CA3136561C - System and method for removing irradiation targets from a nuclear reactor and radionuclide generation system - Google Patents
System and method for removing irradiation targets from a nuclear reactor and radionuclide generation system Download PDFInfo
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- CA3136561C CA3136561C CA3136561A CA3136561A CA3136561C CA 3136561 C CA3136561 C CA 3136561C CA 3136561 A CA3136561 A CA 3136561A CA 3136561 A CA3136561 A CA 3136561A CA 3136561 C CA3136561 C CA 3136561C
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C23/00—Adaptations of reactors to facilitate experimentation or irradiation
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- High Energy & Nuclear Physics (AREA)
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
An irradiation target removal system comprises at least one storage container (34) for receiving activated irradiation targets (16) from an instrumentation tube system (12) of a nuclear reactor; a discharge tube (30) comprising a first discharge tube section (38), a second discharge tube section (40) and a conjunction of the first and second discharge tube sections (38, 40); and a supply (52) of pressurized gas connected to the first discharge tube section (38) for pressurizing the discharge tube (30). The second discharge tube section (40) is coupled to the instrumentation tube system (12), wherein the first discharge tube section (38) comprises an exit port (32) assigned to the storage container (34); a first lock element (36) for blocking movement of the activated irradiation targets (16) to the storage container (34), wherein the first lock element (36) is located between the exit port (32) and the conjunction; and at least one opening (46) located between the first lock element (36) and the conjunction, wherein the supply (52) of pressurized gas is connected to the at least one opening (46). Further, a radioisotope generation system, a discharge tube and a method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor are shown.
Description
System and Method for Removing Irradiation Targets from a Nuclear Reactor and Radionuclide Generation System FIELD OF THE INVENTION
The present invention is directed to a system and a method for removing irradiation targets from a commercial nuclear reactor and a radionuclide generation system.
TECHNICAL BACKGROUND OF THE INVENTION
Radionuclides are used in various fields of technology and science, as well as for medical purposes. Usually, radionuclides are produced in research reactors or cyclotrons. However, since the number of facilities for commercial production of radionuclides is limited already and expected to decrease, it is desired to provide alternative production sites.
The neutron flux density in the core of a commercial nuclear reactor is measured, inter alia, by introducing solid spherical probes into instrumentation tubes passing through the reactor core. It was therefore suggested that instrumentation tubes of commercial nuclear reactors shall be used for producing radionuclides.
EP 2 093 773 A2 suggests that existing instrumentation tube systems conventionally used for housing neutron detectors may be used to generate radionuclides during normal operation of a commercial nuclear reactor. In particular, spherical irradiation targets are linearly pushed into and removed from instrumentation fingers extending into the reactor core. Based on the axial neutron flux profile of the reactor core, the optimum position and exposure time of the targets in the reactor core are determined. A driving gear system is used for moving and holding the irradiation targets in the instrumentation tube system.
The present invention is directed to a system and a method for removing irradiation targets from a commercial nuclear reactor and a radionuclide generation system.
TECHNICAL BACKGROUND OF THE INVENTION
Radionuclides are used in various fields of technology and science, as well as for medical purposes. Usually, radionuclides are produced in research reactors or cyclotrons. However, since the number of facilities for commercial production of radionuclides is limited already and expected to decrease, it is desired to provide alternative production sites.
The neutron flux density in the core of a commercial nuclear reactor is measured, inter alia, by introducing solid spherical probes into instrumentation tubes passing through the reactor core. It was therefore suggested that instrumentation tubes of commercial nuclear reactors shall be used for producing radionuclides.
EP 2 093 773 A2 suggests that existing instrumentation tube systems conventionally used for housing neutron detectors may be used to generate radionuclides during normal operation of a commercial nuclear reactor. In particular, spherical irradiation targets are linearly pushed into and removed from instrumentation fingers extending into the reactor core. Based on the axial neutron flux profile of the reactor core, the optimum position and exposure time of the targets in the reactor core are determined. A driving gear system is used for moving and holding the irradiation targets in the instrumentation tube system.
- 2 -Due to the high activity of the activated irradiation targets retrieved from the instrumentation tube system, and since space within the reactor containment is limited, the activated targets are difficult to handle. In particular, the activated targets including the radionuclides must be filled into and stored in containers provided with heavy radiation shielding. The chambers for a Traversing Incore Probe (TIP) system and/or an Aero-ball Measuring System (AMS) do not have any structures for packaging and transporting those heavy containers. Provision of additional water locks in the reactor containment for handling of the activated targets and shielded containers would also be too expensive.
WO 2016/173664 Al describes an irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core. The target processing system comprises a target retrieving system, a target insertion system and a transport gas supply, which are mounted on a movable support. The target retrieving system comprises a discharge tube having a lock element for blocking movement of the irradiation targets into an exit port. The discharge tube is formed as inverse U, forming an apex and a first section and a second section of the discharge tube. The lock element blocks the movement of the activated irradiation targets in the first discharge tube section. The exit port comprises a gas inlet port coupled to a first gas supply tubing and a ball valve, which connects the exit port with a storage container and an external exhaust system. The target processing system comprises at least one movable magnet, which can differentiate between irradiation targets and positioning targets in case the two types of targets differ in their magnetic properties.
WO 2017/012655 Al describes a method of producing radionuclides from irradiation targets in a nuclear reactor using at least one instrumentation tube system of a commercial nuclear reactor. Irradiation targets and dummy targets are inserted into an instrumentation finger and the irradiation targets are activated by exposing them to neutron flux in the nuclear reactor core to form a desired radionuclide_ The dummy targets are used to hold the irradiation targets at a predetermined axial position in the reactor core corresponding to a pre-calculated neutron flux density sufficient for converting the irradiation targets to the radionuclide. The dummy targets are separated from the activated irradiation targets by exposing the dummy targets and/or the activated irradiation targets to a magnetic field to retain either the dummy targets or the activated irradiation targets
WO 2016/173664 Al describes an irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core. The target processing system comprises a target retrieving system, a target insertion system and a transport gas supply, which are mounted on a movable support. The target retrieving system comprises a discharge tube having a lock element for blocking movement of the irradiation targets into an exit port. The discharge tube is formed as inverse U, forming an apex and a first section and a second section of the discharge tube. The lock element blocks the movement of the activated irradiation targets in the first discharge tube section. The exit port comprises a gas inlet port coupled to a first gas supply tubing and a ball valve, which connects the exit port with a storage container and an external exhaust system. The target processing system comprises at least one movable magnet, which can differentiate between irradiation targets and positioning targets in case the two types of targets differ in their magnetic properties.
WO 2017/012655 Al describes a method of producing radionuclides from irradiation targets in a nuclear reactor using at least one instrumentation tube system of a commercial nuclear reactor. Irradiation targets and dummy targets are inserted into an instrumentation finger and the irradiation targets are activated by exposing them to neutron flux in the nuclear reactor core to form a desired radionuclide_ The dummy targets are used to hold the irradiation targets at a predetermined axial position in the reactor core corresponding to a pre-calculated neutron flux density sufficient for converting the irradiation targets to the radionuclide. The dummy targets are separated from the activated irradiation targets by exposing the dummy targets and/or the activated irradiation targets to a magnetic field to retain either the dummy targets or the activated irradiation targets
- 3 -in the instrumentation tube system and release the other one of the activated irradiation target or the dummy target from the instrumentation tube system.
For this purpose, the dummy targets and the activated irradiation targets have different magnetic properties.
WO 2017/012655 Al describes a method for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor. For this purpose, the instrumentation tube system is coupled to a discharge tube having an apex, an exit port and a lock element between the apex and the exit port. The activated irradiation targets are passed from the instrumentation tube system into the discharge tube and their movement is blocked by means of the lock element. Due to the apex, the activated irradiated targets can be separated into two quantities of targets. By releasing the lock element, the irradiation targets between the lock element and the apex can be passed under action of gravity into a storage container coupled to the exit port, retaining the other quantity of the targets in the discharge tube by means of the apex.
However, the quantity of activated irradiation targets in the discharge tube between the lock element and the apex is fixed by the given geometry of the harvesting system comprising the discharge tube and the apex. However, it has been shown that the size of the available and needed storage containers is often not big enough to incorporate the given quantity of activated irradiation targets.
At the same time, the use of dummy targets, which can be magnetically separated from the irradiation targets, is unfavorable, as the number of targets within the nuclear core is limited and the irradiation times can be very long, in some cases up to 2 weeks. Therefore, it is desirable to use the positions needed for the dummy targets for irradiation targets, too.
It is therefore an object of the invention to provide an irradiation target removal system, which allows the use of a higher amount of irradiation targets for the production of radioisotopes in a commercial nuclear reactor and provides an improved possibility of portioning activated irradiation targets. Furthermore, it is an object of the invention to provide a radionuclide generation system comprising such an irradiation target removal system. In addition, it is an object of the invention to provide a method for removing activated irradiation targets in such systems.
For this purpose, the dummy targets and the activated irradiation targets have different magnetic properties.
WO 2017/012655 Al describes a method for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor. For this purpose, the instrumentation tube system is coupled to a discharge tube having an apex, an exit port and a lock element between the apex and the exit port. The activated irradiation targets are passed from the instrumentation tube system into the discharge tube and their movement is blocked by means of the lock element. Due to the apex, the activated irradiated targets can be separated into two quantities of targets. By releasing the lock element, the irradiation targets between the lock element and the apex can be passed under action of gravity into a storage container coupled to the exit port, retaining the other quantity of the targets in the discharge tube by means of the apex.
However, the quantity of activated irradiation targets in the discharge tube between the lock element and the apex is fixed by the given geometry of the harvesting system comprising the discharge tube and the apex. However, it has been shown that the size of the available and needed storage containers is often not big enough to incorporate the given quantity of activated irradiation targets.
At the same time, the use of dummy targets, which can be magnetically separated from the irradiation targets, is unfavorable, as the number of targets within the nuclear core is limited and the irradiation times can be very long, in some cases up to 2 weeks. Therefore, it is desirable to use the positions needed for the dummy targets for irradiation targets, too.
It is therefore an object of the invention to provide an irradiation target removal system, which allows the use of a higher amount of irradiation targets for the production of radioisotopes in a commercial nuclear reactor and provides an improved possibility of portioning activated irradiation targets. Furthermore, it is an object of the invention to provide a radionuclide generation system comprising such an irradiation target removal system. In addition, it is an object of the invention to provide a method for removing activated irradiation targets in such systems.
- 4 -SUMMARY OF THE INVENTION
The above objects are solved by an irradiation target removal system as described herein, a radionuclide generation system as described herein, a discharge tube as described herein, and a method for removing activated irradiation targets as described herein.
According to a first aspect, the invention provides an irradiation target removal system comprising at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor; and a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube section;
and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises an exit port assigned to the storage container, a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening.
In some implementations, there is provided an irradiation target removal system comprising: at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor; a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube sections; and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises:
Date recue / Date received 2021-11-24 - 4a -- an exit port assigned to the storage container;
- a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and - at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
The irradiation target removal system comprises several possibilities for separating the activated irradiation targets into smaller quantities. A first separation can be done by means of the shape of the discharge tube. Due to the first lock element, a predefined amount of irradiation targets can be kept between the first lock element and the conjunction in the first discharge tube section (from here on defined as "full quantity").
When the first lock element is released, all irradiation targets in the first discharge tube section are removed from the discharge tube, for instance due to gravity, and can be collected by the storage container. This corresponds to methods for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor as known in the art. However, in this case storage _____________ Date recue / Date received 2021-11-24
The above objects are solved by an irradiation target removal system as described herein, a radionuclide generation system as described herein, a discharge tube as described herein, and a method for removing activated irradiation targets as described herein.
According to a first aspect, the invention provides an irradiation target removal system comprising at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor; and a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube section;
and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises an exit port assigned to the storage container, a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening.
In some implementations, there is provided an irradiation target removal system comprising: at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor; a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube sections; and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises:
Date recue / Date received 2021-11-24 - 4a -- an exit port assigned to the storage container;
- a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and - at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
The irradiation target removal system comprises several possibilities for separating the activated irradiation targets into smaller quantities. A first separation can be done by means of the shape of the discharge tube. Due to the first lock element, a predefined amount of irradiation targets can be kept between the first lock element and the conjunction in the first discharge tube section (from here on defined as "full quantity").
When the first lock element is released, all irradiation targets in the first discharge tube section are removed from the discharge tube, for instance due to gravity, and can be collected by the storage container. This corresponds to methods for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor as known in the art. However, in this case storage _____________ Date recue / Date received 2021-11-24
- 5 -containers are needed, which are big enough to incorporate the "full quantity"
of activated irradiation targets.
In contrast, by providing at least one opening located between the first lock element and the conjunction, it is possible to further divide the "full quantity" of irradiation targets into smaller predefined quantities. The size of these predefined quantities is defined by the location of the at least one opening within the first discharge tube section. In fact, the at least one opening is located at a side area of the first discharge tube section, namely the lateral side.
Providing openings is an easy way to realize the supply of pressurized gas into the discharge tube. Also, this is an easy solution to incorporate the irradiation target removal system of the present invention into existing systems.
For instance, the at least one opening relates to a borehole that is drilled into the first discharge tube section_ Hence, already existing discharge tubes can be used.
By applying a stream of pressurized gas through the at least one opening, all irradiation targets above the level of the at least one borehole can be transferred back into the second discharge tube section and even back to instrumentation fingers of the nuclear reactor. Alternatively or additionally, further holding or rather stopping positions may be defined that are located closer to the nuclear reactor with respect to the at least one opening_ For instance, these holding or rather stopping positions are defined by other openings in the discharge tube, which may interact with other lock elements.
In any case, only a predefined quantity of activated irradiation targets is retained in the first discharge tube section due to the pressurized gas, which corresponds to the distance between the first lock element and the position of the at least one opening.
The predefined quantity of activated irradiation targets can be adjusted to the size of the available storage containers, in which the activated irradiation targets are typically stored.
The separation of the different quantities of targets in the first discharge tube section is based only on the location at which gas is supplied into the discharge
of activated irradiation targets.
In contrast, by providing at least one opening located between the first lock element and the conjunction, it is possible to further divide the "full quantity" of irradiation targets into smaller predefined quantities. The size of these predefined quantities is defined by the location of the at least one opening within the first discharge tube section. In fact, the at least one opening is located at a side area of the first discharge tube section, namely the lateral side.
Providing openings is an easy way to realize the supply of pressurized gas into the discharge tube. Also, this is an easy solution to incorporate the irradiation target removal system of the present invention into existing systems.
For instance, the at least one opening relates to a borehole that is drilled into the first discharge tube section_ Hence, already existing discharge tubes can be used.
By applying a stream of pressurized gas through the at least one opening, all irradiation targets above the level of the at least one borehole can be transferred back into the second discharge tube section and even back to instrumentation fingers of the nuclear reactor. Alternatively or additionally, further holding or rather stopping positions may be defined that are located closer to the nuclear reactor with respect to the at least one opening_ For instance, these holding or rather stopping positions are defined by other openings in the discharge tube, which may interact with other lock elements.
In any case, only a predefined quantity of activated irradiation targets is retained in the first discharge tube section due to the pressurized gas, which corresponds to the distance between the first lock element and the position of the at least one opening.
The predefined quantity of activated irradiation targets can be adjusted to the size of the available storage containers, in which the activated irradiation targets are typically stored.
The separation of the different quantities of targets in the first discharge tube section is based only on the location at which gas is supplied into the discharge
- 6 -tube. Therefore, there is no need to implement means to differentiate between different types of targets, for example by their magnetic properties. In this way, there is no need to use dummy targets in the inventive irradiation target removal system for realizing smaller predefined quantities of activated irradiation targets compared to the "full quantity" defined by the geometry of the discharge tube.
Therefore, all possible positions within the instrumentation fingers of the nuclear core of the nuclear reactor can be used for production of irradiation targets.
This increases the efficiency of the generation of radionuclides compared to previous radionuclide generation systems. Simultaneously, the portioning is simplified since no magnetic systems are required for selecting the activated irradiation targets.
However, it is still possible to use dummy targets if wished. This can be necessary if it is known that there are positions in the instrumentation fingers of the nuclear core that do not exhibit sufficiently high neutron flux density to obtain the desired radionuclides in sufficiently high amounts for their intended applications.
Preferably, the dummy targets are magnetic, which allows for using a selector mechanism to easily distinguish between and separate activated irradiation targets from the dummy targets_ Furthermore, the inventive irradiation target removal system can easily be applied to existing facilities by providing the at least one opening to, particularly drilling the at least one borehole into, the first discharge tube section and connecting this at least one opening, particularly borehole, to a supply of pressurized gas.
An apex may be formed at the conjunction of the first and second discharge tube sections, wherein the first and second discharge tube sections are directed downwardly from the apex. The first lock element is located between the exit port and the apex. The at least one opening is located between the first lock element and the apex. As mentioned above, the irradiation target removal system comprises the first separation that is done by means of the shape of the discharge tube, namely the apex. Due to the first lock element, a predefined amount of irradiation targets can be kept between the first lock element and the apex in the first discharge tube section (from here on defined as "full quantity"). The apex and both tube sections directed downwardly from the apex ensure that gravity can be used for the first separation.
Therefore, all possible positions within the instrumentation fingers of the nuclear core of the nuclear reactor can be used for production of irradiation targets.
This increases the efficiency of the generation of radionuclides compared to previous radionuclide generation systems. Simultaneously, the portioning is simplified since no magnetic systems are required for selecting the activated irradiation targets.
However, it is still possible to use dummy targets if wished. This can be necessary if it is known that there are positions in the instrumentation fingers of the nuclear core that do not exhibit sufficiently high neutron flux density to obtain the desired radionuclides in sufficiently high amounts for their intended applications.
Preferably, the dummy targets are magnetic, which allows for using a selector mechanism to easily distinguish between and separate activated irradiation targets from the dummy targets_ Furthermore, the inventive irradiation target removal system can easily be applied to existing facilities by providing the at least one opening to, particularly drilling the at least one borehole into, the first discharge tube section and connecting this at least one opening, particularly borehole, to a supply of pressurized gas.
An apex may be formed at the conjunction of the first and second discharge tube sections, wherein the first and second discharge tube sections are directed downwardly from the apex. The first lock element is located between the exit port and the apex. The at least one opening is located between the first lock element and the apex. As mentioned above, the irradiation target removal system comprises the first separation that is done by means of the shape of the discharge tube, namely the apex. Due to the first lock element, a predefined amount of irradiation targets can be kept between the first lock element and the apex in the first discharge tube section (from here on defined as "full quantity"). The apex and both tube sections directed downwardly from the apex ensure that gravity can be used for the first separation.
- 7 -In one embodiment, the at least one opening can comprise a set of openings provided at the first discharge tube section circumferentially at the same height. In this way, the pressurized gas can be supplied evenly into the first discharge tube, especially when the individual openings are provided symmetrically around the circumference of the first discharge tube section. This leads to a better control of the system when separating the irradiation targets. Particularly, a set of boreholes is drilled into the first discharged tube section circumferentially at the same height.
In a preferred embodiment, the pressurized gas supply comprises a control valve, preferably a 2/2 control valve. This provides an easy and secure way to control the gas flow coming from the gas supply.
To avoid that the gas coming from the gas supply leaks out around the discharge tube, the at least one opening can be housed in a pressure-tight encapsulation. This also increases the stability and control of the applied pressurized gas. Furthermore, the pressure-tight encapsulation may have radiation shielding properties.
In another embodiment, a second lock element can be located in a pathway originating from the instrumentation tube system. For instance, the second lock element is located in a pathway connecting the second discharge tube section and the instrumentation tube system.
In this way, the already activated irradiation targets, which are removed from the first discharge tube section, particularly the entire discharge tube, by the pressurized gas, can be blocked in the pathway before they are charged back into the instrumentation tube system. Therefore, it can be prevented that the irradiation targets again enter the nuclear core and are exposed to additional irradiation without the need to precisely adjust and control the gas flow into the first discharge tube section.
This system can be used for moving the irradiation targets several times between the pathway and the first discharge tube section, particularly the discharge tube section, e.g. when several times predefined quantities of activated irradiation targets are to be collected from the total amount present in the radionuclide generation system and filled in individual storage containers.
In a preferred embodiment, the pressurized gas supply comprises a control valve, preferably a 2/2 control valve. This provides an easy and secure way to control the gas flow coming from the gas supply.
To avoid that the gas coming from the gas supply leaks out around the discharge tube, the at least one opening can be housed in a pressure-tight encapsulation. This also increases the stability and control of the applied pressurized gas. Furthermore, the pressure-tight encapsulation may have radiation shielding properties.
In another embodiment, a second lock element can be located in a pathway originating from the instrumentation tube system. For instance, the second lock element is located in a pathway connecting the second discharge tube section and the instrumentation tube system.
In this way, the already activated irradiation targets, which are removed from the first discharge tube section, particularly the entire discharge tube, by the pressurized gas, can be blocked in the pathway before they are charged back into the instrumentation tube system. Therefore, it can be prevented that the irradiation targets again enter the nuclear core and are exposed to additional irradiation without the need to precisely adjust and control the gas flow into the first discharge tube section.
This system can be used for moving the irradiation targets several times between the pathway and the first discharge tube section, particularly the discharge tube section, e.g. when several times predefined quantities of activated irradiation targets are to be collected from the total amount present in the radionuclide generation system and filled in individual storage containers.
- 8 -The possibilities of an operator to collect a certain quantity of activated irradiation targets can be further increased by providing, particularly drilling, two or more sets of openings, for instance boreholes, at different heights of the first discharge tube section, wherein each set of openings, particularly boreholes, is connected to the pressurized gas supply.
The different sets of openings can be connected to the same or to different supplies of pressurized gas, which can have coupled or uncoupled valves for controlling the gas flow.
The distance between the first lock element and a first set of openings can be different to the distance between the first and a second set of openings.
By choosing different height differences between the first lock element and the different sets of openings, it becomes possible to choose between several different predefined quantities of irradiation targets retained in the first discharge tube section, dependent on through which set of openings pressurized gas is supplied, for instance.
The exit port can be positioned above the assigned storage container so that the predefined quantity of activated irradiation targets can be transferred to an filled in the storage container, for example by the action of gravity. The distance between the exit port and a corresponding opening in the storage container is adapted such that the irradiaton targets cannot miss the opening.
Preferably, the exit port is configured to be coupled to the assigned storage container. Providing a removable connection between the exit port and the storage container allows for operating in a closed system and minimizing the risk for an operator of being exposed to radiation.
In a preferred embodiment, the exit port comprises a stop valve for pressure-tightly sealing the exit port. Such an exit port prevents the pressurized gas supplied through the at least one opening to leak out of the exit port and therefore ensures that the pressure in the first discharge tube section increases and lifts the irradiation targets above the at least one opening beyond the conjunction, particularly over the apex, of the discharge tube.
The different sets of openings can be connected to the same or to different supplies of pressurized gas, which can have coupled or uncoupled valves for controlling the gas flow.
The distance between the first lock element and a first set of openings can be different to the distance between the first and a second set of openings.
By choosing different height differences between the first lock element and the different sets of openings, it becomes possible to choose between several different predefined quantities of irradiation targets retained in the first discharge tube section, dependent on through which set of openings pressurized gas is supplied, for instance.
The exit port can be positioned above the assigned storage container so that the predefined quantity of activated irradiation targets can be transferred to an filled in the storage container, for example by the action of gravity. The distance between the exit port and a corresponding opening in the storage container is adapted such that the irradiaton targets cannot miss the opening.
Preferably, the exit port is configured to be coupled to the assigned storage container. Providing a removable connection between the exit port and the storage container allows for operating in a closed system and minimizing the risk for an operator of being exposed to radiation.
In a preferred embodiment, the exit port comprises a stop valve for pressure-tightly sealing the exit port. Such an exit port prevents the pressurized gas supplied through the at least one opening to leak out of the exit port and therefore ensures that the pressure in the first discharge tube section increases and lifts the irradiation targets above the at least one opening beyond the conjunction, particularly over the apex, of the discharge tube.
- 9 -In a further preferred embodiment, at least one cartridge is provided that is assigned to the irradiation targets, the cartridge containing a radionuclide precursor material. Preferably, the cartridge comprises a housing containing one or more irradiation targets. In this way, the radionuclide precursor material does not need to be capable of forming spherical irradiation targets, which are stable enough to withstand the conditions in the radionuclide generation system. Especially in a pneumatically driven system, the forces acting on the targets might be large and not every desired precursor material is capable of forming sufficiently stable spheroids, which do not break or shatter when exposed to these forces. By using at least one cartridge, only the cartridge has to withstand the mechanical forces encountered. Therefore, radionuclides can be generated which would otherwise be not obtainable.
In another aspect, the invention provides a radionuclide generation system comprising an irradiation target removal system as described above.
According to a further aspect, the invention provides a discharge tube for an irradiation target removal system, particularly an irradiation target removal system as described above, the discharge tube comprising at least a first discharge tube section that comprises:
-an exit port assigned to a storage container of the irradiation target removal system;
-a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas.
In fact, the discharge tube according to the invention relates to the lower part of the irradiation target removal system described above.
In another aspect, the invention provides a radionuclide generation system comprising an irradiation target removal system as described above.
According to a further aspect, the invention provides a discharge tube for an irradiation target removal system, particularly an irradiation target removal system as described above, the discharge tube comprising at least a first discharge tube section that comprises:
-an exit port assigned to a storage container of the irradiation target removal system;
-a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas.
In fact, the discharge tube according to the invention relates to the lower part of the irradiation target removal system described above.
- 10 -In yet another aspect, the invention provides a discharge tube for an irradiation target removal system, the discharge tube comprising at least a first discharge tube section that comprises:
- an exit port assigned to a storage container of the irradiation target removal system;
- a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
In fact, the discharge tube according to the invention relates to the lower part of the irradiation target removal system described above.
In yet another aspect, the invention provides a method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor, wherein the method comprises the steps of:
a) Coupling at least one instrumentation finger of an instrumentation tube system to the irradiation target removal system as described above;
b) Passing the activated irradiation targets from the instrumentation finger into the discharge tube and blocking movement of the activated irradiation targets out of the discharge tube by means of the first lock element;
Date recue / Date received 2021-11-24 - 10a -c) Separating a predefined quantity of the activated irradiation targets from another quantity of the activated irradiation targets in the discharge tube;
and d) Assigning the exit port to a storage container and releasing the first lock element to pass the predefined quantity of activated irradiation targets in the discharge tube into the storage container;
wherein said separating step comprises supplying pressurized gas into the first discharge tube section through the at least one opening, thereby driving the another quantity of activated irradiation targets above the at least one opening from the first discharge tube section beyond the conjunction into the second discharge tube section, and keeping the predefined quantity of activated irradiation targets in the first discharge tube section.
Besides the pressurized gas used for portioning or rather separating the activated irradiation targets, a pneumatically operated drive system may be provided that is configured to insert the irradiation targets, for instance so-called aero-balls, into an instrumentation finger and to remove the irradiation targets, for instance the aero-balls, from the respective instrumentation finger after their activation.
BRIEF DESCRIPTION OF THE DRAWINGS
Further aspects and advantages of the invention will become more apparent from the following description of preferred embodiments and from the accompanying drawings wherein like elements are represented by like numerals. The preferred embodiments are given by way of illustration only and are not Date recue / Date received 2021-11-24
- an exit port assigned to a storage container of the irradiation target removal system;
- a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
In fact, the discharge tube according to the invention relates to the lower part of the irradiation target removal system described above.
In yet another aspect, the invention provides a method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor, wherein the method comprises the steps of:
a) Coupling at least one instrumentation finger of an instrumentation tube system to the irradiation target removal system as described above;
b) Passing the activated irradiation targets from the instrumentation finger into the discharge tube and blocking movement of the activated irradiation targets out of the discharge tube by means of the first lock element;
Date recue / Date received 2021-11-24 - 10a -c) Separating a predefined quantity of the activated irradiation targets from another quantity of the activated irradiation targets in the discharge tube;
and d) Assigning the exit port to a storage container and releasing the first lock element to pass the predefined quantity of activated irradiation targets in the discharge tube into the storage container;
wherein said separating step comprises supplying pressurized gas into the first discharge tube section through the at least one opening, thereby driving the another quantity of activated irradiation targets above the at least one opening from the first discharge tube section beyond the conjunction into the second discharge tube section, and keeping the predefined quantity of activated irradiation targets in the first discharge tube section.
Besides the pressurized gas used for portioning or rather separating the activated irradiation targets, a pneumatically operated drive system may be provided that is configured to insert the irradiation targets, for instance so-called aero-balls, into an instrumentation finger and to remove the irradiation targets, for instance the aero-balls, from the respective instrumentation finger after their activation.
BRIEF DESCRIPTION OF THE DRAWINGS
Further aspects and advantages of the invention will become more apparent from the following description of preferred embodiments and from the accompanying drawings wherein like elements are represented by like numerals. The preferred embodiments are given by way of illustration only and are not Date recue / Date received 2021-11-24
-11 -intended to limit the scope of the invention, which is apparent from the attached claims.
In the drawings:
- Figure 1 shows a schematic sketch of a radionuclide generation system setup according to the invention;
- Figure 2 shows a schematic sketch of an irradiation target removal system of the present invention;
- Figure 3 shows a close-up view of the first discharge tube section of an irradiation target removal system;
- Figure 4 shows the first discharge tube section of Figure 3 during separation of the irradiation targets;
- Figure 5 shows the first discharge tube section of Figure 3 after the separation of the irradiation targets while releasing the predefined quantity of activated irradiation targets;
- Figure 6 is a schematic sequence of the method according to the invention;
- Figure 7 shows another schematic sketch of a radionuclide generation system setup according to the invention; and - Figure 8 shows a close-up view of the first discharge tube section of another embodiment of the invention.
DETAILED DESCRIPTION OF PREFERRED EMBODIMENTS
The invention contemplates that a commercial nuclear reactor can be used for producing radionuclides. In particular, conventional aero-ball measuring systems or other instrumentation tube systems of the commercial reactor can be modified and/or supplemented to enable an effective and efficient production of radionuclides.
Some of the instrumentation tubes for example of a commercial Aero-ball Measuring System (AMS) or Traversing Incore Probe (TIP) system are used to guide the irradiation targets into the reactor core and to lead the activated
In the drawings:
- Figure 1 shows a schematic sketch of a radionuclide generation system setup according to the invention;
- Figure 2 shows a schematic sketch of an irradiation target removal system of the present invention;
- Figure 3 shows a close-up view of the first discharge tube section of an irradiation target removal system;
- Figure 4 shows the first discharge tube section of Figure 3 during separation of the irradiation targets;
- Figure 5 shows the first discharge tube section of Figure 3 after the separation of the irradiation targets while releasing the predefined quantity of activated irradiation targets;
- Figure 6 is a schematic sequence of the method according to the invention;
- Figure 7 shows another schematic sketch of a radionuclide generation system setup according to the invention; and - Figure 8 shows a close-up view of the first discharge tube section of another embodiment of the invention.
DETAILED DESCRIPTION OF PREFERRED EMBODIMENTS
The invention contemplates that a commercial nuclear reactor can be used for producing radionuclides. In particular, conventional aero-ball measuring systems or other instrumentation tube systems of the commercial reactor can be modified and/or supplemented to enable an effective and efficient production of radionuclides.
Some of the instrumentation tubes for example of a commercial Aero-ball Measuring System (AMS) or Traversing Incore Probe (TIP) system are used to guide the irradiation targets into the reactor core and to lead the activated
- 12 -irradiation targets out of the reactor core. The activation of the targets is optimized by positioning the irradiation targets in predetermined areas of the reactor core having a neutron flux sufficient for converting the parent material in the irradiation targets completely into the desired radionuclide(s).
The proper positioning of the irradiation targets may be achieved by means of dummy targets made of an inert material, preferably a magnetic material, and sequencing the dummy targets and the irradiation targets in the instrumentation tube system so as to form a column of the targets within the instrumentation finger.
In fact, the irradiation targets are at pre-calculated optimum axial positions in the reactor core and the other positions are occupied by the inert dummy targets or remain empty. However, it is preferred to use as many positions within the instrumentation fingers for irradiation targets instead of dummy targets to produce as much radionuclides as possible.
Figure 1 illustrates the basic setup of a radionuclide generation system 6 within a commercial nuclear power plant 8. As opposed to a research reactor, the purpose of a commercial nuclear reactor is the production of electrical power.
Commercial nuclear reactors typically have a power rating of 100+ Megawatt electric.
The basis of the radionuclide generation system 6 described in the example embodiments is derived from a conventional Aero-ball Measuring System (AMS) used to measure the neutron flux density in the core of the nuclear reactor, namely the reactor core 10.
A plurality of aero-balls are arranged in a linear order thereby forming an aero-ball column. The aero-balls are substantially spherical or round probes but can have other forms such as ellipsoids or cylinders, as long as they are capable of moving through the conduits of the instrumentation tube system.
The aero-ball measuring system includes a pneumatically operated drive system configured to insert the aero-balls into an instrumentation finger and to remove the aero-balls from the respective instrumentation finger after activation.
Typically, the instrumentation fingers extend into and pass the core 10 through its entire axial length.
The proper positioning of the irradiation targets may be achieved by means of dummy targets made of an inert material, preferably a magnetic material, and sequencing the dummy targets and the irradiation targets in the instrumentation tube system so as to form a column of the targets within the instrumentation finger.
In fact, the irradiation targets are at pre-calculated optimum axial positions in the reactor core and the other positions are occupied by the inert dummy targets or remain empty. However, it is preferred to use as many positions within the instrumentation fingers for irradiation targets instead of dummy targets to produce as much radionuclides as possible.
Figure 1 illustrates the basic setup of a radionuclide generation system 6 within a commercial nuclear power plant 8. As opposed to a research reactor, the purpose of a commercial nuclear reactor is the production of electrical power.
Commercial nuclear reactors typically have a power rating of 100+ Megawatt electric.
The basis of the radionuclide generation system 6 described in the example embodiments is derived from a conventional Aero-ball Measuring System (AMS) used to measure the neutron flux density in the core of the nuclear reactor, namely the reactor core 10.
A plurality of aero-balls are arranged in a linear order thereby forming an aero-ball column. The aero-balls are substantially spherical or round probes but can have other forms such as ellipsoids or cylinders, as long as they are capable of moving through the conduits of the instrumentation tube system.
The aero-ball measuring system includes a pneumatically operated drive system configured to insert the aero-balls into an instrumentation finger and to remove the aero-balls from the respective instrumentation finger after activation.
Typically, the instrumentation fingers extend into and pass the core 10 through its entire axial length.
- 13 -Referring to Figure 1, a commercial nuclear reactor comprises an instrumentation tube system 12 including at least one instrumentation finger
14 passing through the reactor core 10 of the nuclear reactor. The instrumentation tube system 12 is configured to permit insertion and removal of irradiation targets 16 and optionally magnetic or non-magnetic dummy targets 18 (cf. Fig. 2) into the instrumentation fingers 14.
The aero-ball measuring system of the commercial nuclear reactor is adapted to handle irradiation targets 16 having a round, cylindrical, elliptical or spherical shape and having a diameter corresponding to the clearance of the instrumentation finger 14 of the aero-ball measuring system. Preferably, the diameter of the targets 16, 18 is in the range of between 1 to 3 mm, preferably about 1.7 mm.
Conduits of the instrumentation tube system 12 penetrate an access barrier 11 of the reactor and are coupled to one or more instrumentation fingers 14.
Preferably, the instrumentation fingers 14 penetrate the pressure vessel cover of the nuclear reactor, with the instrumentation fingers 14 extending from the top to the bottom over substantially the entire axial length of the reactor core 10.
A
respective end of the instrumentation fingers 14 at the bottom of the reactor core 10 is closed and/or provided with a stop so that the irradiation targets 16 inserted into the instrumentation finger 14 form a column wherein each target 16 is at a predefined axial position.
According to a preferred embodiment, the commercial nuclear reactor is a pressurized water reactor. More preferably, the instrumentation tube system 12 is derived from a conventional aero-ball measuring system of a pressurized water reactor (PWR) such as an EPRTM or SiemensTM PWR nuclear reactor.
The person skilled in the art will however recognize that the invention is not limited to use of an aero-ball measuring system of a PWR reactor. Rather, it is also possible to use the instrumentation tubes of the Traversing Incore Probe (TIP) system of a boiling water reactor (BWR), the view ports of a CANDU reactor and temperature measurement and/or neutron flux channels in a heavy water reactor.
As shown in Figure 1, the instrumentation tube system 12 is connected to a target drive system 20 configured to insert the irradiation targets 16 and optionally dummy targets 18 into the instrumentation fingers 14 in a predetermined linear order and to force the irradiation targets 16 and dummy targets 18 out of the instrumentation finger 14 thereby retaining the linear order of the targets 16, 18.
Preferably, the dummy targets are magnetic.
Preferably, the target drive system 20 is pneumatically operated allowing for a fast processing of the irradiation targets 16 and optionally the dummy targets using pressurized gas such as nitrogen or air.
The target drive system 20 cooperates with an irradiation target removal system 22 configured to receive activated irradiation targets 16 and optionally dummy targets 18 from the instrumentation tube system 12 and pass a predefined quantity 16 of the activated irradiation targets 16 into a shielded storage container 34 (c.f. Figure 2). The irradiation target removal system 22 will be described in greater detail below, with reference to Figure 2.
With further reference to Figure 1, an instrumentation and control unit (ICU) is connected to the target drive system 20 and the irradiation target removal system 22 as well as an online core monitoring system 26 for controlling activation of the irradiation targets 16. Preferably, the ICU 24 is also connected to a fault monitoring system 28 of the aero-ball measuring system for reporting any errors.
The fault monitoring system 28 may also be designed without connection to the existing aero-ball measuring system, but be connected directly to a main control room.
According to an embodiment, the core monitoring system 26 and the instrumentation and control unit 24 are configured such that the activation process for converting the irradiation targets 16 to the desired radionuclide is optimized by considering the actual state of the reactor, especially the current neutron flux, fuel burn-up, reactor power and/or loading. Thus, an optimum axial irradiation position and irradiation time can be calculated for optimum results. It is however not important whether the actual calculation is performed in the ICU 24 or by the core monitoring system 26 of the aero-ball measuring system.
The irradiation targets 16 are made of non-fissile material and comprise a suitable precursor material for generating radionuclides, which are to be used for medical and/or other purposes. More preferably, the irradiation targets 16 consist of the precursor material, which converts to a desired radionuclide upon activating
The aero-ball measuring system of the commercial nuclear reactor is adapted to handle irradiation targets 16 having a round, cylindrical, elliptical or spherical shape and having a diameter corresponding to the clearance of the instrumentation finger 14 of the aero-ball measuring system. Preferably, the diameter of the targets 16, 18 is in the range of between 1 to 3 mm, preferably about 1.7 mm.
Conduits of the instrumentation tube system 12 penetrate an access barrier 11 of the reactor and are coupled to one or more instrumentation fingers 14.
Preferably, the instrumentation fingers 14 penetrate the pressure vessel cover of the nuclear reactor, with the instrumentation fingers 14 extending from the top to the bottom over substantially the entire axial length of the reactor core 10.
A
respective end of the instrumentation fingers 14 at the bottom of the reactor core 10 is closed and/or provided with a stop so that the irradiation targets 16 inserted into the instrumentation finger 14 form a column wherein each target 16 is at a predefined axial position.
According to a preferred embodiment, the commercial nuclear reactor is a pressurized water reactor. More preferably, the instrumentation tube system 12 is derived from a conventional aero-ball measuring system of a pressurized water reactor (PWR) such as an EPRTM or SiemensTM PWR nuclear reactor.
The person skilled in the art will however recognize that the invention is not limited to use of an aero-ball measuring system of a PWR reactor. Rather, it is also possible to use the instrumentation tubes of the Traversing Incore Probe (TIP) system of a boiling water reactor (BWR), the view ports of a CANDU reactor and temperature measurement and/or neutron flux channels in a heavy water reactor.
As shown in Figure 1, the instrumentation tube system 12 is connected to a target drive system 20 configured to insert the irradiation targets 16 and optionally dummy targets 18 into the instrumentation fingers 14 in a predetermined linear order and to force the irradiation targets 16 and dummy targets 18 out of the instrumentation finger 14 thereby retaining the linear order of the targets 16, 18.
Preferably, the dummy targets are magnetic.
Preferably, the target drive system 20 is pneumatically operated allowing for a fast processing of the irradiation targets 16 and optionally the dummy targets using pressurized gas such as nitrogen or air.
The target drive system 20 cooperates with an irradiation target removal system 22 configured to receive activated irradiation targets 16 and optionally dummy targets 18 from the instrumentation tube system 12 and pass a predefined quantity 16 of the activated irradiation targets 16 into a shielded storage container 34 (c.f. Figure 2). The irradiation target removal system 22 will be described in greater detail below, with reference to Figure 2.
With further reference to Figure 1, an instrumentation and control unit (ICU) is connected to the target drive system 20 and the irradiation target removal system 22 as well as an online core monitoring system 26 for controlling activation of the irradiation targets 16. Preferably, the ICU 24 is also connected to a fault monitoring system 28 of the aero-ball measuring system for reporting any errors.
The fault monitoring system 28 may also be designed without connection to the existing aero-ball measuring system, but be connected directly to a main control room.
According to an embodiment, the core monitoring system 26 and the instrumentation and control unit 24 are configured such that the activation process for converting the irradiation targets 16 to the desired radionuclide is optimized by considering the actual state of the reactor, especially the current neutron flux, fuel burn-up, reactor power and/or loading. Thus, an optimum axial irradiation position and irradiation time can be calculated for optimum results. It is however not important whether the actual calculation is performed in the ICU 24 or by the core monitoring system 26 of the aero-ball measuring system.
The irradiation targets 16 are made of non-fissile material and comprise a suitable precursor material for generating radionuclides, which are to be used for medical and/or other purposes. More preferably, the irradiation targets 16 consist of the precursor material, which converts to a desired radionuclide upon activating
- 15 -by exposure to neutron flux present in the reactor core 10 of an operating commercial nuclear reactor. Useful precursor materials are Mo-98, Yb-176 and Lu-176, which are converted to Mo-99 and Lu-177, respectively. It is understood, however, that the invention is not limited to the use of a specific precursor material.
The optional dummy targets 18 are made of an inert material, which is not substantially activated under the conditions in the reactor core 10 of an operating nuclear reactor. Preferably, the dummy targets 18 can be made of inexpensive inert materials and can be re-used after a short decay time so that the amount of radioactive waste is further reduced. More preferably, the dummy targets are magnetic.
For use in a conventional aero-ball measuring system, the irradiation targets
The optional dummy targets 18 are made of an inert material, which is not substantially activated under the conditions in the reactor core 10 of an operating nuclear reactor. Preferably, the dummy targets 18 can be made of inexpensive inert materials and can be re-used after a short decay time so that the amount of radioactive waste is further reduced. More preferably, the dummy targets are magnetic.
For use in a conventional aero-ball measuring system, the irradiation targets
16 and the dummy targets 18 have a round shape, preferably a spherical or cylindrical shape, so that the targets 16, 18 may slide smoothly through and can be easily guided in the instrumentation tube system 12 of the aero-ball measuring system by pressurized gas, such as air or nitrogen, and/or under the action of gravity.
The irradiation target removal system 22 of the present invention is schematically shown in more detail in Figure 2.
A discharge tube 30 is connected to the instrumentation finger 14 through aero-ball conduits of the instrumentation tube system 12. The discharge tube 30 is configured to receive the irradiation targets 16 driven out of the instrumentation finger 14 after activation is completed. The linear order of the irradiation targets 16 and/or the dummy targets 18 is retained in the discharge tube 30. Preferably, the discharge tube 30 is located outside the reactor core 10, but within accessible areas inside the reactor containment.
The discharge tube 30 has an exit port 32, which is assigned to at least one storage container 34, 34' for receiving the activated irradiation targets 16 from the instrumentation finger 14. The exit port 32 can be positioned above the assigned storage container 34 to be filled, or can be coupled and/or removably connected to the assigned storage container 34. The at least one storage container 34, 34' preferably has a shielding to minimize an operator's exposure to radiation from the activated irradiation targets 16.
A first lock element 36 is provided in the discharge tube 30 for blocking movement of the activated irradiation targets 16 to the storage container 34, 34'.
The first lock element 36 can be a magnetically or mechanically operated restriction element, preferably a pin crossing the discharge tube 30.
Referring to Figure 2, the discharge tube 30 comprises a first discharge tube section 38, a second discharge tube section 40 and an apex 42 formed at a conjunction of the first and second discharge tube section 38, 40. The apex 42 is the highest point of the discharge tube 30. The first and second discharge tube sections 38, 40 are directed downwardly from the apex 42.
The exit port 32 is arranged at a free end of the first discharge tube section 38, opposed to the apex 42, and the second discharge tube section 40 is coupled to the instrumentation tube system 12. The exit port 32 comprises a stop valve 44 for pressure-tight sealing the discharge tube 30.
In the shown embodiment, a set of openings 46 is provided circumferentially at the first discharge tube section 38 between the first lock element 36 and the apex 42, namely the conjunction. Particularly, the openings 46 are realized by boreholes that were drilled into the first discharge tube section 38. The set of openings 46 is surrounded by a pressure-tight encapsulation 48, which is connected by a 212 control valve 50 to a supply 52 of pressurized gas.
Preferably, air or nitrogen is used as pressurized gas. The pressurized gas can be supplied from the target drive system 20.
Even though a set of openings 46 is provided in the shown embodiment, a single opening 461s also sufficient to be connected to the supply 52, as will become apparent hereinafter.
In the embodiment shown in Figure 2, the first discharge tube section 38, the second discharge tube section 40 and the apex 42 at the conjunction of both tube sections 38, 40 are shaped in the form of an inverse U.
Other profiles of the discharge tube 30 are also possible.
Preferably, an apex 42 is formed between the first and second discharge tube section 38, 40, which has a radius that is sufficiently small to effectively separate
The irradiation target removal system 22 of the present invention is schematically shown in more detail in Figure 2.
A discharge tube 30 is connected to the instrumentation finger 14 through aero-ball conduits of the instrumentation tube system 12. The discharge tube 30 is configured to receive the irradiation targets 16 driven out of the instrumentation finger 14 after activation is completed. The linear order of the irradiation targets 16 and/or the dummy targets 18 is retained in the discharge tube 30. Preferably, the discharge tube 30 is located outside the reactor core 10, but within accessible areas inside the reactor containment.
The discharge tube 30 has an exit port 32, which is assigned to at least one storage container 34, 34' for receiving the activated irradiation targets 16 from the instrumentation finger 14. The exit port 32 can be positioned above the assigned storage container 34 to be filled, or can be coupled and/or removably connected to the assigned storage container 34. The at least one storage container 34, 34' preferably has a shielding to minimize an operator's exposure to radiation from the activated irradiation targets 16.
A first lock element 36 is provided in the discharge tube 30 for blocking movement of the activated irradiation targets 16 to the storage container 34, 34'.
The first lock element 36 can be a magnetically or mechanically operated restriction element, preferably a pin crossing the discharge tube 30.
Referring to Figure 2, the discharge tube 30 comprises a first discharge tube section 38, a second discharge tube section 40 and an apex 42 formed at a conjunction of the first and second discharge tube section 38, 40. The apex 42 is the highest point of the discharge tube 30. The first and second discharge tube sections 38, 40 are directed downwardly from the apex 42.
The exit port 32 is arranged at a free end of the first discharge tube section 38, opposed to the apex 42, and the second discharge tube section 40 is coupled to the instrumentation tube system 12. The exit port 32 comprises a stop valve 44 for pressure-tight sealing the discharge tube 30.
In the shown embodiment, a set of openings 46 is provided circumferentially at the first discharge tube section 38 between the first lock element 36 and the apex 42, namely the conjunction. Particularly, the openings 46 are realized by boreholes that were drilled into the first discharge tube section 38. The set of openings 46 is surrounded by a pressure-tight encapsulation 48, which is connected by a 212 control valve 50 to a supply 52 of pressurized gas.
Preferably, air or nitrogen is used as pressurized gas. The pressurized gas can be supplied from the target drive system 20.
Even though a set of openings 46 is provided in the shown embodiment, a single opening 461s also sufficient to be connected to the supply 52, as will become apparent hereinafter.
In the embodiment shown in Figure 2, the first discharge tube section 38, the second discharge tube section 40 and the apex 42 at the conjunction of both tube sections 38, 40 are shaped in the form of an inverse U.
Other profiles of the discharge tube 30 are also possible.
Preferably, an apex 42 is formed between the first and second discharge tube section 38, 40, which has a radius that is sufficiently small to effectively separate
- 17 -the target columns in the first and second tube sections 38, 40 from each other in a first separation step.
The operation of the irradiation target removal system 22 of the invention is now described in greater detail.
Irradiation targets 16, which are activated in the instrumentation finger(s) 14 for a period of time sufficient to convert the irradiation targets 16 into the desired radionuclide(s), are driven out of the instrumentation finger(s) 14 into the instrumentation tube system 12 using pressurized gas such as air or nitrogen supplied from the target drive system 20.
The discharge tube 30 is coupled to conduits of the instrumentation tube system 12 for receiving the irradiation targets 16 (step S1 in Figure 6). A
gate system (not shown) such as a three-way valve can be used to guide the irradiation targets 16 into the discharge tube 30 of the irradiation target removal system 22.
The linear order of the irradiation targets 16 in the instrumentation finger(s) 14 is preserved in the discharge tube 30.
At this time, as shown in Figure 3, access to the exit port 32 of the discharge tube 30 is blocked by the first lock element 36, providing a stop for the activated irradiation targets 16 and preventing the targets 16 from leaving the discharge tube 30 (step 82 in Figure 6).
Typically, there are so many irradiation targets 16 within the discharge tube 30, that they pile up until a level above the set of openings 46. In this case, a predefined quantity 16' of the activated irradiation targets 16 can be separated from another quantity 16" of the activated irradiation targets 16 in the discharge tube 30 (step S3 in Figure 6).
For this purpose, pressurized gas is supplied into the first discharge tube section 38 through the at least one opening 46, particularly the set of openings 46.
This drives the another quantity 16" of activated irradiation targets 16 above the at least one opening 46 from the first discharge tube section 38 beyond the conjunction of the first and second discharge tube sections 38, 40, namely the apex 42 in the shown embodiment, into the second discharge tube section 40 (as indicated by the arrows in Figure 4).
The operation of the irradiation target removal system 22 of the invention is now described in greater detail.
Irradiation targets 16, which are activated in the instrumentation finger(s) 14 for a period of time sufficient to convert the irradiation targets 16 into the desired radionuclide(s), are driven out of the instrumentation finger(s) 14 into the instrumentation tube system 12 using pressurized gas such as air or nitrogen supplied from the target drive system 20.
The discharge tube 30 is coupled to conduits of the instrumentation tube system 12 for receiving the irradiation targets 16 (step S1 in Figure 6). A
gate system (not shown) such as a three-way valve can be used to guide the irradiation targets 16 into the discharge tube 30 of the irradiation target removal system 22.
The linear order of the irradiation targets 16 in the instrumentation finger(s) 14 is preserved in the discharge tube 30.
At this time, as shown in Figure 3, access to the exit port 32 of the discharge tube 30 is blocked by the first lock element 36, providing a stop for the activated irradiation targets 16 and preventing the targets 16 from leaving the discharge tube 30 (step 82 in Figure 6).
Typically, there are so many irradiation targets 16 within the discharge tube 30, that they pile up until a level above the set of openings 46. In this case, a predefined quantity 16' of the activated irradiation targets 16 can be separated from another quantity 16" of the activated irradiation targets 16 in the discharge tube 30 (step S3 in Figure 6).
For this purpose, pressurized gas is supplied into the first discharge tube section 38 through the at least one opening 46, particularly the set of openings 46.
This drives the another quantity 16" of activated irradiation targets 16 above the at least one opening 46 from the first discharge tube section 38 beyond the conjunction of the first and second discharge tube sections 38, 40, namely the apex 42 in the shown embodiment, into the second discharge tube section 40 (as indicated by the arrows in Figure 4).
- 18 -The another quantity 16" of activated irradiation targets 16 is driven into the second discharge tube section 40 that may be populated by a third quantity 16¨
of activated irradiation targets 16. Then, the third quantity 16" of activated irradiation targets 16 is driven out of the second discharge tube section 40 by the pressurized gas. Alternatively or additionally, the another quantity 16" of activated irradiation targets 16 is also driven out of the second discharge tube section 40_ For instance, an intermediate storage is provided ensuring that the another quantity 16" of activated irradiation targets 16 and/or the third quantity 16¨
of activated irradiation targets 16 are/is not driven back into the reactor core 10.
Finally, the first lock element 36 and the stop valve 44 are released and the predefined quantity 16' of the activated irradiation targets 16, which is still located within the first discharge tube section 38, can pass under the action of gravity into the storage container 34 assigned to the exit port 32 (as shown in Figure 5 and step S4 in Figure 6).
After collecting the predefined quantity 16' of the activated irradiation targets 16, the stop valve 44 at the exit port 32 is closed for providing a pressure-tight sealing of the exit port 32 and the discharge tube 30, and the shielded storage container 34 is then removed either manually or by means of an automated handling device.
The above process steps can then be repeated for portioning and harvesting a further quantity of activated irradiation targets 16 until all of the activated irradiation targets 16 have been removed from the instrumentation tube system 12. The system is then ready for starting a new radionuclide generation cycle.
A further embodiment of the radionuclide generation system is presented in Figure 7.
For same parts, the same numerals are used as in the embodiments presented above_ The same features and advantages of the equivalent parts apply here, too.
In this embodiment, the first discharge tube section 38 exhibits a first set of openings 46 surrounded by a first pressure-tight encapsulation 48 and a second set of openings 46' surrounded by a second pressure-tight encapsulation 48'.
Each
of activated irradiation targets 16. Then, the third quantity 16" of activated irradiation targets 16 is driven out of the second discharge tube section 40 by the pressurized gas. Alternatively or additionally, the another quantity 16" of activated irradiation targets 16 is also driven out of the second discharge tube section 40_ For instance, an intermediate storage is provided ensuring that the another quantity 16" of activated irradiation targets 16 and/or the third quantity 16¨
of activated irradiation targets 16 are/is not driven back into the reactor core 10.
Finally, the first lock element 36 and the stop valve 44 are released and the predefined quantity 16' of the activated irradiation targets 16, which is still located within the first discharge tube section 38, can pass under the action of gravity into the storage container 34 assigned to the exit port 32 (as shown in Figure 5 and step S4 in Figure 6).
After collecting the predefined quantity 16' of the activated irradiation targets 16, the stop valve 44 at the exit port 32 is closed for providing a pressure-tight sealing of the exit port 32 and the discharge tube 30, and the shielded storage container 34 is then removed either manually or by means of an automated handling device.
The above process steps can then be repeated for portioning and harvesting a further quantity of activated irradiation targets 16 until all of the activated irradiation targets 16 have been removed from the instrumentation tube system 12. The system is then ready for starting a new radionuclide generation cycle.
A further embodiment of the radionuclide generation system is presented in Figure 7.
For same parts, the same numerals are used as in the embodiments presented above_ The same features and advantages of the equivalent parts apply here, too.
In this embodiment, the first discharge tube section 38 exhibits a first set of openings 46 surrounded by a first pressure-tight encapsulation 48 and a second set of openings 46' surrounded by a second pressure-tight encapsulation 48'.
Each
- 19 -of the encapsulations 48, 48' is connected by a 2/2 control valve 50, 50' to a supply 52, 52' of pressurized gas.
In the shown embodiment, the control valves 50, 50' and the supplies 52, 52' of pressurized gas are independent of each other. However, they could also be a single control valve 50 connected to a single supply 52.
The first and second sets of openings 46, 46' are located at different heights of the first discharge tube section 38. Additionally, the height difference of the first to the second set of openings 46, 46' is different to the height difference between the first set of openings 46 and the first lock element 36. In this way, dependent on at which height pressurized gas is applied in step S3 (c.f. Figure 6), different quantities of activated irradiation targets 16 can be kept in the first discharge tube section 38 and afterwards transferred to the storage container 34.
Therefore, when several times a predefined amount of activated irradiation targets 16 are collected, it is possible to first collect an amount corresponding to the height difference between the first lock element 36 and the first set of openings 46 and afterwards a second amount corresponding to the height difference between first lock element 36 and the second set of openings 46'.
Additionally, in this embodiment a second lock element 54 is located in a pathway 56 originating from the instrumentation tube system 12. In fact, the pathway 56 connects the second discharge tube section 40 and the instrumentation tube system 12.
The second lock element 54 prevents irradiation targets 16, which are pushed out of the discharge tube 30, to flow back into the instrumentation fingers 14 of the nuclear reactor, particularly the reactor core 10.
It is also possible that the pathway 56 exhibits further junctions to additional tubes to which the irradiation targets 16 can be transferred during the separating step S3 of Figure 6.
In another embodiment shown in Fig. 8, cartridges 58 are used that are assigned to the irradiation targets 16. Otherwise, the radionuclide generation system 6 exhibits the same components as described in respect to the other embodiments and like numerals are used for referencing like parts.
In the shown embodiment, the control valves 50, 50' and the supplies 52, 52' of pressurized gas are independent of each other. However, they could also be a single control valve 50 connected to a single supply 52.
The first and second sets of openings 46, 46' are located at different heights of the first discharge tube section 38. Additionally, the height difference of the first to the second set of openings 46, 46' is different to the height difference between the first set of openings 46 and the first lock element 36. In this way, dependent on at which height pressurized gas is applied in step S3 (c.f. Figure 6), different quantities of activated irradiation targets 16 can be kept in the first discharge tube section 38 and afterwards transferred to the storage container 34.
Therefore, when several times a predefined amount of activated irradiation targets 16 are collected, it is possible to first collect an amount corresponding to the height difference between the first lock element 36 and the first set of openings 46 and afterwards a second amount corresponding to the height difference between first lock element 36 and the second set of openings 46'.
Additionally, in this embodiment a second lock element 54 is located in a pathway 56 originating from the instrumentation tube system 12. In fact, the pathway 56 connects the second discharge tube section 40 and the instrumentation tube system 12.
The second lock element 54 prevents irradiation targets 16, which are pushed out of the discharge tube 30, to flow back into the instrumentation fingers 14 of the nuclear reactor, particularly the reactor core 10.
It is also possible that the pathway 56 exhibits further junctions to additional tubes to which the irradiation targets 16 can be transferred during the separating step S3 of Figure 6.
In another embodiment shown in Fig. 8, cartridges 58 are used that are assigned to the irradiation targets 16. Otherwise, the radionuclide generation system 6 exhibits the same components as described in respect to the other embodiments and like numerals are used for referencing like parts.
-20 -By using the cartridges 58, the precursor materials and produced radionuclides do not need to be able to form stable spheroids, which can withstand the forces occurring in the radionuclide generation system 6. Only the cartridges 58 housing one or more of the irradiation targets 16 need to be stable enough to be transported from the instrumentation fingers 14 into the discharge tube 30.
Claims (14)
1. An irradiation target removal system comprising:
at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor;
a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube sections; and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises:
- an exit port assigned to the storage container;
- a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and - at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening;
and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
at least one storage container for receiving activated irradiation targets from an instrumentation tube system of a nuclear reactor;
a discharge tube comprising a first discharge tube section, a second discharge tube section and a conjunction of the first and second discharge tube sections; and a supply of pressurized gas connected to the first discharge tube section for pressurizing the discharge tube;
wherein the second discharge tube section is coupled to the instrumentation tube system, and wherein the first discharge tube section comprises:
- an exit port assigned to the storage container;
- a first lock element for blocking movement of the activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and the conjunction; and - at least one opening located between the first lock element and the conjunction, wherein the supply of pressurized gas is connected to the at least one opening;
and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
2. The irradiation target removal system according to claim 1, wherein an apex is formed at the conjunction of the first and second discharge tube sections, wherein the first and second discharge tube sections are directed downwardly from the apex, wherein the first lock element is located between the exit port and the apex, and wherein the at least one opening is located between the first lock element and the apex.
Date revue / Date received 2021-11-24
Date revue / Date received 2021-11-24
3. The irradiation target removal system according to claim 1, wherein the at least one opening comprises a set of openings provided at the first discharge tube section circumferentially at the same height.
4. The irradiation target removal system according to any one of claims 1 to 3, wherein the pressurized gas supply comprises a control valve.
5. The irradiation target removal system according to claim 4, wherein the control valve is a 2/2 control valve.
6. The irradiation target removal system according to any one of claims 1 to 5, wherein the at least one opening is contained in a pressure-tight encapsulation.
7. The irradiation target removal system according to any one of claims 1 to 6, wherein a second lock element is located in a pathway originating from the instrumentation tube system.
8. The irradiation target removal system according to any one of claims 1 to 7, wherein two or more sets of openings are provided at different heights of the first discharge tube section, and wherein each set of openings is connected to the pressurized gas supply.
9. The irradiation target removal system according to claim 8, wherein the distance between the first lock element and a first set of openings is different to the distance between the first and a second set of openings.
10. The irradiation target removal system according to any one of claims 1 to 9, wherein at least one cartridge is provided that is assigned to the irradiation targets, the cartridge containing a radionuclide precursor material.
11. A radionuclide generation system comprising an irradiation target removal system according to any one of claims 1 to 10.
12. A discharge tube for an irradiation target removal system, the discharge tube comprising at least a first discharge tube section that comprises:
Date revue / Date received 2021-11-24 - an exit port assigned to a storage container of the irradiation target removal system;
- a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
Date revue / Date received 2021-11-24 - an exit port assigned to a storage container of the irradiation target removal system;
- a first lock element for blocking movement of activated irradiation targets to the storage container, wherein the first lock element is located between the exit port and a connecting port to an instrumentation tube system of the irradiation target removal system; and - at least one opening located between the first lock element and the connecting port, wherein the at least one opening is configured to provide an interface for a supply of pressurized gas; and wherein the exit port comprises a stop valve for pressure-tightly sealing the exit port.
13. The discharge tube according to claim 12, wherein the discharge tube is for an irradiation target removal system according to any of claims 1 to 10.
14. A method for removing activated irradiation targets from an instrumentation tube system of a nuclear reactor, wherein the method comprises the steps of:
a) Coupling at least one instrumentation finger of an instrumentation tube system to an irradiation target removal system according to any one of claims 1 to 10;
b) Passing the activated irradiation targets from the instrumentation finger into the discharge tube and blocking movement of the activated irradiation targets out of the discharge tube by means of the first lock element;
c) Separating a predefined quantity of the activated irradiation targets from another quantity of the activated irradiation targets in the discharge tube;
and d) Assigning the exit port to a storage container and releasing the first lock element to pass the predefined quantity of activated irradiation targets in the discharge tube into the storage container;
Date recue / Date received 2021-11-24 wherein said separating step comprises supplying pressurized gas into the first discharge tube section through the at least one opening, thereby driving the another quantity of activated irradiation targets above the at least one opening from the first discharge tube section beyond the conjunction into the second discharge tube section, and keeping the predefined quantity of activated irradiation targets in the first discharge tube section.
a) Coupling at least one instrumentation finger of an instrumentation tube system to an irradiation target removal system according to any one of claims 1 to 10;
b) Passing the activated irradiation targets from the instrumentation finger into the discharge tube and blocking movement of the activated irradiation targets out of the discharge tube by means of the first lock element;
c) Separating a predefined quantity of the activated irradiation targets from another quantity of the activated irradiation targets in the discharge tube;
and d) Assigning the exit port to a storage container and releasing the first lock element to pass the predefined quantity of activated irradiation targets in the discharge tube into the storage container;
Date recue / Date received 2021-11-24 wherein said separating step comprises supplying pressurized gas into the first discharge tube section through the at least one opening, thereby driving the another quantity of activated irradiation targets above the at least one opening from the first discharge tube section beyond the conjunction into the second discharge tube section, and keeping the predefined quantity of activated irradiation targets in the first discharge tube section.
Applications Claiming Priority (1)
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| CN113571213B (en) * | 2021-06-23 | 2024-03-22 | 中国原子能科学研究院 | Method for detecting neptunium target integrity in irradiation process |
| CN115064295B (en) * | 2022-06-07 | 2024-05-10 | 上海核工程研究设计院股份有限公司 | System and method for producing radioisotope by using heavy water reactor nuclear power station |
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| EP3973548A1 (en) | 2022-03-30 |
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