurations, not necessarily capsulated radionuclides. As such, the term "capsule" shall not be construed as a geometrical limitation of the radionuclides.

Traditionally, each radionuclide capsule was individually evaluated. However, this is time consuming and highly inefficient, especially for larger shipments, which can include hundreds-or even thousands-of radionuclide capsules. Thus, conventional 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 shelter or shield personnel from dangerous gamma rays. Accordingly, there is a need for devices, systems, and methods to efficiently measure radioactive isotope production capsules in bulk. Such devices, systems, and methods would save money and time, increase safety, and improve manufacturer compliance to governmental regulations and contractual obligations.

Referring now to <FIG>, a perspective view of a source cage <NUM> of a device configured to measure radioactivity emitted by a plurality of radionuclides <NUM> in bulk is depicted in accordance with at least one non-limiting aspect of the present disclosure. The source cage <NUM> of <FIG> is configured to safely store and ship a large shipment of radionuclides. For example, the source cage <NUM> of <FIG> can be used to ship <NUM> radionuclide capsules. However, it shall be appreciated that the capacity of the source cage <NUM> of <FIG> can be easily scaled or otherwise reconfigured to accommodate more or less radionuclides, in any desired form, as long as the storage geometry remains three-hundred-and-sixty-degree symmetric with respect to its centerline. As such, it would be advantageous to streamline the number of measurements required to generate an accurate amount of gamma rays emitted by a plurality of radionuclides <NUM> stored in the source cage <NUM> of <FIG>, because doing so would enable a technician of the source cage <NUM> to quickly verify compliance to governmental regulations and contractual obligations.

In further reference to <FIG>, the source cage <NUM> of <FIG> can include one or more outer rings <NUM> that define a volume <NUM>. According to the non-limiting aspect of <FIG>, the outer rings <NUM> are circular and thus, the volume <NUM> is cylindrical. However, the present disclosure contemplates other non-limiting aspects wherein the source cage <NUM> can include any number of geometric structures and volumes, as long as the geometric structures and volumes remain three-hundred-and-sixty-degree symmetric with respect to their centerlines. The outer rings <NUM> of the source cage <NUM> of <FIG> can further include a plurality of holes <NUM>, wherein each hole <NUM> of the plurality of holes <NUM> can be configured to receive a radionuclide <NUM> of the plurality of radionuclides <NUM>. However, the present disclosure contemplates other means of receiving and securing the radionuclides <NUM>. For example, the source cage <NUM> of <FIG> can additionally and/or alternatively include gripping components, cradles, and/or other structural elements to either assist or replace the plurality of holes <NUM> depicted in the non-limiting embodiment of <FIG>. These structural components most simply secure the radionuclides <NUM> at a predetermined position, i.e., centerline, of the source cage <NUM>.

Notably, the source cage <NUM> of <FIG> can include a three-hundred-and-sixty degree form, such that each radionuclide is equidistant from a center point of a circular plane defined by an upper surface of the outer ring <NUM>. For example, the source cage <NUM> of FIG. <NUM> can include an inner diameter D1. The plurality of holes <NUM> can be defined in the outer ring <NUM> such that, when installed, each radionuclide <NUM> of the plurality of radionuclides <NUM> is positioned the same distance away from the center point of the cylindrical volume <NUM>, or in other words, the center point of the inner diameter D1. However, the radionuclides <NUM> can be configured to be the same distance from any reference point on a source cage <NUM> of any other geometrical configuration. It shall be appreciated that the cylindrical source cage <NUM> of <FIG> is merely depicted for ease of illustration.

According to the non-limiting aspect of <FIG>, the radionuclides <NUM> can be structured as elongated rods. Accordingly, the source cage <NUM> can include three outer rings <NUM> supported by one or more standoff rods <NUM> configured to orient and support the outer rings <NUM> such that the plurality of holes <NUM> of a first outer ring <NUM> aligns with the plurality of holes <NUM> of a second outer ring <NUM>. Each of the plurality of holes <NUM> can include a circular bore configured to accommodate the circular cross-section of each of the radionuclides <NUM>. This allows for the rod-shaped radionuclides <NUM> to be properly inserted into the tioles <NUM> and supported within each outer ring <NUM> of the source cage <NUM> of <FIG>. However, the present disclosure contemplates other non-limiting aspects, wherein the radionuclides <NUM> include varying shapes and sizes. As previously discussed, the present disclosure contemplates other non-limiting aspects, wherein the source cage <NUM> can include components of varying shapes and configurations to effectively accommodate and secure any shape of radionuclide <NUM>. Once the radionuclides <NUM> are inserted into the holes <NUM>, the source cage <NUM> can be submerged in water for testing and/or processing.

In further reference to <FIG>, the source cage <NUM> further includes an orientation feature <NUM>, such as a notch, a slot, an opening, and/or the like. In the non-limiting aspect of <FIG>, the orientation feature <NUM> comprises an orientation notch configured to receive an orientation pin <NUM> (<FIG>) of a frame <NUM> (<FIG>) configured to be coupled to the source cage <NUM>. As will be discussed in further detail, the orientation notch <NUM> is specifically positioned such that a gamma detector <NUM> (<FIG>) coupled to the central rod <NUM> (<FIG>) of the frame <NUM> (<FIG>) is positioned in a predetermined location within the cylindrical volume <NUM>. Although the source cage <NUM> of <FIG> can include a single orientation notch <NUM>, the present disclosure contemplates other non-limiting aspects in which the source cage <NUM> can include several orientation notches <NUM>, or any combination of other geometric features <NUM>, which can allow a technician to position the gamma detector <NUM> (<FIG>) coupled to the central rod <NUM> (<FIG>) of the frame <NUM> (<FIG>) in a variety of predetermined positions within the cylindrical volume <NUM>. This can allow the technician to reorient and reposition the gamma detector <NUM> (<FIG>) to accommodate for margins of error, or enhance measurement accuracy. According to still other non-limiting aspects, the source cage can further include a pre-existing geometrical feature that the gamma detector <NUM> (<FIG>) can be configured to be positioned about. For example, in some non-limiting aspects, the source cage can further include a centerpiece that protrudes from the bottom of the source cage through the center of cylindrical volume <NUM>. According to an example useful for understanding, but not forming part of, the presently claimed invention, a gamma detector-such as a self-powered detector <NUM> (<FIG>)-can be strategically positioned about the centerpiece, as desired, instead of a gamma detector-such as an ion chamber detector <NUM> (<FIG>) -being suspended within the cylindrical volume <NUM> via a central rod <NUM> (<FIG>) of a frame <NUM> (<FIG>).

Referring now to <FIG>, a perspective view of a frame <NUM> of a device configured to measure radioactivity emitted by a plurality of radionuclides <NUM> (<FIG>) in bulk is depicted in accordance with at least one aspect of the present disclosure. According to the non-limiting aspect of <FIG>, the frame <NUM> can include a central rod <NUM>, as well as a first arm <NUM>, a second arm <NUM>, a third arm <NUM>, and a fourth arm <NUM>. The arms <NUM>, <NUM>, <NUM>, <NUM> can be specifically configured to couple to the outer ring <NUM> of the source cage <NUM>. For example, the first arm <NUM> and the fourth arm <NUM> can collectively define a frame diameter D2 that is larger than the inner diameter D1 (<FIG>) of the source cage <NUM> (<FIG>). Accordingly, the first arm <NUM> and fourth arm <NUM> can support the frame <NUM> such that the central rod <NUM> is suspended within the cylindrical volume <NUM> (<FIG>) of the source cage <NUM> (<FIG>). However, it shall be appreciated that the frame <NUM> can include any number of arms <NUM>, <NUM>, <NUM>, <NUM> in varying configurations to achieve the same result. For example, according to another non-limiting aspect of the present disclosure, the frame <NUM> can include a single arm <NUM> configured to be clamped to the outer ring <NUM> (<FIG>) and suspend the central rod <NUM> within the cylindrical volume <NUM> (<FIG>) of the source cage <NUM> (<FIG>).

Still referring to <FIG> and in accordance with some non-limiting aspects of the present disclosure, the arms <NUM>, <NUM>, <NUM>, <NUM> of the frame <NUM> can be configured to move relative to the outer ring <NUM> (<FIG>) of the source cage <NUM> (<FIG>) once they are installed. For example, the arms <NUM>, <NUM>, <NUM>, <NUM> can include additional structural components such as hinges, rollers, tracks, and/or the like which can be used to angle the arms <NUM>, <NUM>, <NUM>, <NUM> relative to a plane defined by a top surface of the outer ring <NUM>. Accordingly, the frame <NUM> and, more specifically, the arms <NUM>, <NUM>, <NUM>, <NUM>, can be articulated and thus, capable of moving the central rod <NUM> between a number of predetermined locations within the cylindrical volume <NUM> (<FIG>).

In further reference to <FIG>, the central rod <NUM> of the frame <NUM> can be configured to suspend a gamma detector <NUM> within the cylindrical volume <NUM> (<FIG>) of the source cage <NUM> (<FIG>), wherein the gamma detector <NUM> will be exposed to gamma rays emitted by the plurality of radionuclides <NUM> (<FIG>). According to the non-limiting aspect of <FIG>, the gamma detector <NUM> can be integral to-and positioned at an end of— the central rod <NUM>. The central rod <NUM> can be further configured to include and/or house a signal cable <NUM>, such that signals can be routed from the gamma detector <NUM> to a remotely located data acquisition unit. This can allow a technician to safely monitor a measure of detected gamma rays that are emitted by at least one of the plurality of radionuclides <NUM> (<FIG>). It shall be appreciated that, although the non-limiting aspect of <FIG> includes a signal cable <NUM> to rout signals from the gamma detector <NUM> to a remotely located data acquisition unit, other non-limiting aspects include gamma detectors <NUM> that can be configured for wireless communication.

According to other aspects of the present disclosure the central rod <NUM> of <FIG> can be further configured to be coupled to an external gamma detector <NUM>. For example, the gamma detector <NUM> can include a farmer ion chamber installed on a sleeve configured to be installed over and around an end of the central rod <NUM>. The sleeve can include a housing specifically configured to position the gamma detector <NUM> at a desired orientation relative to the central rod <NUM>, such as the center line. According to still other non-limiting embodiments of the present disclosure, the gamma detector <NUM> can further include a self-powered detector (e.g. platinum). The self-powered detector can be configured to be wound around an end of the central rod <NUM>, forming a tight, spiral configuration, as depicted in <FIG>.

Although <FIG> depicts a gamma detector <NUM> coupled to the end of the central rod <NUM>, it shall be appreciated that any number of detectors can be coupled to the central rod <NUM> depending on user preference and/or intended application of the frame <NUM>. For example, the central rod <NUM> is configured such that a technician can couple any number or spectroscopes or non-invasive test equipment to it in a similar manner to the gamma detector <NUM>. Accordingly, a technician can utilize the frame <NUM> of <FIG> to perform any number of tests on a bulk shipment of radionuclides, thereby ensuring compliance with any number of governmental regulations and/or contractual obligations. Alternatively and/or additionally, it shall be appreciated that, in still other non-limiting aspects, the central rod <NUM> can be simultaneously configured to accommodate any number of gamma detectors <NUM>, spectroscopes, and/or non-invasive test equipment. This can provide the frame <NUM> with a degree of modularity and flexibility of use, enabling a technician to perform any number of tests on a bulk shipment of radionuclides using the same frame <NUM> by simple swapping out the gamma detector for another spectroscope and/or piece of test equipment.

Referring now to <FIG>, a sectioned view of a gamma detector <NUM> configured to be coupled to the frame of <FIG> is depicted in accordance with at least one non-limiting aspect of the present disclosure. According to the non-limiting aspect of <FIG>, the gamma detector <NUM> can include a self-powered detector <NUM> positioned around an inner tube <NUM> and an outer tube <NUM> positioned. The central rod <NUM> (<FIG>) can constitute the inner tube <NUM>. However, in still other non-limiting aspects of the present disclosure, the gamma detector <NUM> can include a separate tube, which serves as a sleeve configured to be coupled to the central rod <NUM> (<FIG>). The outer tube <NUM>, self-powered detector <NUM>, and the inner tube <NUM> can be specifically configured to ensure that the self-powered detector <NUM> does not move relative to the central rode <NUM> (<FIG>), as the orientation of the self-powered detector <NUM> relative to the plurality of radionuclides <NUM> (<FIG>) can affect the measurement.

In further reference to <FIG>, the self-powered detector <NUM> can be used to measure an amount of gamma rays emitted by the plurality of radionuclides <NUM> (<FIG>). The self-powered detector <NUM> can measure an amount of gamma rays because an electrical current is induced throughout the spiral configuration when the self-powered detector <NUM> is in the proximity of a radionuclide. The electrical current induced within the self-powered detector <NUM> can be measured in a number of different ways. For example, the sensitivity of the self-powered detector <NUM> can be calculated via testing, and will vary depending on the amount of electrical current generated given the length of the self-powered detector <NUM> based on a known quantity of gamma ray exposure. As long as the self- powered detector <NUM> is properly positioned within the cylindrical volume <NUM> (<FIG>) of the source cage <NUM> (<FIG>), the calculated sensitivity can be used to measure the collective gamma rays emitted by the plurality of radionuclides <NUM> (<FIG>). Although the self-powered detector <NUM> of <FIG> is configured to measure gamma rays, according to other aspects of the present disclosure, the self-powered detector <NUM> can be configured to measure other types of radiation. Additionally, although the gamma detector <NUM> of <FIG> can include a self-powered detector <NUM> configured to measure gamma rays, in still other non-limiting aspects contemplate the gamma detector <NUM> can include any number of radiation detectors (e.g. a farmer ion chamber and/or the like).

Referring now to <FIG>, a perspective view of a device <NUM> configured to measure radioactivity emitted by a plurality of radionuclides <NUM> in bulk is depicted in accordance with at least one non-limiting aspect of the present disclosure. According to the non-limiting aspect of <FIG>, the device <NUM> can include a source cage <NUM> and a frame <NUM> similar to the source cage <NUM> and frame <NUM> depicted in <FIG> and <FIG>, respectively. Generally, <FIG> illustrates how previously disclosed elements can be integrated into a device <NUM> configured to measure radioactivity emitted by a plurality of radionuclides <NUM> in bulk. For example, a technician might use the device <NUM> of <FIG> to store and ship a large number of radionuclides <NUM>-a contractual deliverable-to a receiving customer. Alternatively and/or additionally, a technician might use the device <NUM> of <FIG> to store and ship a large number of radionuclides <NUM> internally. Regardless, the device <NUM> of <FIG> can be used to efficiently ensure that a shipment of radionuclides <NUM>-and more specifically, the radioactivity emitted by the radionuclides <NUM>-complies with governmental regulations and/or contractual obligations.

As previously discussed, the orientation and/or the position of a gamma detector <NUM> relative to the plurality of radionuclides <NUM> can affect the integrity of a measurement. Accordingly, the gamma detector <NUM> can be optimally positioned within the cylindrical volume defined by the outer ring <NUM> and therefore, can receive the desired exposure to radioactivity emitted by the plurality of radionuclides <NUM>. As can be seen in the non-limiting aspect of <FIG>, the arms <NUM> of the frame <NUM> are configured to rest on the outer ring <NUM> of the source cage <NUM>. As such, the central rod <NUM> can suspend a gamma detector <NUM> within the cylindrical volume defined by the outer ring <NUM>. It shall be appreciated that the position of the gamma detector <NUM> within the cylindrical volume defined by the outer ring <NUM> can be adjusted by modifying a length of the central rod <NUM>. As such, the present disclosure contemplates non-limiting aspects wherein the central rod <NUM> can be telescopically configured.

Alternatively and/or additionally, an orientation notch <NUM> of the source cage <NUM> can be configured to receive and secure an orientation pin <NUM> of the frame <NUM>. According to the non-limiting aspect of <FIG>, the gamma detector <NUM> can be positioned in a predetermined location relative to the cylindrical volume defined by the outer ring <NUM> when the orientation pin <NUM> of the frame <NUM> is received by the orientation notch <NUM> of the source cage <NUM>. As such, a technician does not need to waste time arranging the frame <NUM> and the source cage <NUM> to properly position the gamma detector <NUM> within the cylindrical volume. Instead, the technician can align the orientation pin <NUM> with the orientation notch <NUM>. As an added bonus, the frame <NUM> can be secured relative to the source cage <NUM> when the orientation pin <NUM> is received by the orientation notch <NUM>, thereby ensuring the desired configuration will not be perturbed. Although the non-limiting aspect of <FIG> can include an orientation pin <NUM> and an orientation notch <NUM>, other non-limiting aspects of the present disclosure include any number of mechanical components and/or features configured to properly orient and secure the frame <NUM> to the source cage <NUM>. For example, a variety of mating geometries, interacting components, visual markings, and/or combinations thereof can be implemented, depending on the intended application and/or specific technician preference.

According to still other non-limiting aspects of the present disclosure, the source cage <NUM> of <FIG> can include more than one orientation notch <NUM>, wherein each orientation notch <NUM>, when engaged with the orientation pin <NUM> of the frame <NUM>, will orient the gamma detector <NUM> in a particular predetermined position of a plurality of predetermined positions within the volume defined by the outer ring <NUM>. This can provide a technician with the flexibility to adjust the position of the gamma detector <NUM> as desired, while retaining the aforementioned ease-of-use and efficiencies.

Still referring to <FIG>, the device <NUM> can be calibrated and/or reconfigured to optimize the integrity of a measurement, as desired. For example, a technician can utilize the frame <NUM> and source cage <NUM> of the device to initially orient the gamma detector <NUM> within the internal volume defined by the outer ring <NUM>. Once the gamma detector <NUM> is initially positioned, the technician can install a single radionuclide <NUM> of a plurality of radionuclides <NUM> into the source cage <NUM> and take a baseline measurement of the radioactivity emitted by the single radionuclide <NUM>. The technician may proceed to install each radionuclide <NUM> of the plurality of radionuclides <NUM> into the source cage <NUM> and take a collective measurement of radioactivity emitted by the plurality of radionuclides <NUM>. The technician can 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 the single radionuclide <NUM> was one Curie, the technician might expect that the collective measurement would be <NUM> Curies. However, if the collective measurement significantly diverges from the what would be expected based on the baseline measurement, the technician might determine a correction factor, which can account for an acceptable margin of error. Accordingly, the technician might decide to reposition the gamma detector <NUM> within the cylindrical volume based, at least in part, on the determined correction factor. The aforementioned structural features of the device <NUM> of <FIG> can assist the technician in easily making these adjustments and therefore, facilitate a more efficient acquisition of accurate data associated with the anticipated shipment.

In other words, the device <NUM> can be capable of enhancing the efficiency of radioactivity measurements due to its symmetrical geometry. For example, in the non-limiting aspect of <FIG>, the source cage <NUM> includes a three-hundred and sixty degree geometry that is symmetric relative to a radial centerline of the plane defined by the outer ring <NUM>. As described above, when the source cage <NUM> is loaded with a number ("X") of radionuclides <NUM>, the device <NUM> can achieve a detection efficiency, which can be defined as the calibrated efficiency ("E") multiplied by the number of installed radionuclides, or X*E.

In further reference to <FIG>, a number of standoff rods <NUM> can support the outer rings <NUM> of the source cage <NUM>. However, the standoff rods <NUM> can interfere with the radiation exposure of the gamma detector <NUM>, thereby imposing a larger calibration error than desired. If such standoff rods <NUM>, or any other structural feature of the device <NUM> generate an unacceptable calibration error, multiple approaches can be taken to account for the error and efficiently calibrate the device <NUM>. For example, an accurate calibration efficiency that accounts for the standoffs <NUM> can be determined either experimentally, or via simulation. Alternatively and/or additionally, the source cage <NUM> can be modified to include a larger number of standoffs <NUM>, wherein each standoff <NUM> includes a smaller diameter. Still, in other non-limiting aspects, the source cage <NUM> can be modified to include a circumferential support plate which provides structural stability independent of the standoff rods <NUM> without interfering with the radiation exposure of the gamma detector <NUM>.

As previously discussed, radionuclides must be carefully controlled at all times to avoid worker overexposure to radiation. Such caution can introduce constraints on the handling of radionuclides, which can only increase inefficiencies and complicate bulk measurements and shipments. Accordingly, the device <NUM> of <FIG> can be further configured to be submerged in water, which can shield personnel from hazardous exposure. For example, the device <NUM> of <FIG> can be utilized for both underwater and/or wet-source-storage models. As such, the device <NUM> an include a manipulating arm <NUM> including a predetermined length that can allow a technician to engage the orientation pin and the orientation notch from afar (e.g. above the surface of the water). It shall be appreciated that the length can further be configured to position the technician a predetermined distance away from the plurality of radionuclides. Alternatively and/or additionally, the frame <NUM> and specifically, the arms <NUM> of the frame <NUM> can be robotically configured for autonomous repositioning relative to the source cage <NUM>. According to some non-limiting aspects, the frame <NUM> can further include a position sensor, which can provide real-time feedback regarding the position of gamma detector <NUM> relative to the radionuclides <NUM>.

Additionally, the gamma detector <NUM> of <FIG> can be coupled to a signal cable <NUM> that can be either integral to or routed to the surface via the central rod <NUM>. For example, the signal cable <NUM> can communicate signals from the gamma detector <NUM> to a data acquisition unit located above the water and a safe distance away from the radionuclides <NUM>. It shall be appreciated that, although the non-limiting aspect of <FIG> includes a signal cable <NUM> to rout signals from the gamma detector <NUM> to a remotely located data acquisition unit, other non-limiting aspects include gamma detectors <NUM> that can be configured for wireless communication.

Referring now to <FIG>, a perspective view of another device <NUM> configured to measure radioactivity emitted by a plurality of radionuclides in bulk is depicted in accordance with at least one non-limiting aspect of the present disclosure. According to the non-limiting aspect of <FIG>, the device <NUM> can be configured substantially similar to the device <NUM> of <FIG>. However, the device <NUM> of <FIG> can further include one or more arms <NUM> movably configured relative to the source cage <NUM>. Accordingly, the frame <NUM> can be repositioned relative to the source cage <NUM>. It shall be appreciated that the arms <NUM> can include any number of structural components and/or features that can facilitate this functionality. For example, the device <NUM> of <FIG> can include arms <NUM> configured with locking hinges, which can be manipulated from a safe distance. Alternatively and/or additionally, the arms <NUM> can include sliding tracks and/or rollers to accomplish the same effect. A manipulating arm <NUM> can be used to manipulate the arms <NUM> from above the water and at a safe distance. Alternatively and/or additionally, the frame <NUM> and specifically, the arms <NUM> of the frame <NUM> can be robotically configured for autonomous repositioning relative to the source cage <NUM>. According to some non-limiting aspects, the frame <NUM> can further include a position sensor, which can provide real-time feedback regarding the position of gamma detector <NUM> relative to the radionuclides <NUM>.

In further reference to <FIG>, the arms <NUM> can be manipulated to adjust the frame <NUM>-and specifically, the central rod <NUM>-relative to the source cage <NUM>. This can subsequently reposition the gamma detector <NUM> relative to the cylindrical volume defined by the outer ring <NUM> and therefore, the orientation and/or the position of the gamma detector <NUM> relative to the plurality of radionuclides <NUM>. For example, according to the non-limiting aspect of <FIG>, the gamma detector <NUM> can be positioned outside of the cylindrical volume defined by the outer ring <NUM>, such that the gamma detector <NUM> is suspended above the outer ring <NUM> of the source cage <NUM>. This can be particularly useful for source cages <NUM> that include geometrical features within the cylindrical volume, such as a centerpiece where the central rod would otherwise be positioned. However, it shall be appreciated that the present disclosure contemplates other non-limiting aspects wherein the gamma detector <NUM> can be positioned within the cylindrical volume. In some non-limiting aspects, the central rod <NUM> can be telescoping or otherwise adjustable to accommodate source cages <NUM> of varying designs and configurations and thus, allow for flexibility regarding the gamma detector <NUM> position. As such, the arms <NUM> of the frame <NUM> depicted in <FIG> can be manipulated to affect the integrity of a measurement. Such features enhance the customization of the device <NUM> configuration and thus, provide more versatility for implementing technicians. In other words, the arms <NUM> can be used instead of-or in conjunction with-an orientation pin and orientation slot opening to optimize efficiency and improve compliance of bulk radionuclide shipments.

Referring now to <FIG>, a flow diagram of a method <NUM> of measuring radioactivity emitted by a plurality of radionuclides using the devices depicted in <FIG> and <FIG> is depicted in accordance with at least one non-limiting aspect of the present disclosure. First, a technician can couple the one or more arms of the frame to the source cage <NUM>. As previously discussed, this can include simply securing a fixed frame on the outer ring of the source cage, or attaching an articulated frame via movable components (e.g. hinges). The technician can then arrange the arm and specifically, the central rod, until the gamma detector is in a predetermined location relative to a cylindrical volume defined by an outer ring of the source cage <NUM>. This can include the use of a manipulating arm, as depicted in <FIG> and <FIG>. Once the frame is properly aligned relative to the source cage, the technician can engage the orientation pin of the frame and the orientation notch of the source cage <NUM>. Of course, the device can include alternate components for initial alignment and coupling, as disclosed above. This will ensure that the gamma detector is properly positioned and secure for testing.

In further reference of <FIG>, once the gamma detector s initially positioned, the technician can install a single radionuclide of a plurality of radionuclides into the source cage. Once installed, the technician can take a baseline measurement of the radioactivity emitted by the single radionuclide <NUM> and. can proceed to install each radionuclide to be shipped into the source cage <NUM>. The technician can then take a collective measurement of radioactivity emitted by the entire shipment of radionuclides <NUM>. The technician can 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 the single radionuclide was one Curie, the technician might expect that the collective measurement would be <NUM> Curies. However, if the collective measurement significantly diverges from the what would be expected based on the baseline measurement, the technician might determine a correction factor, which can account for an acceptable margin of error. Accordingly, the technician might decide to reposition the gamma detector within the cylindrical volume based, at least in part, on the determined correction factor. Without following the aforementioned steps of method <NUM>, the technician would be forced to measure each radionuclide on a one-by-one basis, which is as costly as it is time-consuming. However, by following the aforementioned steps of the method <NUM>, the technician can easily measure and adjustment the method of measurement and therefore, can efficiently acquire accurate data associated with the anticipated shipment.

Referring now to <FIG>, a perspective view of another source cage <NUM> of a device configured to measure radioactivity emitted by a plurality of radionuclides in bulk is depicted in accordance with at least one non-limiting aspect of the present disclosure. The source cage <NUM> of <FIG> is similarly configured to the source cage <NUM> of <FIG>. However, according to the non-limiting aspect of <FIG>, the source cage <NUM> can further include a geometrical feature <NUM> positioned within the volume <NUM> defined by the outer rings <NUM> of the source cage <NUM>. For example, the source cage <NUM> of <FIG> includes a base plate <NUM> coupled to the standoff rods <NUM> of the source cage <NUM>, and the geometrical feature <NUM> includes a centerpiece extending up from the base plate <NUM> into the volume <NUM>, where the central rod <NUM> (<FIG>) of the frame <NUM> (<NUM>) could otherwise be positioned. Accordingly, a gamma detector-such as an ion chamber detector <NUM> (<FIG>)-can be suspended above the cylindrical volume <NUM> via a central rod <NUM> (<FIG>) of a frame <NUM> (<FIG>). Alternatively and/or additionally a gamma detector-such as a self-powered detector <NUM> (<FIG>)-can be strategically positioned about the centerpiece <NUM>, in accordance with the intended application and/or user preference.

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

Those skilled in the art will recognize that, in general, terms used herein, and especially in the appended claims (e.g., bodies of the appended claims) are generally intended as "open" terms (e.g., the term "including" should be interpreted as "including but not limited to," the term "having" should be interpreted as "having at least," the term "includes" should be interpreted as "includes but is not limited to," etc.). It will be further understood by those within the art that if a specific number of an introduced claim recitation is intended, such an intent will be explicitly recited in the claim, and in the absence of such recitation no such intent is present. However, the use of such phrases should not be construed to imply that the introduction of a claim recitation by the indefinite articles "a" or "an" limits any particular claim containing such introduced claim recitation to claims containing only one such recitation, even when the same claim includes the introductory phrases "one or more" or "at least one" and indefinite articles such as "a" or "an" (e.g., "a" and/or "an" should typically be interpreted to mean "at least one" or "one or more"); the same holds true for the use of definite articles used to introduce claim recitations.

In addition, even if a specific number of an introduced claim recitation is explicitly recited, those skilled in the art will recognize that such recitation should typically be interpreted to mean at least the recited number (e.g., the bare recitation of "two recitations," without other modifiers, typically means at least two recitations, or two or more recitations). Furthermore, in those instances where a convention analogous to "at least one of A, B, and C, etc." is used, in general such a construction is intended in the sense one having skill 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 that have 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 instances where a convention analogous to "at least one of A, B, or C, etc." is used, in general such a construction is intended in the sense one having skill in the art would understand the convention (e.g., "a system having at least one of A, B, or C" would include but not be limited to systems that have 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 within the art that typically a disjunctive word and/or phrase presenting two or more alternative terms, whether in the description, claims, or drawings, should be understood to contemplate the possibilities of including one of the terms, either of the terms, or both terms unless context dictates otherwise. For example, the phrase "A or B" will be typically understood to include the possibilities of "A" or "B" or "A and B.

With respect to the appended claims, those skilled in the art will appreciate that recited operations therein may generally be performed in any order. Also, although claim recitations are presented in a sequence(s), it should be understood that the various operations may be performed in other orders than those which are described, or may be performed concurrently. Examples of such alternate orderings may include overlapping, interleaved, interrupted, reordered, incremental, preparatory, supplemental, simultaneous, reverse, or other variant orderings, unless context dictates otherwise. Furthermore, terms like "responsive to," "related to," or other past-tense adjectives are generally not intended to exclude such variants, unless context dictates otherwise.

It is worthy to note that any reference to "one aspect," "an aspect," "an exemplification," "one exemplification," and the like means that a particular feature, structure, or characteristic described in connection with the aspect is included in at least one aspect. Thus, appearances of the phrases "in one aspect," "in an aspect," "in an exemplification," and "in one exemplification" in various places throughout the specification are not necessarily all referring to the same aspect. Furthermore, the particular features, structures or characteristics may be combined in any suitable manner in one or more aspects.

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

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

The terms "about" or "approximately" as used in the present disclosure, unless otherwise specified, means an acceptable error for a particular value as determined by one of ordinary skill in the art, which depends in part on how the value is measured or determined. In certain aspects, the term "about" or "approximately" means within <NUM>, <NUM>, <NUM>, or <NUM> standard deviations. In certain aspects, the term "about" or "approximately" means within <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, <NUM>%, or <NUM>% of a given value or range.

In this specification, unless otherwise indicated, all numerical parameters are to be understood as being prefaced and modified in all instances by the term "about," in which the numerical parameters possess the inherent variability characteristic of the underlying measurement techniques used to determine the numerical value of the parameter. At the very least, each numerical parameter described herein should at least be construed in light of the number of reported significant digits and by applying ordinary rounding techniques.

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

Claim 1:
A method of measuring radioactivity emitted by a plurality of radionuclides using a source cage (<NUM>; <NUM>) comprising an outer ring (<NUM>; <NUM>) that defines a volume (<NUM>) and a plurality of holes (<NUM>), wherein each hole of the plurality of holes (<NUM>) is configured to receive a radionuclide of the plurality of radionuclides (<NUM>), and a frame (<NUM>; <NUM>) comprising an arm (<NUM>) coupled to a central rod (<NUM>; <NUM>), wherein the central rod (<NUM>; <NUM>) is coupled to a gamma detector (<NUM>; <NUM>), wherein the outer ring (<NUM>; <NUM>) comprises an orientation feature (<NUM>; <NUM>), wherein the arm (<NUM>) comprises an orientation pin (<NUM>) configured to engage the orientation feature (<NUM>; <NUM>), and wherein the central rod (<NUM>; <NUM>) is configured to be positioned in a predetermined location relative to the volume (<NUM>) when the orientation pin (<NUM>) and the orientation feature (<NUM>; <NUM>) are engaged, the method comprising:
coupling (<NUM>) the arm (<NUM>) to the outer ring (<NUM>; <NUM>) of the source cage (<NUM>; <NUM>);
arranging (<NUM>) the arm (<NUM>) and the central rod (<NUM>; <NUM>) until the central rod is be positioned in the predetermined location relative to the volume (<NUM>);
engaging (<NUM>) the orientation pin (<NUM>) of the arm (<NUM>) and the orientation feature (<NUM>; <NUM>) of the outer ring (<NUM>; <NUM>) of the source cage (<NUM>; <NUM>);
inserting (<NUM>) a radionuclide of the plurality of radionuclides (<NUM>) into a hole of the plurality of holes (<NUM>) of the outer ring (<NUM>; <NUM>) of the source cage (<NUM>; <NUM>);
taking a baseline measurement (<NUM>) of radioactivity emitted by the inserted radionuclide using the gamma detector (<NUM>; <NUM>);
removing the radionuclide of the plurality of radionuclides (<NUM>) from the hole of the plurality of holes (<NUM>) of the outer ring (<NUM>; <NUM>) of the source cage (<NUM>; <NUM>); and
inserting (<NUM>) each radionuclide of the plurality of radionuclides into the plurality of holes (<NUM>) of the outer ring (<NUM>; <NUM>) of the source cage (<NUM>; <NUM>);
characterized by
taking (<NUM>) a collective measurement of radioactivity emitted by the plurality of radionuclides (<NUM>); and
dividing the collective measurement by the number of radionuclides of the plurality of radionuclides (<NUM>) to determine an average measurement of radioactivity emitted by each radionuclide of the plurality of radionuclides (<NUM>).