NL2027532B1 - Dose calibrator comprising nuclide selector and method for nuclide selection in dose calibrator - Google Patents
Dose calibrator comprising nuclide selector and method for nuclide selection in dose calibrator Download PDFInfo
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- NL2027532B1 NL2027532B1 NL2027532A NL2027532A NL2027532B1 NL 2027532 B1 NL2027532 B1 NL 2027532B1 NL 2027532 A NL2027532 A NL 2027532A NL 2027532 A NL2027532 A NL 2027532A NL 2027532 B1 NL2027532 B1 NL 2027532B1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
- G01T1/365—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry with ionisation detectors, e.g. proportional counter
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
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- A—HUMAN NECESSITIES
- A61—MEDICAL OR VETERINARY SCIENCE; HYGIENE
- A61N—ELECTROTHERAPY; MAGNETOTHERAPY; RADIATION THERAPY; ULTRASOUND THERAPY
- A61N5/00—Radiation therapy
- A61N5/10—X-ray therapy; Gamma-ray therapy; Particle-irradiation therapy
- A61N5/1048—Monitoring, verifying, controlling systems and methods
- A61N5/1075—Monitoring, verifying, controlling systems and methods for testing, calibrating, or quality assurance of the radiation treatment apparatus
Abstract
The invention relates to a dose calibrator comprising an ionisation chamber for holding a dose including one type of radionuclide, a dose calibrator control unit for, based on ionisation chamber measurements and the type of radionuclide, calculating a dose size of the dose in the ionisation chamber, and a user interface connected to the ionisation chamber and configured to provide a user with information on the calculated dose size. The dose calibrator further comprises a radionuclide selector comprising a spectrum analyser connected to the ionisation chamber for measuring an energy spectrum of the radionuclide in the ionisation chamber, and a read—out unit connected to the spectrum analyser for matching the measured energy spectrum to the energy spectra of a list of stored radionuclides and select the matching radionuclide for output to the user interface. The invention also comprises a method for measuring a dose in a dose calibrator.
Description
SELECTION IN DOSE CALIBRATOR The invention relates to a dose calibrator comprising nuclide selector, a method for nuclide selection in dose calibrator, a computer-implemented method and computer-readable storage media for implementing the method.
Dose calibrators are known in practice for measuring a dose of a radio nuclide, for example to measure patient doses of radio-active medicine to be administered to a patient. To that end, the known dose calibrators comprise an ionisation chamber in which a dose is insertable. The ionisation chamber comprises a double walled chamber with an ionisation gas being enclosed between the inner and outer wall. In use, a dose is inserted into the ionisation chamber. Due to the radiation emitted by the radio nuclide the ionisiation gas becomes ionized and an electrical current is elicited. This electrical current can be measured by the dose calibrator and subsequently be calculated to display the dose size of the radio nuclide present in the ionisation chamber.
It is however known that the calculated dose size strongly depends on the type of radio nuclide present in the ionisation chamber. In other words, the calculated dose size depends on the type of radio nuclide present in the ionisation chamber and if the wrong nuclide is used in the calculation, the measurement will not give the proper reading.
Therefore, the dose calibrator is often provided with a user interface at which an operator can (manually) select a type of nuclide inserted in the dose calibrator to obtain a correct reading. It has been found that, especially in environments in which multiple types of nuclides are being used (and therefore measured) to prepare patient doses, errors are made in the selection. Such an incorrect selection of the radio isotope can lead to a wrongly calculated dose, which in turn can lead to a false diagnose or to a therapy treatment that is not working or has a serious negative influence on the welfare of the patient.
It is an object of the invention to obviate or at least strongly reduce the abovementioned disadvantage.
To that end, the invention provides a dose calibrator comprising: — an ionisation chamber that is configured to hold a dose including one type of radionuclide; — a dose calibrator control unit that is configured to, based on ionisation chamber measurements and the type of radionuclide, calculate a dose size of the dose of the type of radionuclide in the ionisation chamber; — a user interface that is operatively connected to the ionisation chamber and that is configured to provide a user with information on the calculated dose size; and — a radionuclide selector comprising:
— a spectrum analyser that is operatively connected to the ionisation chamber, wherein the spectrum analyser is configured to measure an energy spectrum of the type of radionuclide in the ionisation chamber; — aread-out unit that is operatively connected to the spectrum analyser and that is configured to: ~ match the measured energy spectrum to the energy spectra of a list of stored radionuclides; ~ select the matching radionuclide for output to the user interface.
An advantage of the dose calibrator according to the invention is that it automatically determines which radio nuclide is present in the dose calibrator. As a result, an error in the determination of the radio nuclide is substantially prevented. This is achieved by the fact that a radio nuclide emits a certain type of radiation with a specific energy signature. A measurement of the energy spectrum of the inserted radio nuclide with a spectrum analyser provides an accurate measurement of the type of radio nuclide.
Another advantage of the dose calibrator according to the invention is that the radionuclide selector, by virtue of the read-out unit, is activated at the moment a (new) radionuclide is entered into the ionisation chamber of the dose calibrator. This means that any change in radio nuclide is (automatically) detected by change in energy spectrum measured by the nuclide selector and communicated to the operator. This is especially useful in environments in which multiple types of nuclides are being used to prepare patient doses. As such, the nuclide selector forms an automated nuclide selector.
Yet another advantage is that the number of prepared doses can be increased by a reduction in work load of each operator. This is due to the fact that in many places in the Netherlands, including hospitals, patient doses are prepared (and measured) by two trained operators. One operator provides the initial setup of the dose calibrator, including the nuclide selection, and the other operator is only present to check the nuclide selection made by the operator. This check can be obviated by using the dose calibrator according to the invention, because the initial setup is made by the dose calibrator, whereas the check can than be performed by the (single) operator. This reduces workload for the operators, since only asingle operator is needed to prepare each dose. Additionally or alternatively, it also allows the number of doses prepared to be doubled by using two dose calibrators according to the invention for each of the two operators.
Another advantage is that, due to the fact that only a single operator is required to prepare a dose, a radiation dose for each operator is reduced.
It is preferred that a comprehensive list and/or database of radio nuclides and the associated energy spectra is compiled, which is stored in a memory of the dose calibrator (and specifically the nuclide selector thereof). This database and/or list preferably contains at least the most used radio nuclides for the environment in which the dose calibrator is to be used.
It is noted that the list (which may be a database or be stored in a database) may also be provided with combinations of radio nuclides and their associated energy spectra. This is for example useful in situations and/or places in which doses containing multiple radionuclides need to be measured.
Yet another advantage of the dose calibrator according to the invention is that it, alternatively, may also be used to detect and measure doses and/or presence of unknown nuclides in a sample. This provides an effective and easy way to detect whether a radionuclide is present in a sample, and, if so, what the dose of that particular radionuclide in the sample is.
In an embodiment according to the invention, the list of nuclides is preferably stored in a memory, wherein the memory preferably is part of the nuclide selector.
An advantage of providing a memory, which may be a fixed, integrated or removable memory, is that the list of radio nuclides can be regularly updated and/or can be adapted to different locations of use.
In an embodiment according to the invention, the radionuclide selector comprises a radionuclide selector control unit that is operatively connected to the spectrum analyser, read-out unit and/or the user interface, wherein the radionuclide selector unit is configured to send the selected matching radionuclide to the user interface.
An advantage of providing a (radionuclide selector) control unit to the radionuclide selector is that it conveniently integrates and controls the spectrum analyser, read-out unit and/or the user interface.
In an embodiment according to the invention, the read-out unit is further configured to, when matching the measured energy spectrum to an energy spectrum of a list of stored radionuclides and select the matching radionuclide for output, compare the measured energy spectrum to the energy spectra of a list of stored radionuclides, and if a match is found select the associated radionuclide, and output the selected radionuclide to the user interface. The read-out unit is further configured to, if no complete match is found, provide a selection of closely matching radionuclides as output to the user interface. The read- out unit is further configured to, if no match is found, provide a selection failure message and the list of available radionuclides for selection as output to the user interface.
An advantage of this embodiment is that, even if the radionuclide can not or not exactly be determined, an operator is prompted to review the nuclide selection of the dose calibrator. In case, that the radio nuclide can not exactly be determined, the operator is provided with a (small) selection of radionuclides from the list that resemble (i.e. match as close as possible) the measured energy spectrum/spectra. By actively providing the list, the operator is forced to make a selection, thus contributing to the selection of the correct nuclide to be measured.
Even in case no match can be determined between the radio nuclides on the list and the nuclide present in the dose calibrator, the dose calibrator according to the invention significantly reduces the risk of a wrong nuclide selection in the dose calibrator. This is due to the fact that the dose calibrator indicates to the operator that no selection could be made and that a selection should be made by the operator. Therewith, the risk of using a previous selection, as is possible in the dose calibrators known from the art, is obviated.
In an embodiment according to the invention, the read-out unit may be integral part of the control unit An advantage of integrating the control unit and the read-out unit is that a more compact and efficient dose calibrator is obtained.
In an embodiment according to the invention, the control unit is further configured to provide to the user interface a confirmation message to prompt the user to confirm or reject the selected nuclide, and wherein the control unit is optionally configured to prompt the user to select a nuclide from the list of nuclides if the selected nuclide is rejected by the user.
An advantage of providing a confirmation message to the user is that it forces the operator to either confirm or reject the selection made by the nuclide selector. This reduces the risk of an incorrect radionuclide being selected and provides an additional check.
Another advantage is that, when only a partial match or no match can be provided by the nuclide selector, the operator is prompted to make a selection which actively prompts the operator to take action to select the correct radionuclide. Upon rejection, the dose calibrator may additionally actively prompt the operator to select the correct radionuclide from a list of radionuclides that is provided to the user.
In an embodiment according to the invention, the radionuclide selector further comprises a computer program that is configured to correct the energy spectrum that is measured by the spectrum analyser to correct alterations and/or anomalies caused by the ionisation chamber.
It has been found that, depending on the dose calibrator and/or the specific position of the spectrum analyser with respect to the ionisation chamber of the dose calibrator, some distortion of the radioactive spectrum of the radionuclide in the ionisation chamber may be present. This is mainly due to the characteristics of the ionisation chamber (and/or the position of the spectrum analyser with respect to the ionisation chamber). Therefore, the radionuclide selector may comprise a computer program that, when executed, for example by a processer, is configured to correct distortions and/or anomalies in the measurement by the spectrum analyser. An advantage of this embodiment is that an even more accurate detection (and subsequent selection) can be performed by the nuclide selector.
In an embodiment according to the invention, the computer program comprises a correction algorithm and a machine learning component, wherein the computer program is configured to, using the machine learning component, calibrate the correction algorithm.
An advantage of providing the computer program with a correction algorithm and/or a machine learning component is that the radionuclide selector becomes selt-learning with respect to the anomalies,
distortions and/or irregularities in the measured energy spectrum of a dose in the dose calibrator. This reduces time and cost to calibrate the radionuclide selector for use.
In an embodiment according to the invention, the spectrum analyser comprises a sensor for detecting and measuring a radionuclide energy spectrum.
5 An advantage of a sensor is that it provides a sturdy, efficient and low-cost device to measure the radionuclide energy spectrum.
Another advantage is that, contrary to other measuring devices, a sensor can relatively easily be replaced in case of malfunctioning. This reduces maintenance costs and increases operational availability.
In an embodiment according to the invention, the sensor has a detection range of several kBq to 10 GBq, and more preferably has a detection range of 1 MBq to 500 MBq.
It will be understood that kBq relates to kilobecquerel, MBq relates to megabecquerel, and GBg relates to gigabecquerel, wherein Becquerel is defined as the activity of a quantity of radioactive material in which one nucleus decays per second.
In an embodiment according to the invention, the sensor is a pin-photodiode and/or wherein the sensor comprises a crystal-based or crystal sensor.
Another advantage of the pin-photodiode is that it is relatively cheap compared to other sensors, including Germanium- and Nal-based sensors. Therewith, it provides an effective and cost-efficient Sensor.
An advantage of crystal or crystal-based sensor is that it provides accurate measurements, which reduces the need to correct measurement data for deviations or noise in the measurements.
In an embodiment according to the invention, at least part of the radionuclide selector is connected to or integrated in a wall of the ionisation chamber, wherein the wall is a bottom wall, a top wall or a side wall of the ionisation chamber, and wherein the connected or integrated part preferably comprises the spectrum analyser.
An advantage of the connection to or integration of a (small) spectrum analyser inside the dose calibrator (for instance in the bottom of the ionisation chamber) adds functionality to this dose calibrator that can indicate the detected nuclide to the user and select the right nuclide automatically without significantly increasing the cost and size of the dose calibrator.
In an embodiment according to the invention, the radionuclide selector is configured to at least detect gamma and/or beta emitting radionuclides, including Technetium (*"Tc) and/or PET-radiation sources, such as radioactive Fluor (“F).
The dose calibrator according to the invention is preferably adapted to measure at least the most regular isotopes used in nuclear medicine, which includes Technetium (*"Tc). In this way, it is ascertained that the dose calibrator can effectively be used to prepare the (most regular) patient doses with radionuclides.
In an embodiment according to the invention, the dose calibrator additionally comprises one or more of a power supply, preferably a high voltage power supply, an electronic amplifier, and mounting means for mounting the dose calibrator to a support, a wall or a working surface.
In an embodiment according to the invention, the user interface is a graphic user interface (GUI), and preferably comprises a display, and more preferably comprises a touch display.
In order to provide an efficient and user-friendly user interface, the user interface preferably comprises a graphic user interface and/or a display. This allows an operator to more easily react to th information (output) provided to him or her and/or provide input to the dose calibrator.
The invention also relates to a method for measuring a dose in a dose calibrator, the method comprising: — providing a dose calibrator comprising an radionuclide selector; — introducing a radionuclide dose in the ionisation chamber; — determining, by the radionuclide selector, the type of radionuclide in the dose in the ionisation chamber; and — outputting the determined radionuclide type to the user interface.
The method according to the invention provides similar effects and advantages as the dose calibrator according to the invention. It is noted that the method according to the invention is freely combinable with the various embodiments as described in relation to the dose calibrator according to the invention.
An advantage of the method according to the invention is that it provides an efficient manner of reducing the risk of using an incorrect nuclide as base value to determine a dose size of a dose in the dose calibrator.
Another advantage of the method according to the invention is that the detection and selection of the radionuclide entered into the dose calibrator is an automated process, which (preferably) provides feedback to the operator (and/or user) to establish the correct selection is made. Moreover, the mere fact that feedback is provided by the dose calibrator via the user interface already provides additional security, because the operator is required to react, for example by selecting or rejecting the type of nuclide selected by the nuclide selector, to the dose calibrator output. This prevents an operator from performing a measurement with the dose calibrator without choosing a nuclide to be measured or by simply using the previous settings of the dose calibrator.
In an embodiment of the method according to the invention, the step of automatically determining the type of radionuclide comprises the steps of measuring, by a spectrum analyser of the radionuclide selector, an energy spectrum from the radionuclide dose in the ionisation chamber, matching, by a read- out unit of the radionuclide selector, the measured energy spectrum to the energy spectra of a list of stored radionuclides, and selecting the matching radionuclide for output to the user interface.
An advantage of this embodiment of the method according to the invention is that the energy spectrum of the radionuclide in the ionisation chamber is matched to a (large) list of energy spectra of known radionuclides, which allows a wide range of radionuclides to be detected and matched (for output). This increases the range of applications for which the method can be used.
Another advantage of this embodiment of the method according to the invention is that the nuclide is automatically matched and selected for output to the operator. This obviates the step of selecting the (correct) nuclide by the operator and increases processing speed. It also reduces risk of an incorrect (or no) nuclide being selected prior to the dose measurement.
In an embodiment of the method according to the invention, the steps of matching and selecting by the read-out unit comprise the step of comparing the measured energy spectrum to a list of energy spectra stored in a memory, wherein each of the energy spectra is coupled to a radionuclide. It further comprises one of three additional steps. If a match is found during the step of comparing, the method comprises selecting the associated radionuclide, outputting the selected radionuclide to the user interface; and prompting the user through the user interface to confirm or reject the selected radionuclide. If no complete match is found during the step of comparing, the method comprises providing a selection of closely matching radionuclides to the user interface, and prompting the user through the user interface to select the radionuclide in the radionuclide dose from the selection. If no match is found during the step of comparing, the method comprises outputting to the user interface a selection failure message, and prompting the user to manually select the radionuclide in the radionuclide dose from a list of radionuclides.
An advantage of this embodiment of the method according to the invention is that it, even when only a range of possible radionuclides or no radionuclide is found, still provides an operator with a selection menu that prompts him or her to action. This obviates the risk that the radionuclide that was selected for previous measurements can be used in a current of in future measurements without operator input.
Another advantage is that, even in the event the radionuclide can not be established with sufficient certainty, the nuclide selector provides a list of closely matching nuclides from which the operator may choose to perform the measurement. This forces an operator decision to reduce risk of an incorrect nuclide being selected. Additionally or alternatively, it may increase speed or process by providing a short-list.
In an embodiment of the method according to the invention, the step of selecting by the read-out unit additionally comprises the steps of providing by the radionuclide selector, preferably a control unit of the dose selector, to the user interface a confirmation message to prompt the user to confirm or reject the selected radionuclide, and optionally prompt the user to select a radionuclide from the list of radionuclides if the selected radionuclide is rejected by the user.
An advantage of this embodiment of the method according to the invention is that it provides an operator with a prompt to action. This obviates the risk that the radionuclide that was selected for previous measurements can be used in a current of in future measurements without operator input.
In an embodiment of the method according to the invention, the method is a computer- implemented method.
It has been found that, depending on the dose calibrator and/or the specific position of the spectrum analyser with respect to the ionisation chamber of the dose calibrator, some distortion of the radioactive spectrum of the radionuclide in the ionisation chamber may be present. This is mainly due to the characteristics of the ionisation chamber (and/or the position of the spectrum analyser with respect to the ionisation chamber). In this embodiment of the method according to the invention, the method may be computer-implemented method in which the radionuclide selector may comprise a computer program that, when executed, for example by a processer, is configured to correct distortions and/or anomalies in the measurement by the spectrum analyser. An advantage of this embodiment is that an even more accurate detection (and subsequent selection) can be performed by the nuclide selector.
In an embodiment of the method according to the invention, the method is a computer- implemented method comprising a computer program, wherein the computer program comprises a correction algorithm and a machine learning component, wherein the computer program is configured to, using the machine learning component, calibrate the correction algorithm.
An advantage of providing the computer program with a correction algorithm and/or a machine learning component is that the method provides a self-learning radionuclide selector with respect to the anomalies, noise, distortions and/or irregularities in the measured energy spectrum of a dose in the dose calibrator. This reduces time and cost to calibrate the radionuclide selector for use.
The invention also relates to a computer readable storage media comprising computer-readable instructions that, when executed, implement a method according to the invention.
The computer readable storage media according to the invention provides similar effects and advantages as the dose calibrator and the method according to the invention. It is noted that the computer readable storage media according to the invention is freely combinable with the various embodiments as described in relation to the dose calibrator and/or the method according to the invention.
Further advantages, features and details of the invention are elucidated on the basis of preferred embodiments thereof, wherein reference is made to the accompanying drawings, in which: Figures la, 1b shows an example of a perspective view of a dose calibrator according to the invention; Figure 2 shows a cross section of the example of figure la; Figures 3a, 3b shows two examples of energy spectra that are detectable with the dose calibrator according to the invention; and Figure 4 shows a schematic example of the method according to the invention.
In an example of dose calibrator 2 (see figures 1 and 2), dose calibrator 2 comprises housing 4, which essentially is a double housing 6,8. Outer housing 6 comprises outer side wall 10, bottom wall 12, and top wall 14. Top wall 14 is provided with insertion opening 24 that allows a dose, for example in a syringe, to be introduced in ionisation chamber 16. Inner housing 8 comprises inner side wall 18, lower wall 20 and upper wall 22. Upper wall 22 comprises insertion opening 24 that coincides with the insertion opening 24 of top wall 14. Inner housing 8 further comprises ionisation chamber 16, which is provided with chamber side wall 25and chamber bottom wall 26. A top end of portion of chamber side wall 25 is connected with upper wall 22 of inner housing 8. As a result, gas space 28 is formed, which extends between inner side wall 18 and chamber side wall 24 as well as between lower wall 20 and chamber bottom wall 26. Gas space 28 is provided with electrodes 30 as well as with ionisable gas 32.
Housing 4 further comprises housing space 34, which is disposed between inner housing 8 and outer housing 6. Spectrum analyzer 36 of radionuclide selector 38 is provided in housing space 34, and is in this example specifically provided near lower wall 20. The position of spectrum analyzer 36 is chosen such that it is capable of receiving a part of the radiated energy E from the dose in ionisation chamber 16.
Radionuclide selector 38 further comprises read-out unit 40, which is connected to spectrum analyser 36. Read-out unit 40 may be disposed in housing space 34, yet preferably is provided outside dose calibrator 2.
In use of dose calibrator 2, syringe S is introduced into ionisation chamber 16. The radiated energy spectrum E is, at least partially, received by spectrum analyser 36, which transmits the measured energy spectrum E to read-out unit 40. Read-out unit 40 in this example processes received energy spectrum E by matching the measured energy spectrum to the energy spectra of a list of stored radionuclides and subsequently by selecting the matching radionuclide for output to user interface 42. In this case, user interface 42 is GUI 42, more specifically touch screen 42. In this example, read-out unit 40, spectrum analyser 36 and touch screen 42 are controlled by control unit 46. Control unit 46 further controls computer program 48, which is configured to correct alterations and/or distortions in energy spectrum E measured by the spectrum analyser that are caused by its crossing of chamber bottom wall 26 and ionisable gas 32.
Additional components (shown in dashed lines) may comprise power supply 60, electronic amplifier 50, mounting means 52 and memory 54, each of which is schematically shown in figure 1 and/or figure 2. In this example, mounting means 52 comprise supports or feet 52. It is noted that mounting means 52 may also be a clamp or other suitable means, for example for mounting it to a wall.
In an example (see figure 2), energy spectra are shown of radio nuclides that are regularly used in nuclear medicine and which are detectable with the dose calibrator according to the invention, such as the example of dose calibrator 2 according to the invention (see figure 1 and figure 2).
Figures 3a, 3b show the energy spectrum of Technetium (Tc-99m), which can be measured using the lower end of the measurement spectrum of the spectrum analyser of the dose calibrator according to the invention (as shown on the Channel axis). It also shows (below) the energy spectrum of Fluor (F-18}, which uses the medium to higher end of the measurement spectrum of the spectrum analyser of the dose calibrator according to the invention (as shown on the Channel axis).
In an example of the method according to the invention (see figure 4), the method may comprise the steps of providing 1002 a dose calibrator 2 comprising an radionuclide selector 38 and introducing 1004 a radionuclide dose S in ionisation chamber 16. Subsequently, the method comprises determining 1006, by radionuclide selector 38, the type of radionuclide in the dose S in ionisation chamber 16, and outputting 1008 the determined radionuclide type to user interface 42.
The step of determining 1006 the type of radionuclide may comprise the steps of measuring 1010, by spectrum analyser 36 of radionuclide selector 38, energy spectrum E from radionuclide dose S in ionisation chamber 16, and subsequently matching 1012, by read-out unit 40 of radionuclide selector 38, measured energy spectrum E to energy spectra of a list of stored radionuclides, and selecting 1014 the matching radionuclide for output to user interface 42.
In addition, the steps of matching 1012 and selecting 1014 by read-out unit 40 may comprise the steps of comparing 1016 measured energy spectrum E to a list of energy spectra stored in memory 54, wherein each of the energy spectra is coupled to a radionuclide. If a match is found, the method comprises selecting 1018 the associated radionuclide, outputting 1020 the selected radionuclide to user interface 42, and prompting 1022 a user through user interface 42 to confirm or reject the selected radionuclide.
If no complete match is found, the method comprises providing 1024 a selection of closely matching radionuclides to user interface 42, and prompting 1026 the user through user interface 42 to select 1028 the radionuclide in the radionuclide dose from the selection.
If no match is found at all, the method comprises outputting 1030 to user interface 42 a selection failure message 56, and prompting 1032 the user to manually select the radionuclide in the radionuclide dose from a list of radionuclides.
Optionally, the step of selecting 1012 by read-out unit 40 additionally comprises the steps of providing 1034 by radionuclide selector 38, preferably control unit 46 of dose selector 38, to user interface 42 a confirmation message 58 to prompt 1036 the user to confirm or reject the selected radionuclide, and optionally prompt 1038 the user to select a radionuclide from the list of radionuclides if the selected radionuclide is rejected by the user.
The present invention is by no means limited to the above described preferred embodiments thereof. The rights sought are defined by the following claims within the scope of which many modifications can be envisaged.
1. Dose calibrator comprising: — an ionisation chamber that is configured to hold a dose including one type of radionuclide; — adose calibrator control unit that is configured to, based on ionisation chamber measurements and the type of radionuclide, calculate a dose size of the dose of the type of radionuclide in the ionisation chamber; — a user interface that is operatively connected to the ionisation chamber and that is configured to provide a user with information on the calculated dose size; and — anradionuaclide selector comprising: — a spectrum analyser that is operatively connected to the ionisation chamber, wherein the spectrum analyser is configured to measure an energy spectrum of the type of radionuclide in the ionisation chamber; — a read-out unit that is operatively connected to the spectrum analyser and that is configured to: ~ match the measured energy spectrum to the energy spectra of a list of stored radionuclides; ~ select the matching radionuclide for output to the user interface.
2. Dose calibrator according to clause 1, wherein the radionuclide selector comprises a radionuclide selector control unit that is operatively connected to the spectrum analyser, read-out unit and the user interface, wherein the radionuclide selector unit is configured to sent the selected matching radionuclide to the user interface.
3. Dose calibrator according to clause 1 or 2, wherein the read-out unit is further configured to, when matching the measured energy spectrum to an energy spectrum of a list of stored radionuclides and select the matching radionuclide for output: — compare the measured energy spectrum to the energy spectra of a list of stored radionuclides; and — if a match is found: ~ select the associated radionuclide; and ~ output the selected radionuclide to the user interface; — if no complete match is found: ~ provided a selection of closely matching radionuclides as output to the user interface; — if no match is found: ~ provide a selection failure message and the list of available radionuclides for selection as output to the user interface.
4. Dose calibrator according to any one of the preceding clauses, wherein the radionuclide selector further comprises a computer program that is configured to correct the energy spectrum that is measured by the spectrum analyser to correct alterations and/or anomalies caused by the ionisation chamber.
5. Dose calibrator according to any one of the preceding clauses, wherein the spectrum analyser comprises a sensor for detecting and measuring a radionuclide energy spectrum.
6. Dose calibrator according to clause 5, wherein the sensor has a detection range of several kBq to 10 GBq, and more preferably has a detection range of 1 MBq to 500 MBq.
7. Dose calibrator according to clause 5 or 6, wherein the sensor is a pin-photodiode and/or wherein the sensor comprises a crystal sensor or a crystal-based sensor.
8. Dose calibrator according to any one of the preceding clauses, wherein at least part of the radionuclide selector is connected to or integrated in a wall of the ionisation chamber, wherein the wall is a bottom wall, a top wall or a side wall of the ionisation chamber, and wherein the connected or integrated part preferably comprises the spectrum analyser.
9. Dose calibrator according to any one of the preceding clauses, wherein the radionuclide selector . ~ oo. . . . . . OH is configured to at least detect gamma and/or beta emitting radionuclides, including Technetium (Te) and/or PET-radiation sources, such as radioactive Fluor ( BE),
10. Dose calibrator according to any one of the preceding clauses, additionally comprising one or more of: — a power supply, preferably a high voltage power supply; — an electronic amplifier; and — mounting means for mounting the dose calibrator to a support or a wall.
11. Dose calibrator according to any one of the preceding clauses, wherein the user interface is a graphic user interface (GUI), and preferably comprises a display, and more preferably comprises a touch display.
12. Method for measuring a dose in a dose calibrator, the method comprising:
— providing a dose calibrator comprising an radionuclide selector; — introducing a radionuclide dose in the ionisation chamber; — determining, by the radionuclide selector, the type of radionuclide in the dose in the ionisation chamber; and — outputting the determined radionuclide type to the user interface.
13. Method according to clause 12, wherein the step of determining the type of radionuclide comprise the steps of: — measuring, by a spectrum analyser of the radionuclide selector, an energy spectrum from the radionuclide dose in the ionisation chamber; — matching, by a read-out unit of the radionuclide selector, the measured energy spectrum to the energy spectra of a list of stored radionuclides; and — selecting the matching radionuclide for output to the user interface.
14. Method according to clause 13, wherein the steps of matching and selecting by the read-out unit comprise the steps of: — comparing the measured energy spectrum to a list of energy spectra stored in a memory, wherein each of the energy spectra is coupled to a radionuclide; and ~ if a match is found: — select the associated radionuclide; — output the selected radionuclide to the user interface; and — prompting the user through the user interface to confirm or reject the selected radionuclide; or ~ if no complete match is found: — provide a selection of closely matching radionuclides to the user interface; — prompting the user through the user interface to select the radionuclide in the radionuclide dose from the selection; or ~ if no match is found: — outputting to the user interface a selection failure message; and — prompting the user to manually select the radionuclide in the radionuclide dose from a list of radionuclides.
15. Method according to clause 13 or 14, wherein the step of selecting by the read-out unit additionally comprises the steps of:
— providing by the radionuclide selector, preferably a control unit of the dose selector, to the user interface a confirmation message to prompt the user to confirm or reject the selected radionuclide; and — optionally prompt the user to select a radionuclide from the list of radionuclides if the selected radionuclide is rejected by the user.
16. Method according to any one of the clauses 12 to 15, wherein the method is a computer- implemented method.
17. Computer readable storage media comprising computer-readable instructions that, when executed, implement a method according to any one of the clauses 12 to 15.
Claims (17)
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