WO2020233814A1 - Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides. - Google Patents

Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides. Download PDF

Info

Publication number
WO2020233814A1
WO2020233814A1 PCT/EP2019/063328 EP2019063328W WO2020233814A1 WO 2020233814 A1 WO2020233814 A1 WO 2020233814A1 EP 2019063328 W EP2019063328 W EP 2019063328W WO 2020233814 A1 WO2020233814 A1 WO 2020233814A1
Authority
WO
WIPO (PCT)
Prior art keywords
discharge tube
targets
irradiation
irradiation targets
instrumentation
Prior art date
Application number
PCT/EP2019/063328
Other languages
English (en)
Inventor
Alexander SYKORA
Original Assignee
Framatome Gmbh
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Framatome Gmbh filed Critical Framatome Gmbh
Priority to BR112021022587A priority Critical patent/BR112021022587A2/pt
Priority to KR1020217036938A priority patent/KR102716583B1/ko
Priority to EP19727970.6A priority patent/EP3973548A1/fr
Priority to CA3136561A priority patent/CA3136561C/fr
Priority to PCT/EP2019/063328 priority patent/WO2020233814A1/fr
Priority to CN201980096559.XA priority patent/CN113892152B/zh
Publication of WO2020233814A1 publication Critical patent/WO2020233814A1/fr

Links

Classifications

    • 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
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C23/00—Adaptations of reactors to facilitate experimentation or irradiation
    • 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

Definitions

  • 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.
  • 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.
  • 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. 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.
  • 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 A1 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 A1 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 in the instrumentation tube system and release the other one of the activated irradiation target or the dummy target from the instrumentation tube system.
  • the dummy targets and the activated irradiation targets have different magnetic properties.
  • WO 2017/012655 A1 describes a method for harvesting activated irradiation targets from an instrumentation tube system of a nuclear reactor.
  • 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.
  • 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.
  • 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.
  • the size of the available and needed storage containers is often not big enough to incorporate the given quantity of activated irradiation targets.
  • 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.
  • 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.
  • 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”).
  • 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.
  • 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.
  • the at least one opening relates to a borehole that is drilled into the first discharge tube section.
  • already existing discharge tubes can be used.
  • 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.
  • 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.
  • 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 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.
  • 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.
  • 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.
  • 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 at least one opening can comprise a set of openings provided at the first discharge tube section circumferentially at the same height.
  • 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.
  • a set of boreholes is drilled into the first discharged tube section circumferentially at the same height.
  • 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.
  • 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.
  • a second lock element can be located in a pathway originating from the instrumentation tube system.
  • the second lock element is located in a pathway connecting the second discharge tube section and the instrumentation tube system.
  • 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.
  • 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.
  • 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.
  • 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.
  • 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.
  • at least one cartridge is provided that is assigned to the irradiation targets, the cartridge containing a radionuclide precursor material.
  • the cartridge comprises a housing containing one or more irradiation targets.
  • 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.
  • 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.
  • the cartridge 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.
  • the invention provides a radionuclide generation system comprising an irradiation target removal system as described above.
  • 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.
  • the discharge tube according to the invention relates to the lower part of the irradiation target removal system described above.
  • 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; 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
  • 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.
  • FIG. 1 shows a schematic sketch of a radionuclide generation system setup according to the invention
  • FIG. 2 shows a schematic sketch of an irradiation target removal system of the present invention
  • FIG. 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
  • FIG. 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.
  • FIG. 7 shows another schematic sketch of a radionuclide generation system setup according to the invention.
  • the invention contemplates that a commercial nuclear reactor can be used for producing radionuclides.
  • 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.
  • 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 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.
  • 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.
  • Figure 1 illustrates the basic setup of a radionuclide generation system 6 within a commercial nuclear power plant 8.
  • 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.
  • AMS Aero-ball Measuring System
  • 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.
  • 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.
  • 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 1 1 of the reactor and are coupled to one or more instrumentation fingers 14.
  • 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.
  • the commercial nuclear reactor is a pressurized water reactor.
  • 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.
  • PWR pressurized water reactor
  • 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.
  • TIP Traversing Incore Probe
  • BWR boiling water reactor
  • 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.
  • the dummy targets are magnetic.
  • the target drive system 20 is pneumatically operated allowing for a fast processing of the irradiation targets 16 and optionally the dummy targets 18 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.
  • an instrumentation and control unit (ICU) 24 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.
  • 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.
  • 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.
  • 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 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.
  • 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.
  • 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.
  • pressurized gas such as air or nitrogen
  • 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.
  • 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.
  • 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.
  • 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 2/2 control valve 50 to a supply 52 of pressurized gas.
  • pressurized gas Preferably, air or nitrogen is used as pressurized gas.
  • the pressurized gas can be supplied from the target drive system 20.
  • 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.
  • 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 target columns in the first and second tube sections 38, 40 from each other in a first separation step.
  • 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 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.
  • 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).
  • pressurized gas is supplied into the first discharge tube section 38 through the at least one opening 46, particularly the set of openings 46.
  • 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.
  • the third quantity 16’” of activated irradiation targets 16 is driven out of the second discharge tube section 40 by the pressurized gas.
  • the another quantity 16” of activated irradiation targets 16 is also driven out of the second discharge tube section 40.
  • 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.
  • 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 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 the encapsulations 48, 48’ is connected by a 2/2 control valve 50, 50’ to a supply 52, 52’ of pressurized gas.
  • 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.
  • a second lock element 54 is located in a pathway 56 originating from the instrumentation tube system 12.
  • 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.
  • 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.
  • 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.
  • 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.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Particle Accelerators (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

L'invention concerne un système d'élimination de cible d'irradiation qui comprend au moins un récipient de stockage (34) destiné à recevoir des cibles d'irradiation activées (16) à partir d'un système de tube d'instrumentation (12) d'un réacteur nucléaire ; un tube de décharge (30) comprenant une première section de tube de décharge (38), une seconde section de tube de décharge (40) et une jonction des première et seconde sections de tube de décharge (38, 40) ; et une alimentation (52) en gaz sous pression reliée à la première section de tube de décharge (38) pour mettre sous pression le tube de décharge (30). La seconde section de tube de décharge (40) est couplée au système de tube d'instrumentation (12), la première section de tube de décharge (38) comprenant un orifice de sortie (32) associé au récipient de stockage (34) ; un premier élément de verrouillage (36) destiné à empêcher le mouvement des cibles d'irradiation activées (16) vers le récipient de stockage (34), le premier élément de verrouillage (36) étant situé entre l'orifice de sortie (32) et la jonction ; et au moins une ouverture (46) située entre le premier élément de verrouillage (36) et la jonction, l'alimentation (52) en gaz sous pression étant reliée à ladite ouverture (46). En outre, l'invention concerne un système de génération de radio-isotopes, un tube de décharge et un procédé d'élimination de cibles d'irradiation activées à partir d'un système de tube d'instrumentation d'un réacteur nucléaire.
PCT/EP2019/063328 2019-05-23 2019-05-23 Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides. WO2020233814A1 (fr)

Priority Applications (6)

Application Number Priority Date Filing Date Title
BR112021022587A BR112021022587A2 (pt) 2019-05-23 2019-05-23 Sistema de remoção de alvo de irradiação, sistema de geração de radionuclídeo, tubo de descarga e método para remover alvos de irradiação ativados
KR1020217036938A KR102716583B1 (ko) 2019-05-23 2019-05-23 원자로로부터의 조사 타겟을 제거하기 위한 시스템 및 방법, 및 방사성 핵종 생성 시스템
EP19727970.6A EP3973548A1 (fr) 2019-05-23 2019-05-23 Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides
CA3136561A CA3136561C (fr) 2019-05-23 2019-05-23 Systemes et procedes d'elimination de cibles d'irradiations presentes dans un reacteur nucleaire et systeme de generation de radionucleides.
PCT/EP2019/063328 WO2020233814A1 (fr) 2019-05-23 2019-05-23 Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides.
CN201980096559.XA CN113892152B (zh) 2019-05-23 2019-05-23 从核反应堆和放射性核素生成系统中移除辐照靶的系统和方法

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/EP2019/063328 WO2020233814A1 (fr) 2019-05-23 2019-05-23 Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides.

Publications (1)

Publication Number Publication Date
WO2020233814A1 true WO2020233814A1 (fr) 2020-11-26

Family

ID=66690322

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP2019/063328 WO2020233814A1 (fr) 2019-05-23 2019-05-23 Systèmes et procédés d'élimination de cibles d'irradiations présentes dans un réacteur nucléaire et système de génération de radionucléides.

Country Status (6)

Country Link
EP (1) EP3973548A1 (fr)
KR (1) KR102716583B1 (fr)
CN (1) CN113892152B (fr)
BR (1) BR112021022587A2 (fr)
CA (1) CA3136561C (fr)
WO (1) WO2020233814A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2022086433A (ja) * 2020-11-30 2022-06-09 三菱重工業株式会社 放射性同位体の製造装置および放射性同位体の製造方法

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113571213B (zh) * 2021-06-23 2024-03-22 中国原子能科学研究院 一种用于辐照过程中镎靶件完整性的检测方法
CN115064295B (zh) * 2022-06-07 2024-05-10 上海核工程研究设计院股份有限公司 一种利用重水堆核电站生产放射性同位素的系统和方法

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2093773A2 (fr) 2008-02-21 2009-08-26 GE-Hitachi Nuclear Energy Americas LLC Appareil et procédés de production de radio-isotopes dans des tubes d'instrumentation de réacteur nucléaire
WO2016173664A1 (fr) 2015-04-30 2016-11-03 Areva Gmbh Système de génération de radionucléides et procédé de production de radionucléides
WO2017012655A1 (fr) 2015-07-21 2017-01-26 Areva Gmbh Système et procédé de récolte de cibles d'irradiation activées à partir d'un réacteur nucléaire et système de génération de radionucléides

Family Cites Families (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2698713B1 (fr) * 1992-12-01 1995-03-17 Framatome Sa Dispositif et procédé de nettoyage d'un conduit et notamment d'un tube de guidage d'instrumentation d'un réacteur nucléaire.
AU3435297A (en) * 1997-06-19 1999-01-04 European Organization For Nuclear Research Neutron-driven element transmuter
TW440879B (en) * 1999-11-24 2001-06-16 Inst Of Nuclear Energy Res Roc A liquid transfer apparatus for radioisotope production
CN1159726C (zh) * 2002-06-21 2004-07-28 清华大学 球床型高温气冷堆双区堆芯交界面的测定方法及装置
TW200919486A (en) * 2007-10-18 2009-05-01 Atomic Energy Council Transmission system of target material
CN101315815B (zh) * 2008-04-28 2011-06-08 吕应中 快速增殖与转化核燃料的方法与装置
US8488733B2 (en) * 2009-08-25 2013-07-16 Ge-Hitachi Nuclear Energy Americas Llc Irradiation target retention assemblies for isotope delivery systems
CN101702330B (zh) * 2009-11-06 2011-11-09 清华大学 一种球床反应堆燃料元件气力输送减速的方法及系统
US20130083881A1 (en) * 2011-09-29 2013-04-04 Abt Molecular Imaging, Inc. Radioisotope Target Assembly
US9330798B2 (en) * 2011-12-28 2016-05-03 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for processing irradiation targets through a nuclear reactor
US20130315361A1 (en) * 2012-05-22 2013-11-28 John F. Berger Systems and methods for processing irradiation targets through multiple instrumentation tubes in a nuclear reactor
KR101373676B1 (ko) * 2012-08-03 2014-03-13 한국원자력연구원 분리된 질소탱크로 가압되는 질소가스탱크 분리형 안전주입탱크 시스템
DE102013209191A1 (de) * 2013-05-17 2014-11-20 Areva Gmbh Druckentlastungs- und Aktivitätsrückhaltesystem für eine kerntechnische Anlage
CN203397707U (zh) * 2013-08-20 2014-01-15 中广核工程有限公司 一种核电站安全防护系统
US9544983B2 (en) * 2014-11-05 2017-01-10 Asml Netherlands B.V. Apparatus for and method of supplying target material
WO2016129308A1 (fr) * 2015-02-09 2016-08-18 住友電気工業株式会社 Système de traitement de l'eau et procédé de traitement de l'eau
BR112017014717B1 (pt) * 2015-02-09 2022-05-31 Framatome Gmbh Sistema de geração de radionuclídeo
RU2690671C2 (ru) * 2015-02-09 2019-06-05 Фраматом Гмбх Система обработки облучаемых мишеней
US10755829B2 (en) * 2016-07-14 2020-08-25 Westinghouse Electric Company Llc Irradiation target handling device for moving a target into a nuclear reactor
CN106128539B (zh) * 2016-08-30 2019-01-22 中广核研究院有限公司 一种利用压水堆核电站生产医用短寿期放射源的系统
CN111316375B (zh) * 2017-11-02 2024-02-27 格斯根德尼肯核电股份公司 通过核素激活靶和测量体在核反应堆中选择性地进行核素激活和测量的设备和方法
CN108389641B (zh) * 2017-12-28 2019-07-26 中国科学院近代物理研究所 一种核燃料小球的制备装置及制备方法

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2093773A2 (fr) 2008-02-21 2009-08-26 GE-Hitachi Nuclear Energy Americas LLC Appareil et procédés de production de radio-isotopes dans des tubes d'instrumentation de réacteur nucléaire
WO2016173664A1 (fr) 2015-04-30 2016-11-03 Areva Gmbh Système de génération de radionucléides et procédé de production de radionucléides
WO2017012655A1 (fr) 2015-07-21 2017-01-26 Areva Gmbh Système et procédé de récolte de cibles d'irradiation activées à partir d'un réacteur nucléaire et système de génération de radionucléides

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2022086433A (ja) * 2020-11-30 2022-06-09 三菱重工業株式会社 放射性同位体の製造装置および放射性同位体の製造方法
JP7377786B2 (ja) 2020-11-30 2023-11-10 三菱重工業株式会社 放射性同位体の製造装置および放射性同位体の製造方法

Also Published As

Publication number Publication date
CA3136561C (fr) 2024-02-06
EP3973548A1 (fr) 2022-03-30
KR102716583B1 (ko) 2024-10-11
KR20210151925A (ko) 2021-12-14
CA3136561A1 (fr) 2020-11-26
BR112021022587A2 (pt) 2022-01-04
CN113892152B (zh) 2024-05-03
CN113892152A (zh) 2022-01-04

Similar Documents

Publication Publication Date Title
EP3257053B1 (fr) Système de traitement de cible d'irradiation
JP5816223B2 (ja) 原子炉内の複数の計装案内管を通して照射目標物を処理するためのシステム
EP3326175B1 (fr) Système et procédé de récolte de cibles d'irradiation activées à partir d'un réacteur nucléaire et système de génération de radionucléides
CA3136561C (fr) Systemes et procedes d'elimination de cibles d'irradiations presentes dans un reacteur nucleaire et systeme de generation de radionucleides.
CA2984329C (fr) Systeme de generation de radionucleides et procede de production de radionucleides
WO2016207054A1 (fr) Procédé de production de radio-isotopes à l'aide d'une centrale nucléaire à eau lourde
US20230187093A1 (en) Installation and method for producing activated irradiation targets in an instrumentation tube system of a nuclear reactor
RU2804065C1 (ru) Установка и способ производства активированных мишеней для облучения в трубной системе контрольно-измерительного оборудования ядерного реактора

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 19727970

Country of ref document: EP

Kind code of ref document: A1

ENP Entry into the national phase

Ref document number: 3136561

Country of ref document: CA

ENP Entry into the national phase

Ref document number: 20217036938

Country of ref document: KR

Kind code of ref document: A

REG Reference to national code

Ref country code: BR

Ref legal event code: B01A

Ref document number: 112021022587

Country of ref document: BR

NENP Non-entry into the national phase

Ref country code: DE

ENP Entry into the national phase

Ref document number: 2019727970

Country of ref document: EP

Effective date: 20211223

ENP Entry into the national phase

Ref document number: 112021022587

Country of ref document: BR

Kind code of ref document: A2

Effective date: 20211110