CN213123808U - Reactor and reactor-based isotope production system - Google Patents
Reactor and reactor-based isotope production system Download PDFInfo
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- CN213123808U CN213123808U CN202021872440.3U CN202021872440U CN213123808U CN 213123808 U CN213123808 U CN 213123808U CN 202021872440 U CN202021872440 U CN 202021872440U CN 213123808 U CN213123808 U CN 213123808U
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Abstract
Embodiments of the present invention provide a reactor and a reactor-based isotope production system, method, including: a core disposed in a core vessel, the core comprising: a fuel assembly, a removable production assembly and a reflective assembly; a first pipe body disposed axially above the production assembly to provide a passage for the production assembly to move in an axial direction of the core vessel and to restrict movement of the production assembly in a radial direction of the core vessel when the production assembly moves in the axial direction of the core vessel. According to the utility model discloses reactor and isotope production system, method based on reactor can accomplish the installation of production subassembly and dismantle under the condition of not shutting down the heap to can accomplish the production of isotope when carrying out activities such as heating or power supply, improve reactor resource utilization.
Description
Technical Field
The utility model relates to a nuclear technology field especially relates to a reactor and isotope production system based on reactor.
Background
With the continuous maturity of nuclear technology, the application of the reactor is more and more extensive, on one hand, the heat energy generated in the nuclear reaction process can be used for various applications such as heating, power supply, seawater purification and the like, and on the other hand, the neutrons generated in the nuclear reaction process can also be applied to the production of isotopes.
Reactors that can be commercially used in the prior art, such as reactors for heating and power supply, can only utilize the heat energy in the nuclear reaction process, while reactors for isotope production are mostly research reactors, which extract neutrons for research while isotope production is performed, but cannot utilize the heat energy in the nuclear reaction process.
Since isotope production requires frequent replacement of production components, reactors used for heating and heat supply in the prior art cannot replace production components without shutdown, and thus isotope production cannot be performed using these reactors.
SUMMERY OF THE UTILITY MODEL
In view of the above, the present invention has been made in order to provide a reactor and a reactor-based isotope production system that overcome or at least partially solve the above problems.
According to an aspect of the embodiments of the present invention, there is provided a reactor, including: a core disposed in a core vessel, the core comprising: a fuel assembly for performing a nuclear reaction and releasing neutrons; a detachable production assembly for receiving irradiation by said neutrons to produce isotopes; a reflection assembly made of a neutron reflecting material for reflecting neutrons released by the fuel assembly to increase the amount of the neutrons striking the production assembly; a first pipe body disposed axially above the production assembly to provide a passage for the production assembly to move in an axial direction of the core vessel and to restrict movement of the production assembly in a radial direction of the core vessel when the production assembly moves in the axial direction of the core vessel.
Optionally, the core further comprises: the second pipe body is arranged at a position corresponding to the production assembly and used for providing an accommodating space for the production assembly; a flow guide provided in the core vessel for limiting a flow of coolant at the second pipe body after the production assembly is disassembled, the coolant for absorbing heat energy generated by the nuclear reaction.
Optionally, the flow guide member is disposed inside the second pipe body.
Optionally, the second tube is made of a neutron reflecting material.
Optionally, the core vessel is disposed in a containment pool that provides the coolant for the core, the core vessel further comprising: a coolant inlet opening in the bottom of the core vessel for providing a passage for the coolant from the containment pool into the core vessel.
Optionally, the reactor further comprises: and the partition plate is arranged at the top of the accommodating pool, and a cooling mechanism is arranged on the upper layer of the partition plate to inhibit the evaporation of the coolant in the accommodating pool.
Optionally, the reactor further comprises: a valve disposed above the coolant inlet for conducting a passage through which the coolant circulates between the core vessel and the receiving tank to discharge heat energy of the core after the nuclear reaction is stopped.
According to the utility model discloses an embodiment still provides an isotope production system based on reactor, includes: a reactor according to any one of the above; the lifting mechanism is used for completing the installation and the disassembly of the production assembly of the reactor through a first pipe body of the reactor; the transfer mechanism is used for transferring the disassembled production assembly to a first processing module; the first processing module is used for receiving the production assembly and carrying out decay and drying treatment on the production assembly; a second processing module for receiving the production assembly having completed the drying process and extracting isotopes in the production assembly.
Optionally, the isotope production system further comprises: a transfer container for receiving the production components disassembled by the lifting mechanism and storing the production components during transfer by the transfer mechanism; and/or a third processing module for processing radioactive waste generated by the isotope production system.
Optionally, the transfer vessel is movably disposed above a partition of the reactor.
According to the utility model discloses reactor and isotope production system based on reactor have set up reflection subassembly and detachable production subassembly in the reactor core of reactor, have set up first body simultaneously, when utilizing the heat energy of nuclear reaction release, can utilize the neutron of nuclear reaction release to carry out the isotope production to can accomplish the installation and the dismantlement of production subassembly under the condition of not shutting down the heap, make the reactor can realize the production of isotope when realizing uses such as power supply, heating.
Drawings
FIG. 1 is a schematic diagram of a reactor according to an embodiment of the present invention;
FIG. 2 is a schematic view of a reactor core according to an embodiment of the present invention;
fig. 3 is a schematic view of an isotope production system in accordance with an embodiment of the present disclosure;
fig. 4 is a schematic view of an isotope production process in accordance with an embodiment of the present disclosure.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention clearer, the drawings of the embodiments of the present invention will be combined below to clearly and completely describe the technical solutions of the present invention. It is to be understood that the described embodiment is one embodiment of the invention, and not all embodiments. All other embodiments, which can be obtained by a person skilled in the art without any inventive work based on the described embodiments of the present invention, belong to the protection scope of the present invention.
Unless defined otherwise, technical or scientific terms used herein shall have the ordinary meaning as understood by those of ordinary skill in the art to which the invention belongs.
An embodiment according to the present invention firstly provides a reactor 100, see fig. 1 and 2, comprising: a core 10, said core 10 comprising fuel assemblies 11, removable production assemblies 12 and reflection assemblies 13, wherein the fuel assemblies 11 are used for performing nuclear reactions and releasing neutrons; a detachable production assembly 12 for receiving irradiation by said neutrons to produce isotopes; the reflecting assembly 13 is made of a neutron reflecting material for reflecting neutrons released from the fuel assembly to increase the amount of the neutrons irradiated to the production assembly.
The reactor 100 further includes a core vessel 20, wherein the core 10 is disposed in the core vessel 20, it is understood that the core vessel 20 may have different forms according to the type of the reactor 100, for example, the core vessel 20 may be a pressure shell, a reactor body cylinder in a pool reactor, etc., and those skilled in the art can select the core vessel 20 according to actual needs.
The reactor 100 further includes a first pipe 30, the first pipe 30 being disposed axially above the production assemblies 12 for providing a passage for the production assemblies 12 to move in the axial direction of the core vessel 20 and limiting movement of the production assemblies 12 in the radial direction of the core vessel 20 when the production assemblies 12 move in the axial direction of the core vessel 20.
Specifically, fig. 2 shows an example of the arrangement of the components of the core 10, the fuel components 11 being located inside the core 10, the reflection components 13 surrounding the fuel components 11, and the production components 12 being located between the fuel components and the reflection components 13. The specific type, number and arrangement of the fuel assemblies can be designed by those skilled in the art according to actual needs. The reflector assembly 13 is made of a neutron reflecting material, such as graphite, beryllium, etc., and graphite is preferably used as the neutron reflecting material of the reflector assembly 13 because graphite has a smaller reflecting section, which is more advantageous for increasing the concentration of neutrons irradiated to the fuel assembly 11. The reflector assembly 13 may reflect neutrons released during the nuclear reaction of the fuel assembly 11, thereby reducing escape to allow more neutrons to impinge on the production assembly 12 for isotope production. The specific number of production assemblies 12 and reflection assemblies 13 can also be designed by those skilled in the art according to the actual requirements and the results of the neutron physical calculations, which are not described in detail herein.
The production modules 12 may be targets for producing isotopes such as MO-99, CO-60, etc., and the positions of the fuel modules 11, the production modules 12, and the reflection modules 13 in fig. 2 may be appropriately changed according to the neutron physical calculation results, for example, a part of the production modules 12 is disposed at the center of the core 10, a part of the production modules 12 is disposed at the outer side of the reflection modules 13, and so on, according to the neutron irradiation concentration required for producing different types of isotopes. In order to flexibly perform the core layout, the fuel assemblies 11, the production assemblies 12, and the reflection assemblies 13 may be arranged to have the same outer shape and be arranged in the core grid of the same specification.
Axially above the production assembly 12 is provided a first tubular body 30 for providing the production assembly 12 with a passage for axial movement of the production assembly 12 along the core vessel 20, the first tubular body 30 may be configured to have a lumen that is adapted to the profile of the production assembly 12, for example when the production assembly 12 is cylindrical, the first tubular body 30 may be a tubular body configured with a cylindrical lumen, the first tubular body 30 on the one hand ensuring that the production assembly 12 can move axially along the core vessel 20 via its lumen and on the other hand ensuring that the production assembly 12 does not rock radially of the core vessel 20 during axial movement along the core vessel 20, thereby protecting the production assembly 12 and other components in the core vessel 20, such as the control components of the core 10, the guide mechanisms in the core vessel 20, and the like in some embodiments.
The production of isotopes will be completed after the production assemblies 12 are installed in the core vessel 20 and irradiated for a period of time, at which point the completed production assemblies 12 are disassembled and another batch of non-neutron irradiated production assemblies 12 is installed in the core vessel 20 to achieve continuous production of isotopes. According to the utility model discloses an embodiment has guaranteed through setting up first body 30 that can accomplish the installation and the dismantlement of production subassembly 12 in the operation process of reactor 100, consequently can carry out the production of isotope when supplying power, heating etc. activity to the utilization ratio of nuclear reactor resource has been improved.
In some embodiments, the core 10 further includes a second pipe 14 and a flow guide 15, the second pipe 14 is disposed at a corresponding position of the production assembly 12 for providing a receiving space for the production assembly; flow guides 15 are provided in the core vessel 20 for limiting the flow of coolant at the second tubular body 14 for absorbing heat energy generated by the nuclear reaction after the production assembly 12 is disassembled.
The second tube 14 may have a receiving space adapted to the contour of the production assembly 12 so that the production assembly 12 may be mounted in the receiving space of the second tube 14, and in such an embodiment the second tube 14 may be configured to have the same outer shape as the fuel assembly 11 and the reflector assembly 13. The production assembly 12 is disposed in the second pipe body 14 so that the second pipe body 14 can be fixed in the core vessel 20 and the production assembly 12 can be fixed only with the second pipe body 14, making the installation and removal of the production assembly 12 more convenient.
In some embodiments, the core 10 further includes flow guides 15 (not shown). As will be understood by those skilled in the art, the reactor 100 needs to supply coolant to the core 10 during operation, the coolant flows smoothly between the respective components of the core 10 at a certain flow rate, and the vacant space left after the production assembly 12 is disassembled affects the flow rate distribution of the coolant, thereby limiting the flow rate of the coolant in the core vessel 20, particularly the flow rate of the coolant in the second pipe body 14, after the production assembly 12 is disassembled by providing the flow guide. The flow guides 15 may be provided as components, such as valves, conduits, etc., that can be actively or passively opened or closed after the production assembly 12 is disassembled so that the flow in the second tubular body 14 is maintained at a level prior to the disassembly of the production assembly 12 to maintain a steady flow of coolant within the core vessel 20.
In some embodiments, the flow guide 15 may be disposed inside the second pipe 14, so as to be able to better limit the coolant flow at the second pipe 14.
In some embodiments, the second tube 14 may also be made of a neutron reflecting material, for example, the second tube 14 is configured as a tube made of graphite, and preferably, the second tube 14 is made of the same neutron reflecting material as the reflecting assembly 13, so that the neutron physical calculation can be more conveniently performed to control the neutron concentration irradiated on the production assembly 12.
In some embodiments, the core vessel 20 is disposed in a containment pool 40, that is, the reactor 100 is a pool reactor. The containment pool 40 provides coolant, which may be water, to the core 20. in such embodiments, the core vessel 20 further includes a coolant inlet 21 opening at the bottom of the core vessel 20 for providing a passage for coolant from the containment pool 40 into the core vessel 20.
In such an embodiment, the containment pool 40 may be configured to have a depth much greater than the diameter, for example, may be configured to have a depth of 6-10m, the coolant in the containment pool 40 completely covers the core vessel 20, and the core vessel 20 may be configured in a chimney-like structure, for example, in a segmented assembly of upper, middle, and lower cradle-like structures.
Because the depth of the accommodating pool 40 is far greater than the diameter, the temperature of the coolant outlet on the core vessel 20 can be increased by using the hydrostatic pressure of the coolant therein to meet the heat supply requirement, and the reactor core 10 can be ensured to have no reactor melting accident under the conditions of no human intervention and no cooling means and can be freely evaporated for 2-3 weeks, thereby improving the inherent safety of the reactor 100. Furthermore, the chimney structure of the reactor core vessel 20 can also be used as an inertia water tank to assist in the waste heat removal of the reactor core 10 in an accident.
In some embodiments, the reactor 100 further includes a partition plate 50 disposed on the top of the receiving tank 40, and a cooling mechanism 51 is disposed on the upper layer of the partition plate 50 to suppress evaporation of the coolant in the receiving tank 40.
The partition 50 may be made of a heat insulating material, the cooling mechanism 51 may be a mechanism for cooling, such as a condenser tube, etc., and the cooling mechanism 51 may be directly disposed as a cold water layer on the partition 50, thereby being more economical and practical. The partition 50 suppresses the evaporation of the coolant in the receiving tank 40 by insulating heat and providing a certain cooling function without affecting the heating temperature of the reactor.
In some embodiments, the reactor 100 further includes a valve 60 disposed above the coolant inlet 21 for guiding a passage of the coolant circulating between the core vessel 20 and the containment pool 40 to discharge the heat energy of the core 10 after the nuclear reaction is stopped.
It can be understood that, during normal operation of the reactor 100, the coolant in the core container 20, after absorbing the heat energy generated by the nuclear reaction of the core 10, will be led out of the containment pool 40 for heating, power supply, etc., and when the reactor 100 stops operating, the valve 60 on the core container will be opened in an active or passive manner, so that the coolant in the containment pool 41 enters the core container 20 from the coolant inlet 21 and absorbs the residual heat of the core 10, and will be discharged from the valve 60, thereby completing the circulation of the coolant to take away the heat of the core 10.
In some embodiments, a plurality of supports 41 are provided on the wall of the receiving tank 40, and one end of the support 41 is fixed to the wall of the receiving tank 40 and the other end is connected to the core vessel 20. Further, the plurality of support members 41 are respectively provided along the axial direction and the circumferential direction of the core vessel 20, so that the support of the core vessel 20 can be formed, the core vessel 20 is prevented from being severely shaken in the case of an earthquake or the like, and the inherent safety of the reactor 100 is further increased.
In some embodiments, a service platform 42 is further provided on the wall of the containment pool 40, and the service platform may be provided on the wall of the pool near the middle of the core vessel 20 for using an operating space provided by the service platform 42 for service in the event of a failure of a component of the reactor 100.
In some embodiments, the reactor 100 further includes a water outlet pipe 71 and a water inlet pipe 72, the water outlet pipe 71 is configured to fluidly connect the core vessel 20 with a functional module (not shown) disposed outside the containment pool 40, the functional module may be a heating network, a generator, or the like, the coolant enters the functional module through the water outlet pipe 71 after absorbing heat of the core 10, and the functional module is generally configured with a heat exchange structure to utilize the heat in the coolant for heating or power supply, or the like. The water inlet line 72 is configured to fluidly connect the functional module to the containment tank 40 such that the coolant, after heat exchange, will be returned to the containment tank 40 via the water inlet line 72 to enable coolant circulation during operation of the reactor 100.
In some embodiments, a control assembly 80 (not shown) of the core 10 is further disposed in the core vessel 20, the control assembly is made of a neutron absorbing material and is disposed to be movable in the axial direction of the core vessel 20, so that the rate of progress of the nuclear reaction can be controlled by adjusting the depth of insertion of the control assembly 80 into the nuclear reaction active region of the core 10, and the control assembly 80 can be moved by magnetic driving, motor driving, or the like.
In some embodiments, a guide mechanism 81 is also disposed within the core vessel for providing guiding and protection when the control assembly 80 moves in the axial direction of the core vessel 20, and the guide mechanism may be a structure such as a tubular channel, a stop, etc. disposed within the core vessel 20, as well as other components capable of providing guiding and protection. In some embodiments, the reactor 100 further comprises a control assembly driving mechanism 82, and the driving mechanism 82 is connected to the control assembly 80 through a pulley and a steel cable, so as to drive the control assembly 80 to move. In some embodiments, the top of the tank wall of the receiving tank 40 is further provided with a fixing frame 44, in particular, the fixing frame 44 may be disposed above the partition 50, and the control assembly driving mechanism 82 may be fixedly connected with the fixing frame 44.
There is also provided, in accordance with an embodiment of the present invention, a reactor-based isotope production system, see fig. 3, including: the reactor 100 as described in any of the above; a lifting mechanism 200 for completing the mounting and dismounting of the production assembly 12 of the reactor 100 via the first tubular body 30 of the reactor 100; a transfer mechanism 300 for transferring the disassembled production assembly 12 to a first processing module 400; the first processing module 400 is configured to receive the production component and perform a drying process on the production component; a second processing module 500 for receiving the production assembly 12 with the drying process completed and extracting isotopes in the production assembly 12.
The lifting mechanism 200 may be any lifting type tool capable of grasping the production assembly 12 through the first pipe body 30, the lifting mechanism 200 transports the production assembly 12 to the first process module 400 by the transfer mechanism 300 after detaching the production assembly 12 from the core vessel 20, the first process module 400 may include an automatic drying device, etc., and in the first process module 400, the production assembly 12 is first left to stand to decay and then dried to remove moisture from the production assembly 12, and a specific decay time may be selected by a person skilled in the art according to the kind of isotope being produced. The second processing module 500 may include a hot chamber for disassembling the production assembly 12 and a separation plant (not shown) dedicated to separating isotopes. Those skilled in the art can design the first processing module 400 and the second processing module 500 according to the requirements of actual production conditions, production environments, and the like, and details thereof are not repeated herein.
In some embodiments, the isotope production system further includes a transfer container 600 for receiving the production assembly 12 disassembled by the lifting mechanism 200 and storing the production assembly 12 during transfer by the transfer mechanism 300; and/or a third processing module 700 for processing radioactive waste generated by the isotope production system. In some embodiments, the transfer container 600 may be configured as a lead tank to prevent radiation leakage from the production modules 12 during transfer, and in some embodiments, the transfer container 600 may be removably disposed on the partition 50 of the reactor 100, i.e., the transfer container 600 may be placed or removably secured to the partition 50, as shown in FIG. 1, to allow the lifting mechanism 200 to more conveniently place the production modules 12 into the transfer container 600. It is understood that after the lifting mechanism 200 removes and lifts the production modules 12, the production modules 12 may be placed in the transfer container 600, and after all the production modules 12 have been removed and placed in the transfer container 600, the transfer container 600 may be moved by the transfer mechanism 300 and transferred to the first processing module 400.
In the isotope production using the isotope production system as described in any one of the above, the following method, see fig. 4, may be employed, including:
step S102: disassembling a production assembly 12 of a reactor 100 of the isotope production system from a core vessel 20 of the reactor 100 using a lifting mechanism 200 of the isotope production system and removing the core vessel 20 via a first tubular body 30 of the reactor;
step S104: transferring the production assembly 12 to a first process module 400 of the isotope production system for a decay and dry process using a transfer mechanism 300 of the isotope production system;
step S106: the isotopes in the production assembly 12 after the drying process are extracted at a second process module 500 of the isotope production system.
In some embodiments, step S102 further comprises: detaching the production assemblies 12 from the core vessel 20 using the lifting mechanism 300 of the isotope production system and placing the production assemblies 12 into a transfer vessel 600 of the isotope production system after removing the core vessel 20 through the first pipe body 30; step S104 further includes: removing the transfer container 600 from the holding tank 40 using the transfer mechanism 400; standing to drain coolant from the surface of the transfer container 600; transferring the transfer container 600 to the first process module 400; the production module 12 in the transfer container 600 is removed.
In some embodiments, step S104 further comprises: after the production modules 12 are detached from the core vessel 20 by the lifting mechanism 200, another production module 12 that has not been neutron-irradiated is attached to the core vessel 20 via the first pipe body 30 by the lifting mechanism 200, so that continuous production of isotopes can be achieved.
For the embodiments of the present invention, it should be further explained that, under the condition of no conflict, the features in the embodiments and embodiments of the present invention can be combined with each other to obtain a new embodiment.
The above embodiments of the present invention are only examples, but the scope of the present invention is not limited thereto, and the scope of the present invention should be determined by the scope of the claims.
Claims (10)
1. A reactor, comprising:
a core disposed in a core vessel, the core comprising:
a fuel assembly for performing a nuclear reaction and releasing neutrons;
a detachable production assembly for receiving irradiation by said neutrons to produce isotopes;
a reflection assembly made of a neutron reflecting material for reflecting neutrons released by the fuel assembly to increase the amount of the neutrons striking the production assembly;
a first pipe body disposed axially above the production assembly to provide a passage for the production assembly to move in an axial direction of the core vessel and to restrict movement of the production assembly in a radial direction of the core vessel when the production assembly moves in the axial direction of the core vessel.
2. The reactor of claim 1 wherein the core further comprises:
the second pipe body is arranged at a position corresponding to the production assembly and used for providing an accommodating space for the production assembly;
a flow guide provided in the core vessel for limiting a flow of coolant at the second pipe body after the production assembly is disassembled, the coolant for absorbing heat energy generated by the nuclear reaction.
3. The reactor of claim 2, wherein the flow guide is disposed inside the second tubular body.
4. The reactor of claim 2, wherein the second tube is made of a neutron reflecting material.
5. The reactor according to any one of claims 2 to 4, wherein:
the core vessel is disposed in a containment pool that provides the coolant for the core, the core vessel further comprising:
a coolant inlet opening in the bottom of the core vessel for providing a passage for the coolant from the containment pool into the core vessel.
6. The reactor of claim 5, further comprising:
and the partition plate is arranged at the top of the accommodating pool, and a cooling mechanism is arranged on the upper layer of the partition plate to inhibit the evaporation of the coolant in the accommodating pool.
7. The reactor of claim 5, further comprising:
a valve disposed above the coolant inlet for conducting a passage through which the coolant circulates between the core vessel and the receiving tank to discharge heat energy of the core after the nuclear reaction is stopped.
8. A reactor-based isotope production system, comprising:
the reactor according to any one of claims 1 to 7;
the lifting mechanism is used for completing the installation and the disassembly of the production assembly of the reactor through a first pipe body of the reactor;
the transfer mechanism is used for transferring the disassembled production assembly to a first processing module;
the first processing module is used for receiving the production assembly and carrying out decay and drying treatment on the production assembly;
a second processing module for receiving the production assembly having completed the drying process and extracting isotopes in the production assembly.
9. The isotope production system in accordance with claim 8, further comprising:
a transfer container for receiving the production components disassembled by the lifting mechanism and storing the production components during transfer by the transfer mechanism; and/or
A third processing module for processing radioactive waste generated by the isotope production system.
10. The isotope production system in accordance with claim 9, wherein the transfer vessel is movably disposed above a bulkhead of the reactor.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111554414A (en) * | 2020-05-18 | 2020-08-18 | 中国原子能科学研究院 | Reactor core |
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| CN111554414A (en) * | 2020-05-18 | 2020-08-18 | 中国原子能科学研究院 | Reactor core |
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