RU2804065C1 - Installation and method for production of activated targets for irradiation in pipe system of control and measuring equipment of nuclear reactor - Google Patents

Abstract

FIELD: radionuclides; nuclear reactors.

SUBSTANCE: invention is intended for the production of radionuclides in the pipe system of control and measuring equipment of a nuclear reactor. The decay station (30) includes a housing (50) with a radiation protective screen (54), the housing (50) limits the decay pipeline (52), designed to accommodate irradiation targets (16) in a predetermined linear order. The decay pipeline (52) contains an inlet (56) for connection with the structure (12) of the nuclear reactor core (10) for receiving targets (16) from it and an outlet (58) for connection with the system (27) for unloading irradiation targets for unloading targets (16) from the decay station (30). Moreover, the decay station (30) contains an input distributor (68) located at the inlet (56) of the decay pipeline for the simultaneous release from the decay station (30) of only a predetermined number of targets (16) towards the structure (12) of the core (10). The inlet distributor (68) is adapted to release the targets (16) closest to the inlet (56) of the disintegration pipeline, while retaining the remaining targets (16) in the disintegration pipeline (52).

EFFECT: possibility of releasing activated radiation targets 16 from the core 10 of a nuclear reactor while minimizing the risk to the environment.

38 cl, 7 dwg

Description

Technical field

The invention relates to a decay station configured to receive irradiation targets from a structure inside the core of a nuclear reactor, to a diverter of an installation for the production of activated irradiation targets in a nuclear reactor, as well as to an installation and method for the production of activated irradiation targets in a pipe system of nuclear control equipment reactor.

Radioactive nuclides are used in various fields of science and technology, as well as in medicine. Radionuclides are produced in research reactors or cyclotrons. However, it is desirable to establish alternative production sites since the number of facilities for commercial radionuclide production is already limited and is expected to decline.

The neutron flux density in the core of an industrial nuclear reactor is measured, in particular, by solid-state spherical probes inserted into pipes of control equipment passing through the reactor core. Thus, it is advisable to use the pipes of control equipment of industrial nuclear reactors for the production of radionuclides when the reactor is operating in power generation mode. In particular, it is possible to use one or more instrumentation tubes of an industrial nuclear reactor balloon metering system by modifying and/or adding to existing components of said metering ball system to improve the efficiency of radionuclide production during reactor operation.

Patent applications EP3326175A1 or WO2019/086329A1 describe installations and methods for producing radionuclides in a nuclear reactor instrumentation piping system.

However, these settings are not completely acceptable.

In fact, the delivery intervals for radionuclides requested by customers are usually shorter than the time required for the production of radionuclides in the core of a nuclear reactor under the influence of a neutron flux. Since the radionuclide production facilities described above use only a few pipes of instrumentation equipment, it is not possible to shorten the production window and provide radionuclides at the frequency required by customers.

In addition, activation of radiation targets in the core of a nuclear reactor leads to the formation of the required radionuclides, as well as short-lived highly radioactive isotopes as by-products. For example, the production of lutetium-177 in a nuclear reactor core produces the highly radioactive isotope ytterbium as a byproduct. In addition, highly radioactive isotopes of aluminum are formed as by-products when irradiation targets contain an aluminum-containing cladding.

Since these by-products are highly radioactive, the conventional radionuclide discharge systems described in the above-mentioned patent applications cannot be used in order to avoid the release of unacceptably high radiation into the environment, since the said discharge systems are designed to discharge the less radioactive isotopes produced by the installation, which do not contain the specified by-products .

To eliminate the problems associated with unloading activated radiation targets containing both the desired radionuclides and short-lived by-products, the installation can be equipped with a hot chamber that receives the activated radiation targets for subsequent unloading into storage containers. However, the construction of such a hot cell is very expensive, and the hot cell occupies a large space, which makes it difficult to use the hot cell in industrial nuclear reactors where space is limited.

Disclosure of the Invention

In connection with the above, one of the objectives of the invention is to create an economical and compact system that provides a delivery interval for radionuclides that is shorter than the activation time required for the production of radionuclides in the core of a nuclear reactor, and allows for the unloading of activated radiation targets from the structure of the core of a nuclear reactor with minimal risk to the environment.

Thus, the invention relates to a decay station configured to receive radiation targets from a nuclear reactor core structure in a predetermined linear order and including a housing containing a radiation shield adapted to protect the environment surrounding the decay station from radiation, emitted by radiation targets contained in the decay station, and

the housing defines a disintegration pipeline designed to accommodate irradiation targets in a predetermined linear order, wherein the disintegration pipeline contains:

- an input intended for connection to the structure of the nuclear reactor core for receiving radiation targets from it;

- an output intended for connection to the irradiation target unloading system for unloading irradiation targets from the decay station, wherein

The disintegration station additionally contains:

- an inlet distributor located at the inlet of the decay pipeline and adapted for the simultaneous release from the decay station of only a predetermined number of irradiation targets towards the structure of the nuclear reactor core, while the inlet distributor is adapted for the release of irradiation targets closest to the inlet of the decay pipeline, holding at this is the remaining irradiation target in the decay pipeline;

- an input counter configured to count the number of irradiation targets entering or exiting the decay pipeline through the input of the decay pipeline, wherein the input counter is located at the entrance of the decay pipeline, and

- output radiation sensor, adapted for measuring radiation emitted by an irradiation target located at the output of the decay pipeline.

The decay station according to the invention is adapted to receive a certain number of irradiation targets for temporary storage of partially activated irradiation targets, or for holding activated irradiation targets to an acceptable level of decay of short-lived radioisotopes with subsequent unloading into storage containers.

Returning a certain number of irradiation targets contained in the decay station to the core of a nuclear reactor using an input distributor and an associated counter allows the production of batches of radioisotopes with a delivery interval shorter than the activation time required for the production of radioisotopes in the core within the same finger of test equipment. For example, it is possible to produce batches of radioisotopes with a delivery interval equal to half the activation time required to produce radioisotopes in the core.

In particular, in the specified linear order from the entrance to the exit of the decay station, a batch of partially activated irradiation targets that were in the core for part of the required activation time, and a batch of fully activated irradiation targets that were in the core for the required activation time. The inlet distributor allows only partially activated irradiation targets to be selectively moved back into the core after a number of non-activated irradiation targets have been introduced into the core, while fully activated irradiation targets are retained in the decay station for further decay of short-lived by-product isotopes before unloading using an adapted system for unloading fully activated irradiation targets into storage containers.

Thus, from the said decay station, fully activated irradiation targets can be discharged into conventional storage containers without the need for a hot chamber or handlers, while providing intermediate storage of fully activated irradiation targets in the unloading circuit of the system for a period of time sufficient to reduce the activity of short-lived radioisotopes to acceptable level. Once the radioactivity level has decreased below a predetermined threshold, the activated radiation targets can be automatically transferred from the decay station to the facility's unloading system, which ensures the release of the produced activated radiation targets.

The movement of targets into and out of the decay station can be done automatically, without any manual operations required, for example, when using a hot cell.

In addition, the decay station according to the invention can be directly and easily integrated into existing radionuclide production facilities, and ensures the safe decay of short-lived, highly radioactive isotopes that are by-products. The disintegration station can occupy any location along the path of movement of irradiation targets from the core of a nuclear reactor to the unloading system, that is, it is universal.

Thus, the compact decay station proposed in the invention, which ensures the unloading of activated radiation targets from the core of a nuclear reactor with minimal risk to the environment, is an effective and economical technical solution.

The disintegration station may additionally have one or more of the following features, individually or in any technically feasible combination:

- the disintegration station further comprises a source of compressed gas connected to the outlet of the disintegration pipeline for supplying compressed gas to the disintegration pipeline through the outlet of the pipeline;

- the inlet distributor contains, in the direction from the inlet of the decay pipeline to the outlet of the decay pipeline, sequentially located:

- a locking element movable between a locking position in which it prevents the movement of irradiation targets from the decay pipeline through the inlet of the decay pipeline, and a unlocking position in which it allows the release of a predetermined number of irradiation targets from the decay pipeline through the inlet of the decay pipeline; And

- a latch movable between a retracted position in which it allows movement of the irradiation targets, and an extended position in which it engages at least partially into the disintegration conduit, the latch being capable of abutting the irradiation target in the extended position, preventing movement of the irradiation target towards inlet of the decay pipeline,

the input distributor additionally contains:

- a first actuator adapted to move the locking element between a locking position and an unlocking position; And

- a second actuator adapted to move the latch between an extended position and a retracted position, the first and/or second actuator being, for example, a pneumatic, magnetic or hydraulic actuator;

- the locking element comprises a locking pin configured to be radially extended across the disintegration pipeline into a locking position of the locking element, wherein the latch comprises a locking pin configured to be partially radially extended into the disintegration pipeline into the extended locking position, and a spring element connected to the locking pin;

- the decay station additionally contains a controller adapted, using an input distributor, to regulate the sequence of release of a predetermined number of irradiation targets when performing the following steps:

- moving the locking element by means of the first actuator from the unlocking position to the locking position;

- providing a supply of compressed gas to obtain a flow of compressed gas through the disintegration pipeline from its outlet, and the flow of compressed gas is capable of pushing the irradiation targets contained in the disintegration pipeline towards the entrance of the pipeline until they stop at the shut-off element occupying a blocking position;

- moving the latch by means of a second actuator from a retracted position to an extended position in which the latch is capable of abutting the irradiation target contained in the decay pipeline;

- moving the locking element by means of the first actuator from the locking position to the unlocking position, so that a predetermined number of irradiation targets, corresponding to the number of irradiation targets located downstream of the lock in the direction of the flow of compressed gas, is released from the disintegration pipeline through the inlet of the disintegration pipeline, while while the remaining irradiation targets are held in the decay pipeline by a latch occupying an extended position;

- the controller is additionally adapted to repeat successive stages of release of irradiation targets depending on the total number of irradiation targets to be released from the decay station through the inlet of the decay pipeline;

- a predetermined number of irradiation targets is equal to one irradiation target, wherein the distributor is adapted to release the irradiation targets one by one from the decay station towards the structure of the nuclear reactor core;

- the decay station additionally contains at least one intermediate irradiation target counter, configured to count the number of irradiation targets contained in the decay pipeline, and located between the input counter and the output of the decay pipeline, wherein at least one intermediate irradiation target counter is, for example a temperature sensor, a pressure sensor or a radiation sensor, for example a gamma radiation sensor;

- the decay station additionally contains at least one intermediate radiation sensor, configured to measure radiation emitted by irradiation targets contained in the decay pipeline, and located between the output radiation sensor and the input of the decay pipeline;

- the disintegration station additionally contains an output distributor located in the area of the exit of the disintegration pipeline and adapted for the simultaneous release of only a predetermined number of irradiation targets from the disintegration station through the output of the disintegration pipeline, wherein the output dispenser is adapted to release irradiation targets closest to the exit of the disintegration pipeline, holding at this is the remaining irradiation target in the decay pipeline;

- the disintegration pipeline is a straight pipeline, preferably inclined downward from the inlet of the disintegration pipeline to the outlet of the disintegration pipeline;

- the disintegration conduit is substantially U-shaped and comprises a first section, a second section and a lower portion formed at the junction between the first and second disintegration conduit sections, with the first and second disintegration conduit sections extending upward from the lower portion.

- the decay station contains a controller adapted to regulate the release from the decay station of at least some irradiation targets after a predetermined decay time;

- the decay station further comprises a controller adapted to regulate the release of only those radiation targets whose radiation is below a predetermined threshold, the emitted radiation being measured by an output radiation sensor and/or an optional intermediate radiation sensor;

- the decay station further comprises a controller adapted to regulate the release of at least some of the irradiation targets when the radiation measured by the output radiation sensor and, if necessary, intermediate radiation sensors decreases below a predetermined threshold;

- the design of the nuclear reactor core is the pipe system of control and measuring equipment of the nuclear reactor.

The invention also relates to a diverter of an installation for producing activated radiation targets in a nuclear reactor, the diverter having a first configuration in which it determines the trajectory of movement of radiation targets between the structure of the nuclear reactor core, in particular the pipe system of control and measuring equipment, and the system for unloading radiation targets for unloading activated irradiation targets, and a second configuration in which it determines the trajectory of movement of irradiation targets between the irradiation target supply system and the nuclear reactor core structure, wherein

diverter contains:

- the first connector intended for connection with the system for unloading irradiation targets;

- a second connector designed for connection to the irradiation target supply system;

- a third connector intended for connection with the structure of the nuclear reactor core;

- at least one diverter pipeline that is capable of moving between:

- the first position in which it connects to the third connector one of the connectors, namely the first connector or the second connector, defining the trajectory of movement of the targets from one of the connectors, namely from the first or second connector, to the third connector, and

- a second position in which it does not connect one of the connectors, namely the first connector or the second connector, to the third connector; and

said or each diverter pipeline is shaped in such a way that along its length the direction of movement of the irradiation targets intended for circulation in it changes twice, and

- an actuator adapted to move said or each diverter pipeline between a first position and a second position.

The advantage of this diverter is that it is compact and allows targets to be selectively moved to different destinations directly, that is, without the need for additional intermediate movement operations.

The diverter may additionally have one or more of the following features, individually or in any technically feasible combination:

- said or each diverter pipeline contains a substantially straight end section at each end of the divertor pipeline and an intermediate section located between them;

- the intermediate section of each diverter pipeline is straight, and the absolute value of the angle between the end sections of the divertor pipeline and the intermediate section, for example, ranges from 2° to 5°;

- the intermediate section of the specified or each divertor pipeline is curved, and the radius of curvature of the specified or each divertor pipeline at the junction with each of the end sections, for example, ranges from 200 to 800 mm;

- the third connector is located at a distance from the first connector and the second connector in the horizontal direction;

- the first connector and the second connector are substantially aligned vertically and/or the third connector is located at an intermediate height between the heights of the first and second connectors;

- the actuator is adapted to move said or each diverter pipeline between a first position and a second position by means of a translational or rotary motion;

- the diverter contains a first diverter pipeline and a second divertor pipeline, wherein

the first diverter pipeline in its first position connects the first connector to the third connector, defining the trajectory of the targets from the first connector to the third connector, and

the second diverter pipeline, in its first position, connects the second connector to the third connector, defining a path of movement of the targets from the second connector to the third connector;

- the diverter is designed so that the first divertor pipeline occupies the first position when the second diverter pipeline occupies the second position, and vice versa;

- the diverter further comprises a piston that limits the first and second diverter pipelines inside, wherein the piston is configured to move between a first position in which the first divertor pipeline occupies a first position and a second divertor pipeline occupies a second position, and a second position in which the first divertor pipeline the pipeline occupies the second position, and the second diverter pipeline occupies the first position;

- the diverter additionally has a housing, wherein the piston is placed in the divertor housing with the ability to slide in the direction of movement;

- the diverter housing additionally contains:

- first and second chambers formed between the piston and the divertor body, with the first and second chambers located on both sides of the piston in the direction of movement of the piston;

- an inlet port in fluid communication with the first chamber and designed to supply a fluid under pressure into the first chamber to move the piston from a first position to a second position; and

- an outlet port in fluid communication with the second chamber and designed to release air from the second chamber during movement of the piston in the direction of movement;

- the piston is configured to return to the first position if there is no fluid under pressure in the first chamber;

- the divertor body contains first and second walls located at a distance from each other in the longitudinal direction of the divertor pipeline, with the first and second connectors located on the first wall, and the third connector on the second wall;

- the first and second diverter pipelines are located symmetrically relative to the middle plane between the two pipelines;

- the divertor contains one single divertor pipeline, wherein the divertor pipeline in the first position connects the first connector to the third connector, and in the second position connects the second connector to the third connector, while the divertor pipeline is rotatable between the first position and the second position;

- the diverter further comprises a support on which the first and second connectors are located, and a rotary pipeline holder, which is installed on the support with the possibility of rotation around the axis of rotation, and one end of the divertor pipeline is installed on the rotary pipeline holder so that when the pipeline holder is rotated, the divertor pipeline moves between the first position and the second position.

The invention also relates to an installation for the production of activated irradiation targets in a pipe system of control and measuring equipment of a nuclear reactor, containing:

- a system for supplying irradiation targets, designed to ensure the availability of non-activated irradiation targets;

- a pipe system of control and measuring equipment, configured to receive irradiation targets from the irradiation target supply system, based on their activation under the influence of a neutron flux in a nuclear reactor;

- a decay station as defined above, wherein the inlet of the decay conduit is connected to the instrumentation piping system, and the inlet dispenser of the disintegration station is adapted to simultaneously release a predetermined number of irradiation targets from the disintegration station towards the instrumentation piping system, wherein the inlet dispenser adapted to release irradiation targets closest to the instrumentation piping system while retaining the remaining irradiation targets in the decay station;

- a system for unloading irradiation targets, containing a target output port, configured to be connected to a container for storing targets, wherein the unloading system contains an inlet end connected to the outlet of the disintegration station pipeline;

- a diverter moved between the first position in which it determines the trajectory of movement of irradiation targets between the delivery system of irradiation targets and the pipe system of control and measuring equipment, and the second position in which it determines the trajectory of movement of irradiation targets between the pipe system of control and measuring equipment and the station decay; And

- a drive system for irradiation targets, configured to transport at least some targets through the installation, wherein the drive system for irradiation targets contains a unit for supplying compressed gas to the disintegration station.

The installation may further comprise a controller adapted to control the following steps carried out by the installation:

- movement through the drive system of non-activated radiation targets in the amount of q ₁ from the system for supplying radiation targets to the pipe system of control and measuring equipment;

- irradiation with a neutron flux of non-activated irradiation targets in an amount q ₁ in a pipe system of control and measuring equipment during a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets in an amount q ₁ , and the predetermined irradiation time d ₁ is strictly less than the minimum activation time to completely convert the precursor material contained in the irradiation targets into the required radionuclide;

- movement through the drive system of partially activated irradiation targets in the amount of q ₁ from the pipe system of control and measuring equipment to the decay station;

- movement through the drive system of non-activated radiation targets in an amount of q ₂ from the system for supplying radiation targets to the pipe system of control and measuring equipment;

- movement through the drive system of partially activated irradiation targets in the amount of q ₁ back from the decay station to the pipe system of control and measuring equipment;

- irradiation with a neutron flux of partially activated irradiation targets in the amount of q ₁ and non-activated irradiation targets in the amount of q ₂ in the pipe system of control and measuring equipment during a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets in the amount of q ₁ and partially activated irradiation targets in the amount of q ₂ ; And

- unloading at least some of the irradiation targets and, preferably, the fully activated irradiation targets from the decay station into a target storage container.

The diverter may have the design described above.

The invention also relates to a method for producing activated irradiation targets using the apparatus disclosed above, comprising the steps of:

- move non-activated irradiation targets in an amount of q ₁ into the pipe system of control and measuring equipment from the irradiation target supply system;

- irradiate non-activated irradiation targets in an amount q ₁ with a neutron flux in a pipe system of control and measuring equipment for a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets in an amount q ₁ , and the predetermined irradiation time d ₁ is equal to or less than the minimum time activation for complete conversion of precursor material contained in irradiation targets into the required radionuclide;

- move irradiation targets in an amount q ₁ from the pipe system of control and measuring equipment to the decay station;

- unloading at least some irradiation targets from the decay station into a container for storing targets.

The method may further include one or more of the following features, individually or in any technically feasible combination:

- the method further includes the step of holding at least some irradiation targets in the decay station for a predetermined decay time before unloading the irradiation targets from the decay station into a target storage container;

- a predetermined time d ₁ is less than the minimum activation time for complete conversion of the precursor material contained in the irradiation targets into the desired radionuclide, resulting in the number q ₁ of irradiation targets received at the end of the irradiation stage in the instrumentation tubing system being the number q ₁ partially activated radiation targets;

wherein the method, between the step of moving partially activated irradiation targets in an amount of q ₁ from the pipe system of control and measuring equipment to the decay station and the step of unloading at least some irradiation targets from the decay station into a target storage container, further includes the following steps, in which:

- move non-activated radiation targets in an amount of q ₂ into the pipe system of control and measuring equipment;

- move partially activated irradiation targets in an amount q ₁ from the decay station back to the pipe system of control and measuring equipment;

- irradiate partially activated irradiation targets in an amount of q ₁ and non-activated irradiation targets in an amount of q ₂ with a neutron flux in a pipe system of control and measuring equipment for a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets in an amount of q ₁ and partially activated irradiation targets in the amount of q ₂ ;

- the method includes the step of measuring radiation, in particular, the dose rate emitted by irradiation targets in an amount q ₁ located in the outlet pipeline, before unloading the irradiation targets from the decay station, which, before unloading from the decay station, were held in the outlet pipeline until until the radiation, in particular the dose rate, falls below a predetermined threshold.

The invention also relates to an installation for the production of activated irradiation targets in a pipe system of control and measuring equipment of a nuclear reactor, containing:

- a system for supplying irradiation targets, adapted to ensure the presence of non-activated irradiation targets;

- a pipe system of control and measuring equipment, configured to receive irradiation targets from the irradiation target supply system, based on their activation under the influence of a neutron flux in a nuclear reactor;

- a system for unloading irradiation targets, containing a target output port configured to connect to a container for storing targets,

- a diverter, as described above, adapted to selectively determine the trajectory of movement of targets between the irradiation target supply system and the instrumentation pipe system, or between the instrumentation tube system and the irradiation target unloading system, the first connector being connected to the irradiation target unloading system, the second connector is connected to the irradiation target supply system, and the third connector is connected to the instrumentation pipe system; And

- a drive system for irradiation targets, configured to transport at least some irradiation targets through the installation;

According to a particular aspect, the installation further comprises a disintegration station located in the path of movement of irradiation targets between the pipe system of control equipment and the irradiation target unloading system and adapted to hold the activated irradiation targets before they are unloaded from the installation by means of the irradiation target unloading system, wherein the first connector is connected to system for unloading irradiation targets through a decay station.

The invention will become better understood from the following description of purely illustrative embodiments with reference to the drawings.

Brief description of drawings

In fig. 1 shows a schematic view of an installation for the production of activated irradiation targets 16 in a nuclear reactor;

in fig. 2 is a block diagram of an installation for the production of activated irradiation targets in a nuclear reactor, shown in FIG. 1;

in fig. 3 – decay station of the installation shown in Fig. 1, according to the first embodiment of the invention, is a schematic view;

in fig. 4 – decay station of the installation shown in Fig. 1, according to a second embodiment of the invention, is a schematic view;

in fig. 5 – diverter according to the first embodiment of the invention, schematic cross-sectional view;

in fig. 6 – diverter according to the second embodiment of the invention, schematic cross-sectional view;

in fig. 7 – block diagram of a method for producing activated radiation targets in a pipe system of control and measuring equipment of a nuclear reactor.

Embodiments of the Invention

According to the invention, it is assumed that an industrial nuclear reactor can be used to produce artificial radioisotopes or radionuclides. In particular, conventional balloon measurement systems or other systems containing pipes, such as instrumentation pipes, extending into and/or through an industrial reactor core can be modified and/or added to provide efficient and economical production of radionuclides in a power generating plant. reactor mode.

Some of the guide tubes, such as the industrial balloon measurement system or the Traversing Incore Probe (TIP) system, are used to guide irradiation targets containing the precursor of the desired radionuclide into the instrumentation tube in the core reactor and for releasing activated radiation targets from the reactor core.

In fig. 1 shows a plant 6 for producing activated irradiation targets 16, which can be used in an industrial nuclear power plant 8. Unlike a research reactor, the purpose of an industrial nuclear reactor is to generate electricity. The rated power of industrial nuclear reactors is usually more than 100 MW.

The basis of the installation 6 for the production of activated irradiation targets 16, described in the illustrative embodiments of the invention, is a conventional Aero-ball Measuring System (AMS) used to measure the neutron flux density in the core 10 of a nuclear reactor.

The aeroball measuring system includes a pneumatic drive system that enables the aeroballs to be inserted into a test equipment finger and the balloons to be removed from a corresponding test equipment finger upon activation. Typically, the fingers of the control equipment extend into the core 10 along its entire axial length. A plurality of balloons are arranged in a linear pattern on the instrument finger to form a column of balloons. Balloons are essentially spherical or circular probes, but may have other configurations, such as ellipsoidal or cylindrical, as long as they are capable of moving through the piping of the instrumentation piping system.

As shown in FIG. 1, an industrial nuclear reactor includes an instrumentation pipe system 12 including at least one instrumentation finger 14 extending through the nuclear reactor core 10. The pipe system 12 of the control and measuring equipment is made with the possibility of introducing irradiation targets 16 into the fingers 14 of the control and measuring equipment and their removal.

The irradiation targets 16 comprise a shell enclosing a core of non-fissile material and containing suitable precursor material for producing radionuclides that are used in medicine and/or other applications.

The shell hermetically encapsulates the core. As an example, a material that is not activated by neutron flux, such as a material including polyetheretherketone (PEEK), can be used to form the shell. The shell may preferably be partly made of a metallic material to improve detection, for example by an inductive sensor.

The core, in particular, contains precursor material in powder form.

More preferably, the irradiation targets 16 consist of a precursor material that is converted to the desired radionuclide when activated by a neutron flux in the core 10 of an operating industrial nuclear reactor. Suitable precursor materials are Mo-98, Yb-176 and Lu-176, which are converted to Mo-99 and Lu177, respectively. However, it should be understood that the invention is not limited to the use of a particular precursor material.

Conduits 13 of the instrumentation piping system 12 extend through the reactor barrier 11 and are connected to one or more instrumentation fingers 14. Preferably, the instrumentation fingers 14 extend through the pressure vessel cover of the nuclear reactor, with the instrumentation fingers 14 extending from top to bottom along substantially the entire axial length of the reactor core 10. The corresponding lower end of the control equipment fingers 14 in the lower part of the reactor core 10 is closed and/or provided with a stop, as a result of which the irradiation targets 16 inserted into the control equipment finger 14 form a column, with each target 16 pre-occupied a certain axial position.

Activation of the targets 16 is preferably optimized by placing the irradiation targets 16 in predetermined regions of the reactor core in which the neutron flux is sufficient to completely convert the feed material contained in the irradiation targets 16 into the desired radionuclide.

Proper positioning of the irradiation targets 16 can be achieved by using dummy targets 18 made of an inert material, preferably a magnetic material, and sequentially arranging the dummy targets 18 and irradiation targets 16 in the instrumentation tubing system 12 so as to form a column of targets 16, 18 within finger 14 of the instrumentation equipment. In fact, in the reactor core 10, the irradiation targets 16 occupy pre-calculated optimal axial positions, and the remaining positions are occupied by inert false targets 18 or remain empty. However, it is preferable that the majority of positions in the control equipment fingers 14 be occupied by irradiation targets 16 rather than decoy targets 18, thereby increasing radionuclide production.

The optional decoys 18 are made from an inert material that is substantially not activated in the active nuclear reactor core 10. Preferably, decoys 18 can be made from inexpensive inert materials and can be reused after a short decay time, further reducing the amount of radioactive waste. Preferably, the decoys are magnetic.

Installation 6 is adapted to work with irradiation targets 16 and false targets 18 having a round, cylindrical, elliptical or spherical shape and a diameter corresponding to the gap of the finger 14 of the control and measuring equipment of the aeroball measuring system.

The targets 16, 18 preferably have a circular shape, preferably a spherical or cylindrical shape, allowing the targets 16, 18 to slide smoothly through and be easily guided into the instrumentation tubing system 12 under the influence of a compressed gas, such as air or nitrogen, and/or under the action of gravity.

Preferably, the diameter of the targets 16, 18 is in the range of 1 to 3 mm, preferably about 1.7 mm.

According to a preferred embodiment of the invention, the industrial nuclear reactor is a pressurized water cooled reactor. More preferably, the instrumentation tube system 12 is based on a conventional pressurized water reactor (PWR) balloon instrumentation system, such as an EPR ^™ nuclear reactor or a Siemens ^™ PWR.

However, those skilled in the art will appreciate that the invention is not limited to the use of a PWR balloon metering system. Instead, it is also possible to use Boiling Water Reactor (BWR) moving intrazone ionization chamber (TIP) system instrumentation tubes, Canadian heavy water uranium reactor (CANDU) observation ports, and heavy water reactor temperature and/or neutron flux measurement channels.

As shown in FIG. 1, installation 6 contains a system 21 for supplying irradiation targets, designed to supply the pipe system 12 of control and measuring equipment with non-activated irradiation targets 16.

The irradiation target supply system 21 contains a supply pipe 23 having an outlet end intended for connection to the pipe system 12 of control and measuring equipment. The irradiation target supply system 21 further comprises a supply unit 22 adapted for supplying irradiation targets 16, and, if necessary, false targets 18 into the installation 6. The supply unit 22 is configured to be connected to the inlet end of the supply pipe 23. The supply unit 22, for example, contains a container, funnel or cartridge containing non-activated irradiation targets 16 and/or false targets 18.

In the example shown in FIG. 1, the irradiation target supply system 21 further includes a stopper 20 adapted to block movement of the irradiation targets 16 and optional dummy targets 18 through the supply pipe 23. The stopper 20 may be a magnetically or pneumatically actuated pin.

The irradiation target supply system 21 supplies the device with irradiation targets 16 that are non-activated irradiation targets 16, that is, irradiation targets 16 that have not been subjected to any irradiation in the nuclear reactor core 10 and do not contain radioactive isotopes.

As shown in FIG. 2, installation 6 further includes a target drive system 25 configured to transport irradiation targets 16 and optional decoy targets 18 through installation 6.

The target drive system 25 is configured to transport targets 16, 18, in particular, from the feed system 21 to the control equipment fingers 14 in a predetermined linear order and to displace the irradiation targets 16 and false targets 18 from the control equipment finger 14 while maintaining the linear order of the targets 16, 18.

Preferably, the target drive system 25 is pneumatic and uses a compressed gas, such as nitrogen or air. This system allows you to quickly manipulate targets 16 and, if necessary, false targets 18.

Preferably, the target drive system 25 includes one or more pneumatic valve banks (not shown) to separately control the introduction and transport of irradiation targets 16 and, if necessary, dummy targets 18 in the instrumentation tubing system 12. The valve banks of the target drive system 25 may be implemented as a subsystem in addition to the valve banks of a conventional balloon measurement system, or a separate target drive system 25 may be installed.

In the feed system 21, the irradiation targets 16 and optional dummy targets 18 may be moved from the feed unit 22 to the feed pipe 23 by gravity or the target drive system 25.

Installation 6 additionally contains a system 27 for unloading irradiation targets, adapted for receiving irradiation targets 16 from the pipe system 12 of control and measuring equipment and for unloading said irradiation targets 16 into a shielded container 34 for storage. The irradiation target unloading system 27 is described in more detail below with reference to FIG. 1.

Installation 6 according to the invention additionally contains a decay station 30 located between the pipe system 12 of control and measuring equipment and the system 27 for unloading irradiation targets.

Decay station 30 is designed to receive partially or fully activated irradiation targets 16 from the nuclear reactor core structure and, in particular, removed from the pipe system 12 of control and measuring equipment.

Decay station 30 is specifically designed to hold fully activated irradiation targets 16 for a predetermined time to provide a predetermined reduction in the activity of fully activated irradiation targets 16 before unloading said irradiation targets 16 into a storage container 34 by irradiation target unloading system 27.

Preferably, the disintegration station 30 is located outside the reactor core 10, but preferably within accessible areas within the reactor containment. The decay station 30 will be described in more detail below with reference to FIG. 1 and 3.

According to the embodiment of the invention shown in FIG. 1, installation 6 additionally contains a diverter 32, adapted to alternately set the trajectory of movement of irradiation targets 16 and optional false targets 18 between the irradiation target supply system 21 and the pipe system 12 of control and measuring equipment, or between the pipe system 12 of control and measuring equipment and the decay station 30 . More specifically, the diverter 32 has a first configuration in which it determines the path of movement of the irradiation targets 16 and optional decoys 18 from the instrumentation tube system 12 to the decay station 30, and a second configuration in which it determines the path of movement of the irradiation targets 16 and optional decoys. targets 18 from the system 21 for supplying irradiation targets to the pipe system 12 of control and measuring equipment.

The movement of the irradiation targets 16 and optional dummy targets through the diverter 32 is provided by a target drive system 25.

Installation 6 additionally contains a switching unit 40, configured to transfer the diverter 32 to the first configuration or to the second configuration, depending on the need.

The diverter 32 will be described in more detail below with reference to FIG. 5 and 6.

As shown in FIG. 2, installation 6 additionally contains a measurement and control unit 42 (from the English “instrumentation and control unit” (ICU)), connected to a system 21 for supplying irradiation targets, a pipe system 12 of control and measuring equipment, a drive system 25 for targets, a switching unit 40, decay station 30 and system 27 for unloading irradiation targets.

Preferably, the measurement and control unit 42 is also connected to a fault monitoring system 28 of the balloon measuring system, which notifies of any errors. The fault monitoring system 28 may not be connected to an existing balloon measurement system, but may be directly connected to the main control tower.

In addition, installation 6 contains an online core monitoring system 26 for regulating the activation of irradiation targets 16.

According to one embodiment of the invention, the core monitoring system 26 and the measurement and control unit 24 are designed so that the activation process for converting the irradiation targets 16 into the required radionuclide is optimized based on indicators of the actual state of the reactor, characterizing, in particular, the current neutron flux and fuel burnup , reactor power and/or load. Thus, to achieve optimal results, the optimal axial position of the irradiation targets and the irradiation duration can be calculated. However, it does not matter whether the actual calculation is performed by the integrated measurement and control unit 42 or by the core monitoring system 26 of the balloon measurement system.

The disintegration station 30 according to the first embodiment of the invention will be described in more detail below with reference to FIGS. 3.

The decay station 30 according to the first embodiment of the invention is preferably configured to receive cylindrical irradiation targets 16, preferably having a circular base. As described above, the irradiation targets 16 preferably have a diameter of 1 mm to 3 mm, and preferably equal to about 1.7 mm.

The length of each cylindrical irradiation target 16 is preferably greater than or equal to twice the diameter of the irradiation targets 16. The upper limit on the length of the cylindrical irradiation targets 16 is in particular determined by the radius of curvature of the pipelines of the installation 6. The length of each cylindrical target 16 is, for example, from 60 mm to 75 mm, and in particular is approximately 70 mm.

Decay station 30 has a housing 50 defining a decay conduit 52 designed to accommodate irradiation targets 16 and, in particular, partially or fully activated irradiation targets.

The linear order of the irradiation targets 16 in the instrumentation tube system 12 is maintained in the disintegration station 30 .

The installation 6 may include a separation device 53 (shown in FIG. 3) located along the path of movement of the targets 16, 18 from the instrumentation pipe system 12 to the decay station 30 to remove unnecessary false targets 18, resulting in the decay station 30 Only the irradiation targets 16 move. Preferably, the decoy targets 18 are magnetic and the irradiation targets 16 are non-magnetic, wherein the separating device 53 includes an optional magnetic device, for example, containing an electromagnet and located along the path of the targets 16, 18 from the instrumentation pipe system 12 to the disintegration station 30 for holding only decoy targets 18. It should be noted that if decoy targets 18 are present, they will typically be located in the test equipment finger 14 below the targets 16, so that when the targets 16, 18 are moved from the test equipment pipe system 12 to the decay station 30, the target 16 irradiations moved ahead of the false targets 18. The false targets 18 and the separating device 53 are optional.

The disintegration line 52 preferably has a circular cross-section. The inner diameter of the decay conduit 52 essentially matches the outer diameter of the irradiation targets 16.

The housing 50 includes a radiation shield 54 to protect the environment surrounding the decay station 30 from radiation emitted by partially or fully activated radiation targets 16 contained in the decay station 30, and, in particular, to limit the amount of radiation emanating from inside the station 30 disintegration into the environment.

The radiation shield 54 is made of a material designed to absorb or reflect radiation, in particular alpha, gamma and/or beta radiation. According to one embodiment of the invention, the radiation shield 54 is made of lead or tungsten or a combination thereof.

The thickness of the radiation shield 54 is selected, in particular, depending on the nature of the radionuclides that are to be located in the decay station 30, and, in particular, depending on the magnitude of the emitted radiation. Preferably, the thickness of the radiation shield 54 is selected such that the dose of radiation penetrating from outside the decay station 30 into the environment is less than or equal to a predetermined threshold. The predetermined threshold is, for example, 25 μSv/h at a distance of 50 cm from the decay station 30.

The radiation shield 54 preferably extends throughout the entire circumferential outer surface of the housing 50. In particular, the radiation shield 54 forms a wall of the housing 50 delimiting the decay conduit 52.

The decay pipeline 52 has:

- input 56, intended for connection with the pipe system 12 of control and measuring equipment, for receiving irradiation targets 16;

- output 58, intended for connection with the system 27 for unloading irradiation targets, for unloading irradiation targets 16 from the decay station 30.

The inlet 56 of the disintegration pipeline forms the input of the disintegration station 30, and the output 58 of the disintegration pipeline forms the output of the disintegration station 30.

The decay conduit inlet 56 is particularly designed to connect to the instrumentation piping system 12 in the first configuration of the divertor 32.

Preferably, the length of the decay conduit 52 between the inlet 56 and the outlet 58 is equal to or greater than the length of the activation zone of the instrumentation conduit 12, such that all irradiation targets 16 activated in the instrumentation conduit 12 are contained within the disintegration conduit 52. The activation zone corresponds to the zone of the pipe system 12 of control and measuring equipment designed to receive irradiation targets 16 that are activated in the core. In particular, the length of the decay line 52 between the inlet 56 and the outlet 58 is greater than or equal to the length of the instrument pin 14.

According to a first embodiment of the invention shown in FIG. 3, the disintegration line 52 extends in a straight line from inlet 56 to outlet 58.

As shown in FIG. 3, the decay conduit 52 preferably extends at an angle from the inlet 56 to the outlet 58. This inclination prevents the irradiation targets 16 from moving toward the inlet 56 of the disintegration conduit in the absence of an additional force directed toward the inlet 56 of the disintegration conduit.

According to one alternative embodiment of the invention (not shown), the disintegration line 52 runs substantially horizontally.

The housing 50 is, for example, substantially cylindrical.

Decay station 30 further contains:

- a first compressed gas supply unit 60 connected to the output 58 of the disintegration pipeline for supplying compressed gas to the disintegration pipeline 52 through the output 58; And

- a second compressed gas supply unit 62 connected to the inlet 56 of the disintegration pipeline for supplying compressed gas to the disintegration pipeline 52 through the inlet 56.

The first and second compressed gas supply units 60, 62 are shown only schematically in FIG. 2.

The first and second compressed gas supply units 60, 62 are in particular part of the drive system 25 for the irradiation targets. For example, the first and second compressed gas supply units 60, 62 are connected to a common compressed gas source 63 of the drive system 25 for irradiation targets.

As shown in FIG. 1, the disintegration station 30 further includes an inlet distributor 68 located at the inlet 56 of the disintegration conduit, adapted to release only a predetermined number of irradiation targets 16 at a time from the disintegration station 30 towards the instrumentation pipe system 12, retaining at least some irradiation targets 16 in the decay station 30, that is, the remaining irradiation targets 16. The input distributor 68 provides the release of irradiation targets 16 closest to the inlet 56 of the decay pipeline.

The input distributor 68 is capable of clamping and holding the irradiation target 16 in the disintegration conduit 52 against the flow of compressed gas circulating through the disintegration conduit 52 .

The predetermined number of irradiation targets 16 is less than the total number of irradiation targets 16 that the decay station 30 can accommodate.

The inlet distributor 68 is preferably adapted to release only a predetermined number of irradiation targets 16 at a time from the decay station 30 towards the instrumentation pipe system 12, while retaining at least some of the irradiation targets 16 in the decay station 30, i.e. the remaining targets 16 irradiation, regardless of the magnetic properties of the irradiation targets 16, in particular due to mechanical action.

In particular, the inlet distributor 68 contains, in the direction from the inlet 56 of the disintegration pipeline to the outlet 58 of the disintegration pipeline, sequentially located:

- a locking element 70 movable between a locking position in which it prevents the movement of irradiation targets 16 from the decay line 52 through the decay line inlet 56, and a unlocking position in which it allows the release of a predetermined number of irradiation targets 16 from the decay line 52 through the inlet 56 pipeline decay;

- a latch 72 movable between a retracted position, in which it allows movement of the irradiation targets 16, and an extended position, in which it extends at least partially into the decay conduit 52, and can abut the irradiation target 16, preventing the movement of the specified irradiation target 16 along towards the entrance 56 of the decay pipeline.

Input distributor 68 further includes:

- a first actuator 74 for moving the locking element 70 between a locking position and an unlocking position; and

- a second actuator 76 for moving the latch 72 between an extended position and a retracted position.

Due to their configuration, the locking element 70 in the locked position and the latch 72 in the extended position are capable of allowing gas to pass through.

The locking element 70, for example, includes a locking pin 73 configured to extend radially into the disintegration conduit 52 to a locking position, preventing movement of the irradiation targets 16. Specifically, the locking pin includes a drive end coupled to the first actuator 74 and a free end opposite the drive end. In the extended position, the free end of the locking pin 73 abuts the inner surface of the disintegration pipeline 52. In the extended position, the locking pin 73 extends from one side of the disintegration conduit 52 to the opposite side along the diameter of the disintegration conduit 52. In particular, the length of the locking pin 73 is greater than or equal to the diameter of the disintegration pipeline 52.

In the unlocked position, the closure member 70 is preferably retracted into the housing 50 and does not protrude into the disintegration line 52.

The first actuator 74 is, for example, a pneumatic, magnetic or hydraulic actuator.

In the extended position, the latch 72 clamps the irradiation targets 16, pressing them against the inner wall of the decay pipeline 52. The latch 72 is configured to apply a force, in particular a radial force, to the irradiation target 16 against which it abuts in the extended position, the latch being capable of applying a force sufficient to hold said irradiation target 16 against the force of a stream of compressed gas flowing through the conduit 52 decays.

The second actuator 76 is, for example, a pneumatic, magnetic or hydraulic actuator.

The retainer 72, for example, includes a locking pin 75 configured to extend radially into the disintegration conduit 52 into an extended position, and a spring element (not shown) coupled to the locking pin 75. The spring element reduces the risk of damage to the irradiation target 16 against which the locking pin rests. pin 75 when latch 72 moves to the extended position. According to a specific embodiment of the invention, the second actuator 76 is configured to move linearly, transmitted to a spring, the force of which acts on the irradiation target 16. The second actuator 76 further includes a stop that limits the linear movement of the second actuator 76 to a predetermined range. Thus, the force applied by the locking pin 75 to the irradiation target 16 is limited by the stiffness of the spring as well as the predetermined range of movement of the second actuator 76. In particular, there is no dependence on the force acting on the second actuator 76.

The distance between the closure element 70 and the latch 72 is selected so that only a predetermined number of irradiation targets 16 can be placed between the closure element 70 and the latch 72. In particular, the distance between the locking element 70 and the latch 72 is strictly greater than the total length of the predetermined number of irradiation targets 16 and strictly less than the total length of the predetermined number of irradiation targets 16 increased by one irradiation target 16. When the closure element 70 is in the locked position and the latch 72 is in the extended position, a predetermined number of irradiation targets 16 are located in the disintegration conduit 52 between the closure element 70 and the latch 72, with the latch 72 abutting the irradiation target 16 located immediately adjacent to the most remote from the entrance 56 of the decay pipeline by an irradiation target 16 from a predetermined number of irradiation targets 16.

According to a preferred embodiment of the invention, the predetermined number of irradiation targets 16 distributed by the input distributor 68 is equal to one irradiation target. In this case, the input distributor 68 is adapted to release from the decay station 30 one irradiation target 16 at a time towards the instrumentation pipe system 12. In addition, the distance between the closure element 70 and the latch 72 is preferably selected such that only one irradiation target 16 can be located between the closure element 70 and the latch 72. In particular, the distance between the closure element 70 and the latch 72 is strictly greater than the length of one target 16 irradiation and strictly less than the length of the two 16 irradiation targets. When the closure member 70 is in the locked position and the latch 72 is in the extended position, only one irradiation target 16 can be located in the portion of the decay conduit 52 between the closure member 70 and the latch 72, with the latch 72 abutting the irradiation target 16 immediately adjacent to said target 16 irradiation. The distance between the locking element 70 and the latch 72 is approximately 1.5 times the length of the irradiation target 16.

The disintegration station 30 further includes a controller 80 (see FIG. 2) designed, using an input distributor 68, to regulate the release of a predetermined number of irradiation targets 16 when performing the following steps:

- moving the locking element 70 by means of the first actuator 74 from the unlocking position to the locking position;

- actuating the first compressed gas supply unit 60 to obtain a flow of compressed gas through the disintegration pipeline 52 from its outlet to push the irradiation targets 16 located in the disintegration pipeline 52 towards its entrance until they stop at the shut-off element 70 occupying the locking position;

- moving the latch 72 by means of the second actuator 76 from the retracted position to the extended position, allowing the latch 72 to abut the irradiation target 16 located in the decay pipeline 52 opposite the latch 72;

- moving the locking element 70 by means of the first actuator 74 from the locking position to the unlocking position so that a predetermined number of irradiation targets 16, corresponding to the number of irradiation targets 16 located downstream of the latch in the direction of the flow of compressed gas, is released from the disintegration line 52 through the inlet 56 of the decay pipeline is a stream of compressed gas, while the remaining irradiation targets 16 in the area of the clamp 72 or upstream of it are held in the decay pipeline 52 by the clamp 72 occupying an extended position.

The above unloading sequence results in the release of only a predetermined number of irradiation targets 16 from the decay station 30 through the decay conduit inlet 56, while the remaining irradiation targets 16 are retained in the decay station 30.

According to a specific embodiment of the invention, the controller 80 is configured to repeat the sequence of release steps multiple times depending on the total number of irradiation targets 16 to be released from the disintegration station 30 through the disintegration conduit inlet 56.

For example, in the preferred example in which the predetermined number of irradiation targets 16 released at one time is one, if N irradiation targets 16 are released from the decay station 30 through the input dispenser 68, the controller 80 is capable of repeating the above-described sequence of steps N times when N is different from units.

The controller 80, in particular, may be part of the measurement and control unit 42 described above.

To introduce the irradiation targets 16 into the decay station 30 from the instrumentation pipe system 12, the locking element 70 occupies the unlocked position, and the latch 72, accordingly, occupies the retracted position.

Decay station 30 further includes an input counter 96 located at the inlet 56 of the decay pipeline and configured to count the number of irradiation targets 16 passing by the input counter 96. Thus, the input counter 96 is configured to count the number of irradiation targets 16 entering or exiting disintegration pipeline 52 through the disintegration pipeline inlet 56.

The input counter 96 is a device capable of detecting the passage of an irradiation target 16 in front of the input counter 96. The counter is particularly selected from inductive sensors capable of measuring a change in the inductive or dielectric field of a passing irradiation target 16, pressure sensors capable of measuring a pressure difference arising when passing the irradiation target 16, optical sensors capable of optically detecting the passage of the irradiation target 16, such as laser sensors or contrast sensors, dielectric sensors or radiation sensors capable of detecting differences in radiation intensity occurring when passing the irradiation target 16.

The number of irradiation targets 16 counted by the input counter 96 is preferably compared with a preset value to confirm that the required number of irradiation targets 16 has entered or exited the decay station 30 through the decay conduit inlet 56.

According to the embodiment of the invention shown in FIG. 1 - 3, the decay station 30 additionally contains an output stopper 84 located at its output end and designed to prevent the movement of irradiation targets 16 from the decay station 30 through the output 58 of the decay pipeline. The output stop 84 ensures that the irradiation targets 16 are held in a predetermined position inside the disintegration conduit 52 when there is no force directed on the irradiation targets 16 in the direction of the disintegration conduit inlet 56, in particular, in the absence of a flow of compressed gas directed from the disintegration conduit outlet 58 towards the inlet 56 pipeline decay.

According to the first embodiment of the invention, the disintegration conduit 52 is inclined downward from the inlet 56 to the outlet 58, due to which the irradiation targets 16 are driven by gravity against the outlet stopper 84, which also helps to keep the irradiation targets 16 in a predetermined position in the disintegration conduit 52.

The exit stop 84 can be moved between a locking position in which it prevents movement of irradiation targets 16 from the decay station 30 through the decay conduit outlet 58, and an unlocking position in which it allows movement of the irradiation targets 16 from the decay station 30 through the disintegration conduit outlet 58.

In the locking position, the outlet stopper 84 preferably allows gas flow.

The output stopper 84 has a design similar to that of the locking element 70 of the input distributor 68. For example, said stopper includes a locking pin 86 configured to extend radially into the decay conduit 52 to a locking position of the output stopper 84 to prevent movement of the irradiation targets 16, and also includes an actuator a locking pin mechanism 88 for moving the locking pin 86 between a locking position and an unlocking position.

In particular, the locking pin 86 includes a drive end coupled to the locking pin actuator 88 and a free end opposite the drive end. In the extended position of the stopper 84, the free end of the stopper pin 86 abuts the inner surface of the disintegration pipeline 52. In the extended position, the locking pin 86 extends from one side of the decay line 52 to the opposite side along the diameter of the decay line 52. In particular, the length of the locking pin 86 is greater than or equal to the diameter of the disintegration conduit 52.

In the retracted position, locking pin 86 is preferably retracted into housing 50 and does not protrude into disintegration line 52.

The locking pin actuator 88 is, for example, a pneumatic, magnetic, or hydraulic actuator.

Optionally, the disintegration station 30 also includes an inlet stopper 90 located at the inlet 56 of the disintegration conduit upstream of the inlet distributor 68 when considering the flow of irradiation targets 16 from the inlet towards the outlet. The inlet stop 90 is designed to prevent the movement of irradiation targets 16 from the decay station 30 through the inlet 56 of the decay pipeline and, in particular, back into the pipe system 12 of the control equipment.

The input stopper 90 has a design similar to that of the output stopper 84, with the only difference that in the locked position it prevents the movement of irradiation targets 16 from the decay conduit 52 through its input.

Optionally, the disintegration station 30 further includes an output distributor 92 located at the disintegration conduit outlet 58 and adapted to release only a predetermined number of irradiation targets 16 at a time from the disintegration station 30 through the disintegration conduit outlet 58, while retaining the remaining irradiation targets 16 in the disintegration conduit 52.

The output distributor 92 is shown only schematically in FIG. 3 and not shown in FIG. 1. It has a structure similar to that of the inlet distributor 68, except that the locking element and the latch of the outlet distributor 92 are located in series in the direction from the outlet 58 of the disintegration pipeline to the inlet 56 of the disintegration pipeline. In addition, in the output distributor 92, the inlet and outlet are arranged in the reverse order compared to the input distributor 68, and instead of the first compressed gas supply unit 60, a second compressed gas supply unit 62 is used, and the controller 80 is configured to drive the second supply unit 62 compressed gas to create a flow of compressed gas through the pipeline 52 disintegration.

If necessary, the decay station 30 further includes an output counter 98 located at the decay pipeline outlet 58 and configured to count the number of irradiation targets 16 passing by it, that is, exiting the decay pipeline 52 through the decay pipeline outlet 58. The output counter 98 is a device capable of detecting the passage of irradiation targets 16 in front of the output counter 98. It is of a similar design to the input counter 92.

In addition, if necessary, the decay station 30 contains at least one and, for example, a plurality of intermediate irradiation target counters 100 located along the decay pipeline 52 between the decay pipeline inlet 56 and the decay pipeline outlet 58 and configured to count the number of irradiation targets 16, located in the pipeline 52 decay at a given time.

Sensors selected in particular from temperature sensors and gamma radiation measurement sensors can serve as intermediate counters 100 of irradiation targets.

In particular, the irradiation targets 16 activated in the core have a certain temperature, thus, by measuring the temperature, the presence of irradiation targets 16 in the decay line 52 can be detected. In particular, the irradiation target 16 is detected in the core if the temperature measured by the temperature sensor is greater than or equal to a predetermined threshold depending, in particular, on the characteristics of the radionuclides contained in the irradiation targets 16.

Alternatively, the presence of an irradiation target 16 in the decay line 52 may be detected by measuring gamma radiation, with each irradiation target 16 located in the decay line 52 emitting a specific gamma radiation depending, in particular, on the characteristics of the radionuclides contained in the irradiation target 16 and in the shell of the irradiation target 16.

According to one example, schematically shown in FIG. 3, the decay station 30 includes one intermediate irradiation target counter 100 facing each irradiation target 16 in the decay line 52. In particular, adjacent intermediate irradiation target counters 100 are spaced along the length of the decay pipeline 52 at a distance corresponding to the length of the irradiation target 16 to be placed in the decay pipeline 52. For example, adjacent intermediate irradiation target counters 100 are spaced apart by a distance of 60 mm to 70 mm, eg about 70 mm.

Alternatively, the number of intermediate irradiation target counters 100 may be less than the total number of irradiation targets 16 in the decay line 52, particularly if homogeneous material is activated in all irradiation targets 16. In fact, if homogeneous material is activated in the irradiation targets 16, then the measurement results made by the intermediate counters 100 on some irradiation targets 16 can be extrapolated to other irradiation targets 16.

Intermediate irradiation target counters 100 are used as a means to confirm the counting performed by input counter 96 and/or optional output counter 98. Intermediate counters differ from input counter 96 and optional counter 98 in that input counter 96 and output counter 98 are countable moving targets, while the intermediate counters 100 are configured to count stationary targets located in the decay pipeline 52.

According to the embodiment of the invention shown in FIG. 3, the disintegration station 30 further includes an output radiation sensor 102 adapted to measure radiation emitted by an irradiation target 16 located in the disintegration conduit 52 at the disintegration conduit outlet 58 and, for example, abutting the output stopper 84.

The output radiation sensor 102 may be located in the wall of the housing 50 or outside the housing 50 of the decay station 30, in particular above or below the housing 50.

The distance between the output radiation sensor 102 and the exit stopper 84, when viewed along the decay conduit 52, is less than or equal to the length of one irradiation target 16.

According to the embodiment of the invention shown in FIG. 3, the output radiation sensor 102 is located in a fixed position at the output 58 of the decay pipeline.

If necessary, the decay station 30 additionally contains at least one or, for example, a plurality of intermediate radiation sensors 104 configured to measure the radiation emitted by the irradiation targets 16 at different sections along the length of the decay pipeline 52 between the input 56 and the output 58.

For example, decay station 30 includes one radiation sensor 102, 104 facing each irradiation target 16 in decay line 52. Adjacent radiation sensors 102, 104 are, in particular, spaced apart from each other by a distance corresponding to the length of the irradiation target 16 located in the decay pipeline 52. For example, adjacent radiation sensors 102, 104 are separated by a distance of from 60 mm to 70 mm and, for example, equal to about 70 mm.

Optional intermediate radiation sensors 104 are preferably located in a wall of the housing 50 or outside the housing 50 of the decay station 30, particularly above or below the housing 50.

Radiation sensors 102, 104 can serve, in particular, to confirm a reduction in radiation intensity, for example dose rate, below a predetermined threshold, which guarantees the safety of movement of activated irradiation targets 16 from the decay station 30 to the irradiation target unloading system 27, which is less protected, than station 30 decay.

According to an embodiment of the invention using one radiation sensor 102, 104 for each specific radiation target 16, it is possible to detect deviations in the activation level of individual radiation targets 16, compared to an embodiment of the invention using a smaller number of radiation sensors 102, 104.

According to one alternative embodiment of the invention, the total number of radiation sensors 104 may be less than the total number of irradiation targets 16 in the decay line 52, in particular if homogeneous material is activated in all irradiation targets 16. In fact, if homogeneous material is activated in the irradiation targets 16, the measurements made by the radiation sensors 102, 104 on some irradiation targets 16 can be extrapolated to other irradiation targets 16.

The output radiation sensor and/or intermediate radiation sensors 104 may be a gamma radiation sensor.

Intermediate radiation sensors 104 may be used as intermediate radiation target counters 100. In particular, the intermediate radiation sensors 104 may be gamma radiation sensors, which may be used to both measure the radiation emitted by the irradiation target 16 and to detect the target.

According to one alternative embodiment (not shown), the output radiation sensor 102 may move along the decay line 52 between the decay line inlet 56 and the decay line outlet 58, allowing the radiation emitted by the irradiation targets 16 to be measured at various points along the length of the line 52. decay. The output radiation sensor 102 may, in particular, be moved to a position at the decay conduit outlet 58 to measure radiation emitted by an irradiation target 16 located in the decay conduit 52 at the decay conduit outlet 58, wherein, in particular, the output radiation sensor 102 may be adjacent to output stop 84.

The radiation sensors 102, 104 are configured to monitor the decay of irradiation targets 16 contained in the decay station 30. Thanks to these sensors, only irradiation targets 26 with a sufficient degree of decay are unloaded from the decay station 30, that is, when the radiation emitted by the targets is below a predetermined threshold.

The radiation sensors 102, 104 are, in particular, configured to measure the radiation dose rate emitted by the irradiation targets 16.

The controller 80 is preferably adapted to regulate movement of the output stop 84 from a locked position to an unlocked position based on measurements made by the output radiation sensor 102, with the output stop 84, for example, moving to the unlock position when the measured radiation is equal to or lower than a predetermined threshold.

In the decay station 30, radioactive decay of the irradiation targets 16 occurs before moving the irradiation targets 16 to a less protected area of the installation 6, such as the irradiation target unloading system 27, which allows the irradiation targets 16 to be unloaded from the decay station 30 only when the radiation emitted by the irradiation targets 16 , and in particular their dose rate, has decreased to a predetermined level.

The disintegration station 30' according to the second embodiment of the invention is shown in FIG. 4. This disintegration station 30' has the same characteristics as the above-described disintegration station according to the first embodiment of the invention, the only difference being the shape of the disintegration station 30'.

According to this embodiment of the invention shown in FIG. 4, the disintegration line 52 is not straight as in the first embodiment of the invention. In the second embodiment of the invention, the disintegration line 52 is U-shaped. Said disintegration conduit includes a first section 110, a second section 112, and a lower portion 114 formed at the junction between the first section 110 and the second disintegration conduit section 112. The first and second sections 110, 112 of the breakdown conduit extend upward from the bottom portion 114.

According to the second embodiment of the invention, the housing 50 of the decay station 30' has a U-shape, and the walls of the housing 50 delimiting the decay pipeline 52 are, in particular, formed by a radiation shield 54. The U-shape of the decay pipeline 52 ensures safe storage of irradiation targets 16 there are 52 decays in the pipeline.

According to a second embodiment of the invention, the disintegration station 30' is preferably configured to receive spherical irradiation targets 16. The diameter of the spherical irradiation targets 16 is particularly between 1 and 3 mm and is preferably about 1.7 mm.

The irradiation target unloading system 27 will be described in more detail below with reference to FIG. 1.

As shown in FIG. 1, the irradiation target discharging system 27 includes an outlet conduit 120 having an inlet end connected to a conduit outlet 58 of the disintegration station 30, and a target output port 124 configured to be connected to a target storage container 34.

The linear order of the irradiation targets 16 discharged from the decay station 30 is maintained in the outlet conduit 120.

Preferably, the outlet conduit 120 is located outside the reactor core 10, but preferably within accessible areas within the reactor containment.

The outlet port 124 is located at the free end of the outlet conduit 120. According to the embodiment of the invention shown in FIG. 1, the outlet port includes a shut-off valve 126 to seal the outlet conduit 120.

The outlet port 124 may be located above the storage container 34 to be filled, or may be configured to be connected and/or releasably connected to a corresponding storage container 34. At least one storage container 34 preferably has a shield to minimize operator exposure to radiation emitted by the activated radiation targets 16 .

The system 27 for unloading irradiation targets additionally contains an unloading limiter 128, configured to prevent the movement of irradiation targets 16 into the storage container 34. The discharge stop 128 is movable between a locking position, in which it prevents the irradiation targets 16 from moving into the storage container 34, and a unlocking position, in which it allows the irradiation targets 16 to move into the storage container 34. The discharge stop 128 is, for example, a magnetically or mechanically actuated stop member, preferably a pin, that crosses the discharge conduit 120.

The irradiation target unloading system 27 may comprise, instead of or upstream of the unloading limiter 128, an unloading distributor (not shown) located at the exit port 124 and adapted to discharge only a predetermined number of irradiation targets 16 at a time into a storage container 34, more specifically, a dispenser. The unloader discharges the irradiation targets 16 closest to the exit port 124 while retaining the remaining targets in the outlet conduit 120. Preferably, the predetermined number of irradiation targets 16 to be unloaded is equal to one target, so the discharge distributor ensures that only one irradiation target 16 is unloaded from the outlet conduit at a time 120. The design of the additional unloading distributor is similar to the design of the input distributor 68 of the decay station 30, and therefore will not be described in detail.

The exhaust pipe 120 according to the embodiment of the invention shown in FIG. 1 is essentially straight forward. In this embodiment, the inclination of the outlet conduit 120 is selected such that the irradiation targets 16 are discharged from the outlet conduit 120 by gravity when the discharge stop 128 is in the unlocked position.

According to one alternative embodiment (not shown), the exhaust conduit 120 is shaped like an inverted U and includes a first section, a second section, and a top portion formed at the junction of the first and second exhaust conduit sections. The top portion is the highest point of the exhaust conduit 120, and the first and second sections of the exhaust conduit are directed downward from the top portion. A similar U-shaped outlet pipe is described, for example, in patent application EP 3326175 A1 filed by the applicant.

It should be noted that other profiles of the exhaust pipe 120 are possible.

The irradiation target discharge system 27 further includes at least one compressed gas inlet 130 provided in the wall of the outlet conduit 120. According to the embodiment of the invention shown in FIG. 1, the compressed gas inlet 130 is located between the shut-off valve 126 and the discharge restrictor 128. Said opening is connected to a source of compressed gas, for example a source 63 of compressed gas, and is part of the drive system 25 for the targets of the installation 6.

If necessary, the irradiation target unloading system 27 further includes a radiation sensor 134 adapted to measure the radiation emitted by the irradiation targets 16 located in the outlet conduit 120, and, in particular, the dose rate of the radiation emitted by the irradiation targets 16 located in the outlet conduit 120.

If necessary, the system 27 for unloading irradiation targets may contain an unloading counter 140, configured to count the number of irradiation targets 16 moving from the disintegration station 30 into the outlet pipeline. The unloading counter 140 is configured to count the number of irradiation targets 16 passing by the unloading counter 140. The discharge counter 140 is a device capable of detecting the passage of irradiation targets 16 in front of the discharge counter 140 . The discharge counter 140 has the same structure as the input counter 96 described above.

If necessary, the installation 6 further includes a counter 144 targets of the pipe system of control equipment, located at the entrance of the pipe system of control equipment 12 downstream of the diverter 30 relative to the direction of movement of the targets 16, 18 in the pipe system of control equipment 12, and configured to count the number of irradiation targets 16 or dummy targets 18 moving into or out of the instrumentation tubing system 12. The tubular instrumentation system target counter 144 is, in particular, a device capable of detecting the passage of a magnetic target, such as a decoy 18, in front of the counter 144.

The instrumentation tubing target counter 144 is preferably located upstream of an instrumentation tubing 12 shut-off valve, said shutoff valve being configured to seal the instrumentation tubing 12 as a tight seal.

If necessary, the irradiation target supply system 12 may also include a target counter (not shown) located upstream of the diverter 30 relative to the direction of movement of the targets 16, 18 into the instrumentation tubing system 12.

In the above description, a decay station 30 connected to a nuclear reactor core instrumentation piping system 12 was considered. However, depending on the needs, said decay station 30 may be coupled to other components of the nuclear reactor core structure besides the instrumentation piping system 12, which is advantageous.

The diverter 32 according to the first embodiment of the invention will be described next with reference to FIGS. 5.

As shown in FIG. 5, the divertor 32 according to the first embodiment of the invention includes:

- the first connector 150, intended for connection with the system 27 for unloading irradiation targets;

- a second connector 152 intended for connection with the system 21 for supplying irradiation targets;

- a third connector 154, designed for connection with the pipe system 12 of the control and measuring equipment.

In particular, each connector 150, 152, 154 is intended for connection with a corresponding pipeline for moving targets 16, 18. For example, the first connector 150 is intended for connection with the pipeline 52 of the disintegration station 30, the second connector 152 is intended for connection with the supply pipe 23 of the system 21 supply of irradiation targets, and the third connector 154 is intended for connection with the pipeline 13 of the pipe system 12 of the control and measuring equipment.

The first connector 150 can be connected to the irradiation target unloading system 27 either directly, that is, without intermediate systems between the irradiation target unloading system 27 and the divertor 32, or, for example, through a decay station 30, as shown, for example, in FIG. 1.

The third connector 154 is located at a distance from the first connector 150 and the second connector 152 in a horizontal direction. Moreover, according to the embodiment of the invention shown in FIG. 5, the first connector 150 and the second connector 152 are substantially aligned in the vertical direction. The third connector 154, for example, is located at an intermediate height between the heights of the first and second connectors 150, 152.

The targets 16, 18 are moved through the divertor 32 by the target drive system 25 described above.

The diverter 32 includes at least one diverter conduit 156 movable between a first position in which it connects one of the connectors, namely the first connector 150 or the second connector 152, with a third connector 154, determining the path of movement of the targets 16, 18 from one of connectors, namely the first connector 150 or the second connector 152, to the third connector 154, and a second position in which it does not connect one of the connectors, namely the first connector 150 or the second connector 152, to the third connector 150.

More specifically, according to the embodiment of the invention shown in FIG. 5, diverter 32 includes a first divertor conduit 156A and a second divertor conduit 156B.

The geometry of the divertor conduits 156A, 156B is selected to minimize the size of the divertor 32. In particular, each divertor conduit 156A, 156B is formed such that it causes two changes in direction along its length of the targets 16, 18 designed to circulate therein. This particular shape of the divertor conduit 156A, 156B provides a more compact diverter 32, compared, for example, with an embodiment in which the diverter conduits 156A, 156B are straight along their entire length. The compactness of the diverter is of great importance because the space available for the divertor 32 inside a nuclear reactor is limited.

Each change in direction occurs at a distance from the longitudinal ends of the divertor conduits 156A, 156B.

Specifically, each diverter conduit 156A, 156B includes substantially straight end sections 158, 159 at each end of the divertor conduit 156A, 156B and an intermediate section 160 located between the end sections 158, 159. The end sections 158, 159 are preferably parallel to each other and, in particular, extend substantially horizontally. For example, the central axes of the end sections 158, 159 are offset from each other in a direction perpendicular to their longitudinal direction, and in particular in the vertical direction. The offset x is strictly greater than zero and, for example, ranges from 10 to 50 mm.

According to the embodiment of the invention shown in FIG. 5, the intermediate section 160 is curved. Preferably, in each diverter conduit 156A, 156B, the transition from the curved intermediate section 160 to each substantially straight end section 158, 159 is smooth, that is, without corners. Preferably, according to this embodiment, the central axis of the divertor pipeline 156A, 156 is straight. According to the embodiment of the invention shown in FIG. 5, the intermediate section 160 has a smooth curve between its ends. The smooth bend of the divertor pipeline 156A, 156B and the absence of angles along its length allows the targets 16, 18 to be smoothly moved along the divertor pipelines 156A, 156B, despite a change in the direction of movement.

In the example in FIG. 5, the intermediate section 160 preferably has a concave portion and a convex portion, between which there is a transition point. Specifically, the transition point is the geometric midpoint of the central axis of the intermediate section 160.

The radius of curvature of each divertor pipeline 156A, 156B and its diameter are selected depending on the length and diameter of the targets 16, 18 so as to ensure smooth movement of the targets 16, 18 along the divertor pipelines 156A, 156B.

Preferably, the radius of curvature of each diverter pipeline 156A, 156B at the junction of the intermediate section 160 with the end sections 158 is from 200 to 800 mm. Tests conducted by the inventors have shown that the divertor 32, manufactured with the specified radius of curvature of the divertor conduits, is small in size, while the movement of the targets 16, 18 along the divertor conduits 156A, 156B is essentially unimpeded. This geometry is particularly preferred when using cylindrical targets 16, 18 with a circular base having a diameter of 9 mm to 12 mm and a length of 9 mm to 80 mm.

According to one alternative embodiment (not shown), the intermediate section 160 is straight rather than curved as shown in FIG. 5 and described above. The advantage of this diverter variant is that it is simpler to manufacture compared to a divertor having a curved intermediate section 160.

To ensure smooth movement of the targets 16, 18 along the divertor pipelines 156A, 156B, depending on the length and diameter of the targets 16, 18, for each divertor pipeline 156A, 156B, the absolute value of the angle between the direction of the end sections 158, 159 and the central axis of the intermediate section 160 is selected , as well as the diameter of the divertor pipeline 156A, 156B.

According to this embodiment, for each diverter pipeline 156A, 156B, the absolute value of the angle between the direction of the end sections 158, 159 and the central axis of the intermediate section 160 is from 2° to 5°. Tests conducted by the inventors have shown that the diverter 32, manufactured with the specified angle of inclination of the intermediate section 160, is small in size, while the movement of the targets 16, 18 along the divertor conduits 156A, 156B is essentially unimpeded. This geometry is particularly preferred when using cylindrical targets 16, 18 with a circular base having a diameter of 9 mm to 12 mm and a length of 9 mm to 80 mm.

The first and second diverter conduits 156A, 156B are preferably located symmetrically with respect to the midplane between the two conduits 156A, 156B. The first diverter conduit 156A, for example, extends downward from the first connector 150 to the third connector 154, while the second diverter conduit 156B extends upward from the second connector 152 to the third connector 156.

The first diverter conduit 156A connects the first connector 150 to the third connector 154 in a first position, defining a path of movement of the targets 16, 18 from the first connector 150 to the third connector 154. In this position, as shown in FIG. 1 - 4, the first diverter pipeline 156A determines the trajectory of the targets 16, 18 between the decay station 30 and the pipe system 12 of the control and measuring equipment. In the position of the divertor 32 shown in FIG. 5, the first diverter pipeline 156A is in the first position.

More specifically, in the first position, the ends of the first diverter conduit 156A are aligned with the first connector 150 and the third connector 154, respectively.

In the second position of the first divertor conduit 156A, the first divertor conduit 156A does not connect the first connector 150 to the third connector 154. For example, in the second position, the ends of the first divertor conduit 156A are not aligned with the first connector 150 and the third connector 154. Therefore, no movement of the targets is possible. 16, 18 between the first connector 150 and the third connector 154 and, accordingly, according to the present embodiment, between the disintegration station 30 and the instrumentation pipe system 12.

A second diverter conduit 156B connects the second connector 152 to the third connector 154 in its first position, defining a path of movement of the targets 16, 18 from the second connector 152 to the third connector 154. In this position, as shown in FIG. 1 - 4, the second diverter pipeline 156B determines the trajectory of the targets 16, 18 between the irradiation target supply system 21 and the control and measuring equipment pipe system 12.

More specifically, in the first position, the ends of the second diverter conduit 156B are aligned with the second connector 152 and the third connector 154, respectively.

In the second position of the second divertor conduit 156B, the second divertor conduit 156B does not connect the second connector 150 to the third connector 154. For example, in the second position, the ends of the second divertor conduit 156B are not aligned with the second and third connectors 152, 154. Therefore, no movement of the targets is possible. 16, 18 between the second connector 152 and the third connector 154 and, accordingly, according to the present embodiment, between the irradiation target delivery system 21 and the instrumentation tubing system 12.

As shown in FIG. 5, the second diverter pipeline 156B occupies the second position.

The configuration of the diverter 32 shown in FIG. 5 corresponds to the first position of the diverter 32. In the position shown in FIG. 5, the divertor 32 sets the trajectory of the targets 16, 18 from the decay station 30 to the pipe system 12 of the control and measuring equipment.

The configuration of the divertor 32 in which the first divertor conduit 156A occupies the second position and the second divertor conduit 156B occupies the second position corresponds to the second position of the divertor 32. In this position, the diverter 32 determines the path of movement of the targets 16, 18 between the irradiation target supply system 21 and the pipe system 12 control and measuring equipment.

Due to its design, the diverter 32 in the first position allows the targets 16, 18 to move directly from the pipeline connected to the first connector 150, for example from the decay pipeline 52, into the pipeline connected to the third connector 156, for example into the pipeline 13 of the pipe system 12 equipment, that is, said diverter 32 in the first position provides direct communication between said pipelines.

In the second position, the diverter 32 ensures the movement of targets 16, 18 directly from the pipeline connected to the second connector 152, for example, from the supply pipeline 23 of the irradiation target supply system 21 into the pipeline connected to the third connector 156, for example, into the pipeline 13 of the control pipe system 12 -measuring equipment, that is, the specified diverter 32 in the second position provides direct communication between the specified pipelines.

Diverter 32 further includes an actuator configured to move at least one divertor conduit 156 from a second position to a first position and/or from a first position to a second position, for example, through a translational or rotary motion.

According to the embodiment of the invention shown in FIG. 5, the actuator includes a piston 168. In the illustrated embodiment, the piston 168 acts on the first and second diverter conduits 156A, 156B.

The piston 168 may move between a first position (as shown in FIG. 5) in which the first diverter line 156A is in a first position and the second diverter line 156B is in a second position, and a second position (not shown) in which the first diverter line 156A is in a second position. the second position, and the second diverter pipe 156B occupies the first position. The diverter 32 is configured such that the first diverter line 156A occupies a first position when the second diverter line 156B occupies a second position, and vice versa.

The piston 168 is preferably a pneumatic piston.

More specifically, according to the embodiment of the invention shown in FIG. 5, the diverter 32 has a housing 170 including a first wall 172 and a second wall 174 that are spaced apart from each other, with diverter diverter conduits 156A, 156B extending from the first wall 172 to the second wall 174. According to the embodiment of the invention shown in fig. 5, the first and second walls 172, 174 are substantially parallel. The first and second connectors 150, 152, for example, are located on the first wall 172, and the third connector 156 is located on the second wall 174.

The piston 168 is located in the housing 170 with the possibility of sliding along the specified housing 170 in the direction X of movement. The movement direction X is in particular perpendicular to the axes of the end sections 158, 159 of the diverter conduits 156A, 156B and, more specifically, is vertical.

The first and second chambers 176, 178 are defined between the piston 168 and the housing 170, and said chambers 176, 178 are located on both sides of the piston 168 along the direction X of movement of the piston 168.

The diverter housing 170 further includes an inlet port 180 for supplying pressurized fluid to the first chamber 176 to move the piston 168 from a first position to a second position, and an outlet port 182 for releasing air from the second chamber 178 while moving the piston 168 .

The piston 168 is configured to return to the first position if there is no fluid under pressure in the first chamber 176. According to this embodiment of the invention, the first position of the piston 168 corresponds to the passive safety position, since it connects the instrumentation tubing 12 to the decay station 30 and, therefore, to the area having enhanced radiation protection.

According to the embodiment of the invention shown in FIG. 5, the first diverter conduit 156A is positioned above the second divertor conduit 156B, wherein the piston 168 is movable upward from a first position to a second position and downwardly from a second position to a first position.

The divertor 32 preferably includes sealing means 177 configured to seal the space between the piston 168 and the first and second walls 172, 174 of the diverter housing 170. The sealing means 177 may be, for example, O-rings extending around the periphery of the piston 168.

The largest dimension of the piston 168 in a plane perpendicular to the direction of movement of the piston 168 depends on the offset "x" between the end sections 158, 159 of the conduits 156A, 156B and on the geometry of each of the conduits 156A, 156B, in particular, on the angle between the end sections 158, 159 and the intermediate section 160 or from the radius of curvature at the connection points of the intermediate section 160 with the end sections 158, 159.

The diverter housing 170 is in particular cylindrical, for example with a circular base. In this case, the first and second connectors 150, 152 are formed, for example, on one of the cylinder bases, and the third connector 154 is formed on the opposite cylinder base. The piston 168 is shaped to match the shape of the divertor housing 170, particularly cylindrical with a circular base, the diameter of the base substantially corresponding to the diameter of the divertor housing 170.

According to this embodiment of the invention, the actuator provides a supply of compressed gas to move the piston 168.

The switching unit 40 provides a controlled supply of a predetermined amount of compressed gas to the first chamber 176 to move the piston 168 from a first position to a second position and, accordingly, move the diverter 32 to a second position. The piston 168 moves from the second position to the first position when there is no supply of compressed gas to the first chamber 176.

Next, the diverter 32' according to the second embodiment of the invention will be described with reference to FIGS. 6. In the said drawing, elements identical to those shown in FIG. 5, the elements of the divertor 32 according to the first embodiment of the invention are designated by similar reference numerals.

The divertor 32' according to the second embodiment of the invention differs from the divertor 32 according to the first embodiment in that there is only one divertor conduit 156. More specifically, the divertor conduit 156 connects the first connector 150 to the third connector 154 in the first position, and the second connector 152 to the third connector 154 in the second position.

According to this embodiment of the invention, the diverter pipeline 156 can be rotated between a first position and a second position.

In particular, in this embodiment, the diverter 32' includes a support 180, such as a plate, on which the first and second connectors 150, 152 are located, and a rotatable conduit holder 182, such as a disk, mounted on the support 180 and capable of rotating relative to it about an axis R rotation perpendicular to the plane of the support 180.

One end 184 of the diverter conduit 156 is mounted on a rotating conduit holder 182 such that the rotational movement of the rotating holder 182 causes the divertor conduit 156 to move between a first position and a second position. The rotation axis R is aligned with the axis of the end section 159 of the divertor conduit 156 located opposite the end of the divertor conduit 156 mounted on the rotary conduit holder 182 .

Depending on the angular position of the rotary holder 182 of the pipeline, the end section 158 of the divertor pipeline 156, closest to the support 180, is located on the same axis with the first connector 150, or with the second connector 152, respectively, determining the trajectory of movement of the target 16, 18 from the first connector 150 to to a third connector 154, or from a second connector 152 to a third connector 154.

The position of the end section 159 of the diverter pipeline 156 does not change when the rotary holder 182 of the pipeline is rotated.

For example, according to the embodiment of the invention shown in FIG. 6, the first connector 150 is positioned above and vertically aligned with the second connector 152 in the vertical direction, rotation of the divertor conduit 156 about the 180° rotation axis R in the first rotation direction D causes the divertor conduit 156 to move from the first position to the second position, and the rotation of the divertor the conduit 156 about the 180° rotation axis R in a second direction opposite to the first rotation direction D causes the divertor conduit 156 to move from the second position to the first position.

The third connector 154, in particular, is rigidly attached to a fixed support structure (not shown). The fixed support structure is formed, for example, by a plate which, in particular, extends parallel to the plate forming the support 180. The fixed support structure and the support 180, in particular, may be part of a diverter housing, further comprising at least one connecting wall connecting the fixed support structure support structure 180. The diverter housing may be similar to the housing shown in FIG. 5.

The end section 159 of the divertor conduit 156 is connected to the third connector 154 by means of an intermediate connector 185, which allows the diverter conduit 156 to rotate relative to the third connector 154. The intermediate connector 185 is, for example, a quick-release coupling system containing two separate parts 185A, 185B capable of rotating relative to each other and thus provide rotation of the diverter pipeline 156 relative to the third connector 154.

According to this embodiment, the actuator, for example, includes a motor for rotating the divertor pipeline 156 in a first or second rotation direction through a predetermined angle to move between the first position and the second position. In particular, the motor may be coupled to the rotary conduit holder 182 by means of an adapter to enable rotation of the rotary conduit holder 182 through a predetermined angle in a first or second rotation direction.

The switching unit 40 is adapted to control the motor as required.

The geometry of the divertor pipeline 156 is identical to the described geometry of the divertor pipelines 156A, 156B.

The method for producing activated irradiation targets 16 using the above-described installation 6 includes the following steps:

- move 200 non-activated irradiation targets 16 in an amount q ₁ into the pipe system 12 of control and measuring equipment from the irradiation target supply system 21;

- irradiate 202 non-activated irradiation targets 16 in an amount q ₁ with a neutron flux in the pipe system 12 of control and measuring equipment for a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets 16 in an amount q ₁ , and the predetermined irradiation time d ₁ is equal to or less than the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into the desired radionuclide; And

- move 204 irradiation targets 16 in an amount q ₁ from the pipe system 12 of control and measuring equipment to the decay station 30;

- unloading 214 at least some of the irradiation targets 16 from the decay station 30 into the target storage container 34, in particular through the unloading system 27.

The method according to the first embodiment will be described in more detail below with reference to FIG. 7.

According to a first embodiment of the invention, the predetermined irradiation time d ₁ is strictly less than the minimum activation time required to completely convert the precursor material contained in the irradiation targets 16 into the desired radionuclide.

Therefore, the first number q ₁ of irradiation targets 16 obtained at the end of step 204 represents the first number q ₁ of partially activated irradiation targets 16. At step 206, said first number q _{1 of} partially activated irradiation targets 16 is transferred from the instrumentation tube system 12 to the decay station 30.

The method according to this embodiment of the invention between step 206 and step 214 further includes the following steps:

- move 208 non-activated irradiation targets 16 in an amount q ₂ from the irradiation target supply system 21 to the pipe system 12 of control and measuring equipment;

- move 210 partially activated irradiation targets 16 in an amount q ₁ from the decay station 30 back to the pipe system 12 of control and measuring equipment;

- irradiate 212 neutron flux partially activated irradiation targets 16 in an amount q ₁ and non-activated irradiation targets 16 in an amount q ₂ in the pipe system 12 of control and measuring equipment for a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets 16 in an amount of q ₁ and partially activated irradiation targets 16 in an amount of q ₂ .

Preferably, at step 214, the irradiation targets 16 discharged from the decay station 30 into the target storage container 34 are fully activated irradiation targets 16.

The above "moving" steps are performed by the target drive system 25.

At step 210, the partially activated irradiation targets 16 are moved from the decay station 30 through an input dispenser 68, which releases only a predetermined number A of irradiation targets 16 at a time, while the remaining irradiation targets 16 are retained in the decay station 30.

In particular, to release a predetermined number A of irradiation targets 16, the following steps are performed:

- step a1 of moving the locking element 70 from the unlocking position to the locking position by means of the first actuator 74;

- step a2 of actuating the compressed gas supply unit 60 to obtain a flow of compressed gas supplied to the disintegration pipeline 52 through the pipeline outlet 58 for pushing the irradiation targets 16 located in the disintegration pipeline 52 to the pipeline inlet 56 until it stops against the shut-off element 70 occupying lock position;

- step a3 of moving the latch 72 by means of the second actuator 76 from the retracted position to the extended position, in which the latch 72 abuts the irradiation target 16 located in the decay pipeline 52;

- step a4 of moving, by means of the first actuator 74, the locking element 70 from the locking position to the unlocking position, so that, under the action of the compressed gas flow, a predetermined number of irradiation targets 16, that is, irradiation targets 16 located downstream of the latch 72 relative to the direction of the compressed gas flow , were forced out of the decay pipeline 52 through the inlet 56 of the decay pipeline, while the remaining irradiation targets 16, i.e. the irradiation target 16, to which the latch 72 is adjacent, and the irradiation targets 16 located upstream of them, are held in the decay pipeline 52 by means of the latch 72 located in the extended position.

Preferably, the compressed gas flow remains activated during all stages a2 to a4.

In particular, in step a3, the latch 72 abuts an irradiation target 16 located opposite the latch 72, with said irradiation target 16 extending on both sides of the latch 72 along the decay conduit 52.

The number q ₁ is preferably a multiple of a predetermined number A of irradiation targets, so that q ₁ =m*A, where m is an integer greater than or equal to one and, preferably, strictly greater than one.

If m is strictly greater than one, at step 210 the above sequence of steps a1 to a4 is repeated m times, as a result of which q ₁ irradiation targets 16 are released from the decay station 30.

In the preferred example, when the predetermined number A of irradiation targets 16 is equal to one, the above-described sequence of steps a1 to a4 is repeated q ₁ times.

Preferably, at step 210, the input counter 96 counts the number of irradiation targets 16 transferred from the decay station 30 to the instrumentation tube system 12, and the above-described sequence of steps a1 to a4 is repeated until the instrumentation tube system 12 the irradiation targets 16 in the amount of q ₁ will not be moved.

At step 210, partially activated irradiation targets 16 in the amount of q ₁ from the decay station 30 are moved to the control equipment finger 14 and are located in said control equipment finger 14 above the irradiation targets 16 in the amount q ₂ passed into the control equipment finger 14 equipment at step 208.

Consequently, at the end of step 210, the test finger 14 contains, in the bottom-up direction, a number of q ₂ unactivated irradiation targets and a number of q ₁ partially activated irradiation targets 16 .

Step 214 is the step of unloading from the decay station 30 fully activated irradiation targets 16 in an amount q ₁ .

At this stage, irradiation targets in an amount q ₁ are unloaded through the output 58 of the decay station 30 and supplied to the unloading system 27 by means of the drive system 25 for the targets.

According to one embodiment of the invention, at step 214, the output stopper 84 is in the unlocked position, and under the influence of a flow of compressed gas passing in the direction from the inlet 56 to the outlet 58 of the decay pipeline 52, the irradiation targets 16 move in the outlet pipeline 120 until it stops at the stopper. 128 unloads. Then, after unlocking the unloading limiter 128, the irradiation targets 16 can be unloaded into the corresponding unloading container 34.

In an embodiment of the invention in which the decay station 30 includes an output dispenser 92, irradiation targets in quantity q ₁ are discharged through the decay station output 58 in batches containing a predetermined number of targets in steps a1 to a4 described above, with the "input" being considered "output" and "output" is considered "input".

If necessary, the radiation, in particular the dose rate of radiation emitted by the number q ₁ of irradiation targets 16 located in the decay pipeline 52, is measured by the output radiation sensor 102 and/or additional intermediate radiation sensors 104 before unloading the irradiation targets 16 from the decay station 30, when In this case, the irradiation targets 16 are discharged only if the measured radiation, in particular the radiation dose rate, is below a predetermined threshold.

At step 214, only the number q ₁ of fully activated irradiation targets 16 is unloaded from the decay station 30. According to a preferred embodiment of the invention, the unloaded number q _{1 of} fully activated irradiation targets 16 corresponds to the number q ₁ of irradiation targets 16 located in the decay station 30 .

Preferably, the method includes, between steps 212 and 214, a step 216 of moving into the decay station 30 fully or partially activated irradiation targets 16 in an amount q ₁ and partially activated irradiation targets 16 in an amount q ₂ .

Step 216 is performed by the target drive system 25. At step 216, the target drive system 25 moves into the disintegration station 30, preferably, the first and second number of irradiation targets 16 until they stop against the output stop 84 of the disintegration station 30 or into the locking element of the output dispenser 92 if the device has an output dispenser 92.

At this stage, the linear order of the irradiation targets 16 is maintained, and therefore, the fully or partially activated irradiation targets 16 in the amount of q ₁ are located closer to the exit 52 of the decay pipeline than the partially activated irradiation targets 16 in the amount of q ₂ .

After step 216, q ₁ unactivated irradiation targets 16 are passed into the test tube system 12 (step 218), and q ₂ partially activated irradiation targets 16 are moved back into the test tube system 12 in steps a1 along a4, as described above, via the target drive system 25 (step 220).

At the end of step 220, the instrumentation finger 14 contains, from bottom to top, a number of q ₁ unactivated irradiation targets 16 and a number of q ₂ partially activated irradiation targets 16 .

After step 220, the method includes the step 222 of irradiating targets 16 contained in the control equipment finger 14 of the nuclear reactor core 10 with a neutron flux for a predetermined irradiation time d ₃ to obtain partially activated irradiation targets 16 in quantity q ₁ and fully activated targets. 16 irradiation in the amount of q ₂ .

Steps 216, 218, 220 and 222 may be repeated multiple times, each repetition resulting in a batch of fully activated irradiation targets 16. Each batch of fully activated irradiation targets 16 is unloaded from the decay station at step 214.

If necessary, the method includes the step of shifting the divertor 32 into the second configuration before performing steps 200, 208 and 218 of moving the irradiation targets 16 from the irradiation target supply system 21 into the pipe system 12 of the control and measuring equipment, as well as the step of shifting the divertor 32 from the second configuration to the first configuration before performing steps 206, 210 and 220 of moving the irradiation targets 16 from the instrumentation tube system 12 to the decay station 30.

Preferably, the input counter 96 at steps 206, 210, 216 and 220 counts the number of irradiation targets 16 being moved from the test tube system 12 to the decay station 30 or from the decay station 30 to the test tube system 12.

The amount of q ₁ is preferably equal to the amount of q ₂ .

It is preferable that the irradiation of targets 16 with a neutron flux in the core of a nuclear reactor lasts the same time, for example, d ₁ , d ₂ and d ₃ are the same.

According to one embodiment of the invention, each specified irradiation time is equal to half the minimum activation time required to completely convert the precursor material contained in the irradiation targets 16 into the desired radionuclide. In this case, the number q ₁ of irradiation targets 16 received at the end of step 212 and the number of irradiation targets 16 located at the top of the test equipment finger 14 at the end of step 222 constitute the number of fully activated irradiation targets 16. Thus, the frequency of removal of irradiation targets from installation 6 corresponds to half the activation time of the required radionuclide.

In fact, in all cases, the irradiation time may be 1/M of the minimum activation time to completely convert the precursor material contained in the irradiation targets 16 into the desired radionuclide. The integer number M is selected depending on the relationship between the required frequency of target extraction and the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into the required radionuclide. Thus, at the end of step 222, the test equipment finger 14 may contain irradiation targets 16 in M different stages of activation, with targets 16 of each batch in the core 10 having to be exposed to the neutron flux M times before complete activation. More precisely, at the end of step 212, a number q ₁ of irradiation targets 16 are obtained that are only partially activated, therefore, said irradiation targets 16 must be returned to the neutron flux test equipment finger 14 as many times as necessary to achieve the minimum time activation.

If necessary, the method further includes, after step 216 and before unloading the fully activated irradiation targets 16 at step 214, the step of holding the fully activated irradiation targets 16 in the decay station 30 for a decay time d ₄ .

The decay time d ₄ corresponds to the time required to reduce below a predetermined radiation threshold and, in particular, the dose rate emitted by the fully activated irradiation targets 16 in the amount q ₁ . According to one example, the decay time d ₄ is predetermined depending on the nature of the material contained in the irradiation targets 16 . According to one alternative embodiment of the invention, the decay time d ₄ is determined based on the results of radiation measurements and, in particular, dose rate, performed by the output radiation sensor 102 and/or additional intermediate radiation sensors 104.

According to this embodiment of the invention, step 214 is performed after a certain number of fully activated irradiation targets 16 have been kept in the decay station 30 for a decay time d ₃ .

According to a specific embodiment of the invention, a predetermined delivery interval of batches N of irradiation targets equal to half the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into the desired radionuclide, if necessary, can be increased by the decay time d ₄ required to reduce below a predetermined radiation threshold, in particular the dose rate emitted by the number q ₁ of fully activated irradiation targets 16,

In this particular embodiment of the invention, at all stages of irradiation, the predetermined irradiation time is 50% of the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into the desired radionuclide.

At method step 200, a batch N of non-activated irradiation targets 16 is transferred to the test equipment finger 14 from the irradiation target supply system 21.

At step 204, said batch N of non-activated irradiation targets 16 is subjected to irradiation with a neutron flux in the nuclear reactor core for a time equal to half the minimum activation time to completely convert the precursor material contained in the irradiation targets 16 into the desired radionuclide.

At step 206, said batch N of partially activated irradiation targets 16 is transferred to the decay station 30.

At batch step 208, a batch N of non-activated irradiation targets 16 from the irradiation target supply system 21 is transferred to the test equipment finger 14.

At step 210, a batch N of partially activated irradiation targets 16 is transferred to the test equipment finger 14 from the decay station 30, resulting in a batch N of non-activated irradiation targets 16 and a batch N of partially activated irradiation targets sequentially contained in the test finger in a bottom-up direction. 16 irradiation targets.

At step 212, the targets 16 contained in the control equipment finger 14 are irradiated with the neutron flux in the nuclear reactor core for a time equal to half the minimum activation time to completely convert the precursor material contained in the irradiation targets 16, that is, to obtain a batch N fully activated irradiation targets 16 and a batch of N partially activated irradiation targets 16.

At step 216, a batch N of fully activated irradiation targets 16 and a batch N of partially activated irradiation targets 16 are moved from the instrument finger 14 to the decay station 30, while the linear order of the irradiation targets 16 is maintained. Thus, the batch N of fully activated irradiation targets 16 is located closer to the output of the decay station 30 than the batch N of partially activated irradiation targets 16.

Then, at step 214, a batch N of fully activated irradiation targets 16 are unloaded into an unloading container 34. If necessary, the targets are held in the decay station 30 for a predetermined decay time d ₄ before being unloaded at step 214.

At step 218, a batch N of non-activated irradiation targets 16 is transferred to the test equipment finger 14 from the irradiation target supply system 21.

At step 220, a batch N of partially activated irradiation targets 16 located in the decay station 30 are transferred from the decay station 30 to the test equipment finger 14, resulting in the test equipment finger containing, from bottom to top, a batch N of non-activated targets 16 irradiation and batch N of partially activated irradiation targets 16.

At step 222, the targets 16 contained in the control equipment finger 14 are irradiated by the neutron flux in the nuclear reactor core for a time equal to half the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16, resulting in batch N of fully activated irradiation targets 16 and batch N of partially activated irradiation targets 16.

Steps 216 - 222 can be repeated as many times as necessary, with each repetition of these steps resulting in a batch of N fully activated irradiation targets 16, the production duration of which is equal to half the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into required radionuclide. At step 214, the specified batch, after an optional decay time d ₄ , can be unloaded from the decay station 30.

The above-described installation 6 preferably includes a controller 160 configured to perform the above-described method.

In particular, the installation 6 for the production of activated irradiation targets and, for example, the integrated monitoring and control unit (ICU) 42 further includes a controller 160 designed to control the following stages of the workflow carried out by the installation 6:

- movement through the drive system 25 of non-activated irradiation targets 16 in the amount of q ₁ from the system 21 for supplying irradiation targets to the pipe system 12 of control and measuring equipment;

- irradiation with a neutron flux of non-activated irradiation targets 16 in an amount q ₁ in the pipe system 12 of control and measuring equipment for a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets 16 in an amount q ₁ , and the predetermined irradiation time d ₁ should be strictly less than the minimum activation time for complete conversion of the precursor material contained in the irradiation targets 16 into the required radionuclide;

- movement by means of a drive system 25 of partially activated irradiation targets 16 in an amount q ₁ from the pipe system 12 of control and measuring equipment to the decay station 30;

- movement through the drive system 25 of non-activated irradiation targets 16 in the amount of q ₂ from the system 21 for supplying irradiation targets to the pipe system 12 of control and measuring equipment;

- movement through the drive system 25 of partially activated irradiation targets 16 in the amount of q ₁ back from the decay station 30 to the pipe system 12 of control and measuring equipment;

- irradiation with a neutron flux of partially activated irradiation targets 16 in an amount of q ₁ and non-activated irradiation targets 16 in an amount of q ₂ in a pipe system of control and measuring equipment for a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets 16 in an amount q ₁ and partially activated irradiation targets 16 in the amount of q ₂ ;

- unloading at least some of the irradiation targets 16 and, preferably, the fully activated irradiation targets 16 from the decay station 30 into the target storage container 34.

The above-described decay station 30 and installation 6 have clear advantages.

In fact, the decay station 30 has an input dispenser 68 allowing the movement of a predetermined number of irradiation targets 16 into the decay station 30 for the purpose of temporary storage of partially activated irradiation targets 16 before being returned to the nuclear reactor core 10 for further activation, or for the purpose of aging the irradiation targets 16 for the decay of short-lived radioisotopes to an acceptable level before unloading the targets into containers 34 for storage.

Since the decay station 30 housing the irradiation targets 16 is adapted to move a predetermined number of irradiation targets 16 back into the core 10, it is possible to produce batches of radioisotopes with a delivery interval shorter than the activation time of the radioisotopes in the reactor core within the same pipe system 12 control and measuring equipment. For example, it is possible to produce batches of radioisotopes with a delivery interval corresponding to half the activation time of the radioisotopes in the core.

In particular, the decay station 30 can receive, in the specified linear order from the input to the output of the decay station, a batch of partially activated irradiation targets 16 that were in the core for only part of the required activation time, and a batch of fully activated irradiation targets that were in the core 10 for the required activation time . Input distributor 68 and associated input counter 96 allow selective movement of only partially activated radioisotopes back into core 10 while retaining fully activated irradiation targets 16 in decay station 30.

Decay station 30 is also adapted to discharge fully activated irradiation targets 16 into conventional storage containers 34 without the need for a hot chamber or handlers, the unloading circuit of the plant providing intermediate storage of fully activated irradiation targets 16 for a period of time sufficient to reduce the activity of short-lived radioisotopes to acceptable level. Once the level of radioactivity decreases below a predetermined threshold, the activated irradiation targets 16 can be automatically transferred from the decay station 30 to the unloading system 27 of the installation 6. In addition, the specified decay station 30 is easily integrated directly into existing radionuclide production systems and ensures the safe decay of short-lived highly radioactive isotopes that are by-products.

Thus, the proposed compact decay station 30 is a cost-effective technical solution for releasing activated irradiation targets 16 from a nuclear reactor core 10 while minimizing the risk to the environment.

The method according to the invention makes it possible to reduce the delivery interval of radioisotopes contained in fully activated irradiation targets 16. In fact, at any given time, the test equipment finger 14 contains at least two batches of irradiation targets 16 at different stages of activation. Decay station 30 serves as interim storage for a batch of partially activated targets while a new batch of non-activated irradiation targets 16 is introduced into instrumentation finger 14. Once a new batch is introduced into the test equipment finger 14, the batch of partially activated irradiation targets 16 can be transferred from the decay station back to the test equipment finger 14 for additional neutron flux irradiation. The design features of the decay station 30 include the presence of an input distributor 68 and a corresponding input counter 96, which allows only one of the two batches of irradiation targets to be moved back to the control equipment finger 14, while the other batch can be held before being discharged into the appropriate discharge container in the decay station 30 for a decay time d ₃ sufficient for the decay of short-lived highly emitting isotopes.

According to a second embodiment of the invention, a method for producing activated irradiation targets 16 using the above-described apparatus 6 includes the following steps:

- move non-activated irradiation targets 16 into the pipe system 12 of control and measuring equipment from the irradiation target supply system 21;

- irradiate the neutron flux of the irradiation target 16 in the pipe system 12 of the control and measuring equipment for a predetermined irradiation time corresponding to the minimum activation time required for the complete conversion of the precursor material contained in the irradiation targets 16 into the required radionuclide in order to obtain fully activated targets 16 irradiation;

- move fully activated irradiation targets 16 from the pipe system 12 of control and measuring equipment to the decay station 30;

- hold fully activated irradiation targets 16 in the decay station 30 during the decay time;

- irradiation targets 16 are unloaded from the decay station 30 into a container 34 for storing targets.

The decay time corresponds to the time required to reduce the radiation, in particular the dose rate emitted by the number q ₁ of fully activated irradiation targets 16, below a predetermined threshold. According to one example, the decay time is predetermined depending on the nature of the material contained in the irradiation targets 16. According to an alternative embodiment, the decay duration depends on the measurement of radiation, and in particular dose rate, by the output radiation sensor 102 and/or additional intermediate radiation sensors 104.

If necessary, the method includes the step of shifting the divertor 32 into a second configuration before moving the irradiation targets 16 from the irradiation target supply system 21 into the pipe system 12 of the control and measuring equipment and the step of shifting the divertor 32 from the second configuration to the first configuration before moving the irradiation targets 16 from the pipe system 12 control and measuring equipment in the decay station 30.

Preferably, input counter 96 counts the number of irradiation targets 16 transferred from instrumentation tubing 12 to decay station 30.

The method according to this alternative embodiment of the invention allows the production of radionuclides with a delivery interval equal to the minimum activation time of the desired radionuclide, increased by the decay time.

The method for producing radionuclides according to this alternative embodiment of the invention is preferred. In fact, when implementing this method, safety is increased and radiation contamination of the environment and personnel is reduced, since irradiation targets are sent to container 34 only after the decay of highly radioactive isotopes that are by-products. In addition, this method can be carried out automatically and does not require the use of additional installations, for example hot chambers. The method according to the invention can be easily implemented using a compact installation.

In the above description, the diverter 32 was considered as part of an installation containing a decay station 30. In this case, it is connected to the system 27 for unloading irradiation targets through the decay station 30. However, the diverter 32 may be part of an installation that does not contain a decay station 30, in which case the diverter is connected directly to the irradiation target unloading system 27 without an intermediate decay station 30.

In addition, the diverter 32 has been described as being connected to the nuclear reactor core instrumentation piping system 12. However, the divertor 32 may be coupled to other structural components within the nuclear reactor core, in addition to the instrumentation piping system 12, depending on needs, which is advantageous.

This application also relates to a plant for producing activated irradiation targets 16 in a nuclear reactor instrumentation pipe system 12, comprising:

- system 21 for supplying irradiation targets, described above, designed to ensure the presence of non-activated irradiation targets 16;

- a pipe system 12 of control and measuring equipment, described above, configured to receive irradiation targets 16 from the irradiation target supply system 21, based on their activation under the influence of a neutron flux in a nuclear reactor;

- a system 27 for unloading irradiation targets, containing a target output port configured to connect to a container 34 for storing targets,

- diverter 32, described above, adapted to selectively determine the trajectory of movement of irradiation targets 16 between the irradiation target supply system 21 and the pipe system 12 of control and measuring equipment, or between the pipe system 12 of control and measuring equipment and the system 27 for unloading irradiation targets, the first connector 150 connects to the irradiation target unloading system 27, the second connector 152 connects to the irradiation target supply system 21, and the third connector 154 connects to the instrumentation equipment pipe system 12; and

- a drive system 25 for targets, configured to transport at least a certain number of irradiation targets 16 through installation 6.

Claims (95)

1. A decay station configured to receive radiation targets from the structure of a nuclear reactor core in a predetermined linear order and including a housing containing a radiation shield adapted to protect the environment surrounding the decay station from radiation emitted by the radiation targets, contained in the disintegration station, and the housing defines a disintegration pipeline designed to accommodate irradiation targets in a predetermined linear order, wherein the disintegration pipeline contains: - an input intended for connection to the structure of the nuclear reactor core for receiving radiation targets from it; - an output intended for connection to the irradiation target unloading system for unloading irradiation targets from the decay station, wherein The disintegration station additionally contains: - an inlet distributor located at the inlet of the decay pipeline and adapted for the simultaneous release from the decay station of only a predetermined number of irradiation targets towards the structure of the nuclear reactor core, while the inlet distributor is adapted for the release of irradiation targets closest to the inlet of the decay pipeline, holding at this is the remaining irradiation target in the decay pipeline; - an input counter configured to count the number of irradiation targets entering or exiting the decay pipeline through the input of the decay pipeline, wherein the input counter is located at the entrance of the decay pipeline, and - output radiation sensor, adapted for measuring radiation emitted by an irradiation target located at the output of the decay pipeline. 2. The disintegration station according to claim 1, further comprising a source of compressed gas connected to the outlet of the disintegration pipeline for supplying the compressed gas to the disintegration pipeline through the outlet of the pipeline. 3. Decay station according to claim 2, in which the input distributor contains, in the direction from the entrance of the decay pipeline to the output of the decay pipeline, sequentially located: - a locking element movable between a locking position in which it prevents the movement of irradiation targets from the decay pipeline through the inlet of the decay pipeline, and a unlocking position in which it allows the release of a predetermined number of irradiation targets from the decay pipeline through the inlet of the decay pipeline; And - a latch movable between a retracted position in which it allows movement of the irradiation targets, and an extended position in which it engages at least partially into the disintegration conduit, the latch being capable of abutting the irradiation target in the extended position, preventing movement of the irradiation target towards inlet of the decay pipeline, the input distributor additionally contains: - a first actuator adapted to move the locking element between a locking position and an unlocking position; And - a second actuator adapted to move the latch between an extended position and a retracted position. 4. The disintegration station according to claim 3, in which the locking element includes a locking pin configured to be radially extended across the disintegration pipeline into a locking position of the locking element, and the latch includes a locking pin configured to be partially radially extended into the disintegration pipeline into an extended locking position , and a spring element connected to the locking pin. 5. Decay station according to claim 3 or 4, additionally containing a controller adapted, using an input distributor, to regulate the sequence of release of a predetermined number of irradiation targets when performing the following steps: - moving the locking element by means of the first actuator from the unlocking position to the locking position; - providing a supply of compressed gas to obtain a flow of compressed gas through the disintegration pipeline from its outlet, and the flow of compressed gas is capable of pushing the irradiation targets contained in the disintegration pipeline towards the entrance of the pipeline until they stop at the shut-off element occupying a blocking position; - moving the latch by means of a second actuator from a retracted position to an extended position in which the latch is capable of abutting the irradiation target contained in the decay pipeline; - moving the locking element by means of the first actuator from the locking position to the unlocking position, so that a predetermined number of irradiation targets, corresponding to the number of irradiation targets located downstream of the lock in the direction of the flow of compressed gas, is released from the disintegration pipeline through the inlet of the disintegration pipeline, while while the remaining irradiation targets are held in the decay pipeline by a clamp occupying an extended position. 6. Decay station according to claim 5, in which the controller is additionally adapted to repeat successive stages of release of irradiation targets depending on the total number of irradiation targets to be released from the decay station through the inlet of the decay pipeline. 7. Decay station according to any one of paragraphs. 1 - 6, in which a predetermined number of irradiation targets is equal to one irradiation target, wherein the distributor is adapted to release the irradiation targets one by one from the decay station towards the structure of the nuclear reactor core. 8. Decay station according to any one of paragraphs. 1 – 7, additionally containing at least one intermediate irradiation target counter, configured to count the number of irradiation targets contained in the decay pipeline, and located between the input counter and the output of the decay pipeline. 9. Decay station according to any one of paragraphs. 1 – 8, additionally containing at least one intermediate radiation sensor, configured to measure radiation emitted by irradiation targets contained in the decay pipeline, and located between the output radiation sensor and the input of the decay pipeline. 10. Decay station according to any one of paragraphs. 1 – 9, additionally containing an output distributor located in the area of the exit of the decay pipeline and adapted for the simultaneous release of only a predetermined number of irradiation targets from the decay station through the output of the decay pipeline, wherein the output distributor is adapted to release irradiation targets closest to the exit of the decay pipeline, holding while the remaining irradiation targets are in the decay pipeline. 11. Decay station according to any one of paragraphs. 1 – 10, in which the decay pipeline is a straight pipeline. 12. Decay station according to any one of paragraphs. 1 to 10, wherein the disintegration conduit is substantially U-shaped and comprises a first section, a second section, and a lower portion formed at a junction between the first and second disintegration conduit sections, the first and second disintegration conduit sections extending upward from lower part. 13. Decay station according to any one of paragraphs. 1 - 12, containing a controller adapted to regulate the release from the decay station of at least some radiation targets after a predetermined decay time and/or upon a decrease below a predetermined radiation threshold measured by the output radiation sensor. 14. Decay station according to any one of paragraphs. 1 – 13, in which the design of the nuclear reactor core is a pipe system of control and measuring equipment of a nuclear reactor. 15. A diverter of an installation for producing activated radiation targets in a nuclear reactor, the diverter having a first configuration in which it determines the trajectory of movement of the radiation targets between the nuclear reactor core structure and the radiation target unloading system for unloading the activated radiation targets, and a second configuration in which it determines the trajectory of movement of irradiation targets between the irradiation target supply system and the structure of the nuclear reactor core, and diverter contains: - the first connector intended for connection with the system for unloading irradiation targets; - a second connector designed for connection to the irradiation target supply system; - a third connector intended for connection with the structure of the nuclear reactor core; - at least one diverter pipeline that is capable of moving between: - the first position in which it connects to the third connector one of the connectors, namely the first connector or the second connector, defining the trajectory of movement of the targets from one of the connectors, namely from the first or second connector, to the third connector, and - a second position in which it does not connect one of the connectors, namely the first connector or the second connector, to the third connector; and said or each diverter pipeline is shaped in such a way that along its length the direction of movement of the irradiation targets intended for circulation in it changes twice, and - an actuator adapted to move said or each diverter pipeline between a first position and a second position; the diverter comprises a first diverter pipeline and a second divertor pipeline, wherein the first diverter pipeline in its first position connects the first connector to the third connector, defining the trajectory of movement of the irradiation targets from the first connector to the third connector, and the second divertor pipeline in its first position connects the second connector to the third connector, defining the trajectory of movement of the irradiation targets from the second connector to the third connector. 16. The diverter of claim 15, wherein said or each divertor conduit comprises a substantially straight end section at each end of the divertor conduit and an intermediate section located therebetween. 17. The divertor according to claim 15 or 16, in which the intermediate section of each divertor pipeline is straight. 18. Diverter according to any one of paragraphs. 15 – 17, in which the intermediate section of the specified or each diverter pipeline is curved. 19. Diverter according to any one of paragraphs. 15 - 18, in which the third connector is located at a distance from the first connector and the second connector in a horizontal direction. 20. Diverter according to any one of paragraphs. 15 - 19, wherein the first connector and the second connector are substantially vertically aligned and/or the third connector is located at an intermediate height between the heights of the first and second connectors. 21. Diverter according to any one of paragraphs. 15 - 20, wherein the actuator is adapted to move said or each diverter conduit between a first position and a second position through a translational or rotary motion. 22. Diverter according to any one of paragraphs. 15-21, configured such that the first diverter pipeline occupies a first position when the second diverter pipeline occupies a second position, and vice versa. 23. The diverter according to claim 22, further comprising a piston defining the first and second divertor pipelines inside, wherein the piston is movable between a first position, in which the first divertor pipeline occupies a first position, and the second divertor pipeline occupies a second position, and the second a position in which the first diverter pipeline occupies a second position and the second diverter pipeline occupies a first position. 24. The diverter according to claim 23, additionally having a housing, wherein the piston is placed in the divertor housing with the ability to slide in the direction of movement. 25. The diverter according to claim 24, in which the diverter housing additionally contains: - first and second chambers formed between the piston and the divertor body, with the first and second chambers located on both sides of the piston in the direction of movement of the piston; - an inlet port in fluid communication with the first chamber and designed to supply a fluid under pressure into the first chamber to move the piston from a first position to a second position; and - an outlet port in fluid communication with the second chamber and designed to release air from the second chamber during movement of the piston in the direction of movement. 26. The diverter according to claim 25, in which the piston is configured to return to the first position if there is no fluid under pressure in the first chamber. 27. Diverter according to any one of paragraphs. 24 – 26, in which the diverter housing contains first and second walls located at a distance from each other in the longitudinal direction of the divertor pipeline, with the first and second connectors located on the first wall, and the third connector on the second wall. 28. Diverter according to any one of paragraphs. 15 – 27, in which the first and second diverter pipelines are located symmetrically relative to the middle plane between the two pipelines. 29. Diverter according to any one of paragraphs. 15 - 23, containing one single divertor pipeline, wherein the divertor pipeline in the first position connects the first connector to the third connector, and in the second position connects the second connector to the third connector, while the divertor pipeline is rotatable between the first position and the second position. 30. The diverter according to claim 29, further comprising a support on which the first and second connectors are located, and a rotary pipeline holder, which is installed on the support with the possibility of rotation around the axis of rotation, and one end of the divertor pipeline is installed on the rotary pipeline holder so that when By rotating the pipeline holder, the diverter pipeline moves between the first position and the second position. 31. Installation for the production of activated irradiation targets in the pipe system of control and measuring equipment of a nuclear reactor, containing: - a system for supplying irradiation targets, designed to ensure the availability of non-activated irradiation targets; - a pipe system of control and measuring equipment, configured to receive irradiation targets from the irradiation target supply system, based on their activation under the influence of a neutron flux in a nuclear reactor; - a disintegration station according to any one of claims 1 to 14, wherein the inlet of the disintegration pipeline is connected to the pipe system of the control and measuring equipment, and the input distributor of the disintegration station is adapted for the simultaneous release of a predetermined number of irradiation targets from the disintegration station towards the pipe system of the control and measuring equipment equipment, wherein the inlet distributor is adapted to release irradiation targets closest to the instrumentation tubing system, while retaining the remaining irradiation targets in the decay station; - a system for unloading irradiation targets, containing a target output port, configured to be connected to a container for storing targets, wherein the unloading system contains an inlet end connected to the outlet of the disintegration station pipeline; - a diverter moved between the first position in which it determines the trajectory of movement of irradiation targets between the delivery system of irradiation targets and the pipe system of control and measuring equipment, and the second position in which it determines the trajectory of movement of irradiation targets between the pipe system of control and measuring equipment and the station decay; And - a drive system for irradiation targets, configured to transport at least some targets through the installation, wherein the drive system for irradiation targets contains a unit for supplying compressed gas to the disintegration station. 32. The installation according to claim 31, additionally containing a controller adapted to control the following stages carried out by the installation: - movement through the drive system of non-activated radiation targets in the amount of q ₁ from the system for supplying radiation targets to the pipe system of control and measuring equipment; - irradiation with a neutron flux of non-activated irradiation targets in an amount q ₁ in a pipe system of control and measuring equipment during a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets in an amount q ₁ , and the predetermined irradiation time d ₁ is strictly less than the minimum activation time to completely convert the precursor material contained in the irradiation targets into the required radionuclide; - movement through the drive system of partially activated irradiation targets in the amount of q ₁ from the pipe system of control and measuring equipment to the decay station; - movement through the drive system of non-activated radiation targets in an amount of q ₂ from the system for supplying radiation targets to the pipe system of control and measuring equipment; - movement through the drive system of partially activated irradiation targets in the amount of q ₁ back from the decay station to the pipe system of control and measuring equipment; - irradiation with a neutron flux of partially activated irradiation targets in the amount of q ₁ and non-activated irradiation targets in the amount of q ₂ in the pipe system of control and measuring equipment during a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets in the amount of q ₁ and partially activated irradiation targets in the amount of q ₂ ; And - unloading at least some irradiation targets from the decay station into a target storage container. 33. Installation according to paragraph 31 or 32, containing a diverter according to any of paragraphs 15 - 30. 34. A method for producing activated irradiation targets using the installation according to claims. 31 – 33, which includes stages in which: - move non-activated irradiation targets in an amount of q ₁ into the pipe system of control and measuring equipment from the irradiation target supply system; - irradiate non-activated irradiation targets in an amount q ₁ with a neutron flux in a pipe system of control and measuring equipment for a predetermined irradiation time d ₁ in order to obtain partially activated irradiation targets in an amount q ₁ , and the predetermined irradiation time d ₁ is equal to or less than the minimum time activation for complete conversion of precursor material contained in irradiation targets into the required radionuclide; - move irradiation targets in an amount q ₁ from the pipe system of control and measuring equipment to the decay station; - unloading at least some irradiation targets from the decay station into a container for storing targets. 35. The method of claim 34, further comprising holding at least some of the irradiation targets in the decay station for a predetermined decay time before unloading the irradiation targets from the decay station into a target storage container. 36. The method of claim 34 or 35, wherein the predetermined time d ₁ is less than the minimum activation time for complete conversion of the precursor material contained in the irradiation targets into the desired radionuclide, resulting in the number q ₁ of irradiation targets obtained at the end of the irradiation step in a pipe system of control and measuring equipment, represents the number q ₁ of partially activated irradiation targets; wherein the method, between the step of moving partially activated irradiation targets in an amount of q ₁ from the pipe system of control and measuring equipment to the decay station and the step of unloading at least some irradiation targets from the decay station into a target storage container, further includes the following steps, in which: - move non-activated radiation targets in an amount of q ₂ into the pipe system of control and measuring equipment; - move partially activated irradiation targets in an amount q ₁ from the decay station back to the pipe system of control and measuring equipment; - irradiate partially activated irradiation targets in an amount of q ₁ and non-activated irradiation targets in an amount of q ₂ with a neutron flux in a pipe system of control and measuring equipment for a predetermined irradiation time d ₂ in order to obtain partially activated or fully activated irradiation targets in an amount of q ₁ and partially activated irradiation targets in the amount of q ₂ . 37. Installation for the production of activated irradiation targets in a pipe system of control and measuring equipment of a nuclear reactor, containing: - a system for supplying irradiation targets, adapted to ensure the presence of non-activated irradiation targets; - a pipe system of control and measuring equipment, configured to receive irradiation targets from the irradiation target supply system, based on their activation under the influence of a neutron flux in a nuclear reactor; - a system for unloading irradiation targets, containing a target output port configured to connect to a container for storing targets, - diverter according to any one of paragraphs. 15 – 30, adapted to selectively determine the trajectory of movement of targets between the irradiation target supply system and the pipe system of control and measuring equipment, or between the pipe system of control and measuring equipment and the irradiation target unloading system, wherein the first connector is connected to the irradiation target unloading system, the second connector is connected with the irradiation target supply system, and the third connector is connected to the pipe system of the instrumentation equipment; And - a drive system for irradiation targets, configured to transport at least some irradiation targets through the installation. 38. The installation according to claim 37, additionally containing a decay station located on the path of movement of irradiation targets between the pipe system of control and measuring equipment and the irradiation target unloading system and adapted for holding activated irradiation targets before they are unloaded from the installation by means of the irradiation target unloading system, wherein the first connector is connected to the system for unloading irradiation targets through a decay station.