CN214752962U

CN214752962U - Reactor system with high inherent safety

Info

Publication number: CN214752962U
Application number: CN202120796217.3U
Authority: CN
Inventors: 鄢炳火; 陈焕栋
Original assignee: Sun Yat Sen University
Current assignee: Sun Yat Sen University
Priority date: 2021-04-16
Filing date: 2021-04-16
Publication date: 2021-11-16
Anticipated expiration: 2031-04-16

Abstract

The utility model relates to the technical field of reactors and discloses a reactor system with high inherent safety.A pressure vessel is provided with a water inlet positioned at the upper part and a gas outlet positioned at the top part, and the gas inlet and outlet ends of a steam turbine are respectively connected with the gas outlet and the gas inlet end of a condenser, and the gas outlet end of the condenser is connected with the water inlet; the intracavity is filled with the feedwater to the water supply, the reactor core is located the reaction chamber, the upper and lower both sides of reactor core are equipped with the axial reflection layer respectively, a plurality of heat pipe equipartitions are on metal substrate, the lower extreme and the axial reflection layer of heat pipe are connected, the upper end of heat pipe extends to the water supply intracavity, be equipped with a plurality of uranium zirconium hydride fuel rods between two adjacent heat pipes, the periphery of reactor core is equipped with first radial reflection stratum from inside to outside in proper order, first neutron absorbing layer and shielding layer, be equipped with the control rotary drum in the first radial reflection stratum. The utility model has the advantages of low thermal stress of the reactor core structural material, convenient use, high intrinsic safety and high thermal efficiency.

Description

Reactor system with high inherent safety

Technical Field

The utility model relates to a reactor technical field especially relates to a reactor system of intrinsic safety nature security.

Background

Nuclear power is the parent of the future irreplaceable energy, nuclear reactors are devices for starting, controlling and maintaining nuclear fission or nuclear fusion chain reaction, so that the energy of nuclear fission can be released outwards at a slow speed, the nuclear transformation rate can be accurately controlled, and the nuclear fission or the nuclear fusion chain reaction is provided for people to use. The safety of the existing reactor is low, and the thermal efficiency is low.

SUMMERY OF THE UTILITY MODEL

The to-be-solved technical problem of the utility model is: a reactor system having a low thermal stress of a core structural material, a high intrinsic safety and a high thermal efficiency, and being convenient to use, and having an intrinsic safety is provided.

In order to solve the technical problem, the utility model provides a reactor system with high inherent safety, which comprises a steam turbine, a condenser, a pressure vessel and a reactor core, wherein the pressure vessel is provided with a water inlet positioned at the upper part and a gas outlet positioned at the top part, the gas outlet is connected with the gas inlet end of the steam turbine through a pipeline, the gas outlet end of the steam turbine is connected with the gas inlet end of the condenser through a pipeline, and the gas outlet end of the condenser is connected with the water inlet through a pipeline;

the pressure vessel includes for water cavity and reaction chamber, it has feedwater to fill in the for water cavity, water inlet and gas outlet all are located for water cavity, the reactor core is located the reaction chamber, the upper and lower both sides of reactor core be equipped with respectively with the axial reflection layer that the chamber wall of reaction chamber is connected, the reactor core includes uranium zirconium hydride fuel rod, heat pipe and metal matrix, the heat pipe is equipped with a plurality ofly and the interval inlays to be established on the metal matrix, the lower extreme of heat pipe is in with the setting the axial reflection layer of the downside of reactor core is connected, the upper end of heat pipe extends to in the for water cavity, two adjacent be equipped with a plurality ofly between the heat pipe the uranium zirconium hydride fuel rod, the periphery of reactor core is equipped with first neutron absorbing layer and shielding layer from inside to outside in proper order, be equipped with the control rotary drum in the first radial reflection layer, the control rotary drum is provided with a plurality of spacing rings and arranged outside the reactor core, and the control rotary drum is driven by the driving unit to rotate.

As the preferred scheme of the utility model, the working solution in the heat pipe is mercury, diphenyl ether or naphthalene.

As the preferred scheme of the utility model, the uranium zirconium hydride fuel rod is by the zirconium hydride crystal as moderator, and concentrated uranium is as fuel composition.

As the preferred scheme of the utility model, the heat pipe is the medium temperature heat pipe.

As the utility model discloses preferred scheme, the control rotary drum includes radial reflection stratum of second and second neutron absorbing layer, second neutron absorbing layer is circular-arc setting and is in the edge of the radial reflection stratum of second.

As the preferred scheme of the utility model, the second radial reflection stratum is solid formula cylinder structure.

As the utility model discloses preferred scheme, the gas outlet with be equipped with first valve on the pipeline between the inlet end of steam turbine.

As the preferred scheme of the utility model, the end of giving vent to anger of condenser with be equipped with the feed pump on the pipeline of water inlet.

As the preferred scheme of the utility model, the cross section of metal matrix is the polygon.

The embodiment of the utility model provides a reactor system that intrinsic safety is high compares with prior art, and its beneficial effect lies in:

therefore, the uranium zirconium hydride fuel rod is subjected to nuclear fission to generate heat, the heat is transferred to the heat pipe through the metal substrate, the feed water in the feed water cavity is heated into steam under the action of the heat pipe, the steam is conveyed to the steam turbine to drive the steam turbine to do work for power generation, the reactor fission energy is converted into electric energy, the exhaust steam generated after the steam turbine does work is conveyed to the steam turbine through a pipeline, the exhaust steam is condensed into supercooled water in the condenser and conveyed into the feed water cavity through the water inlet, so that Rankine cycle is formed, the reactor core structure material is low in thermal stress, high in inherent safety and convenient to use, can be applied to various types of miniature nuclear power systems, has high inherent safety and high thermal efficiency, and is subjected to heat transfer through the heat pipe, and is high in inherent safety; wherein, first radial reflecting layer and axial reflecting layer can have the reflex action to nuclear fission's neutron, prevent neutron leakage, make more neutron by slowing down return the reactor core, make uranium zirconium hydride fuel rod fission rate grow, impel reactor thermal power rising, and first neutron absorbing layer has the absorption to the neutron of slowing down, make uranium zirconium hydride fuel rod fission rate diminish, reduce reactor thermal power, can control reactor reactivity through the cooperation of first radial reflecting layer, axial reflecting layer and neutron absorbing layer and control rotary drum, thereby reach the control of in-pile thermal power.

Drawings

FIG. 1 is a schematic diagram of a reactor system with high intrinsic safety provided by an embodiment of the present invention;

FIG. 2 is a schematic diagram of the structure of a reactor core;

in the figure, 1, a steam turbine; 2. a condenser; 3. a pressure vessel; 31. a water inlet; 32. an air outlet; 33. a water supply cavity; 34. a reaction chamber; 4. a reactor core; 41. a shielding layer; 42. uranium zirconium hydride fuel rods; 43. an axial reflective layer; 44. a heat pipe; 45. a metal substrate; 46. a first radially reflective layer; 461. controlling the rotary drum; 4611. a second radially reflective layer; 4612. a second neutron absorbing layer; 47. a first neutron absorbing layer; 5. a first valve; 6. a feed pump; 7. a second valve.

Detailed Description

The following detailed description of the embodiments of the present invention is provided with reference to the accompanying drawings and examples. The following examples are intended to illustrate the invention, but are not intended to limit the scope of the invention.

In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", and the like, which indicate the orientation or positional relationship, are used in the present invention as being based on the orientation or positional relationship shown in the drawings, and are used only for convenience of description and simplification of the description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.

As shown in fig. 1 and 2, the present invention provides a preferred embodiment of a reactor system with high intrinsic safety, which includes a steam turbine 1, a condenser 2, a pressure vessel 3 and a reactor core 4, wherein the pressure vessel 3 is provided with a water inlet 31 at the upper part and a gas outlet 32 at the top part, the gas outlet 32 is connected with the air inlet of the steam turbine 1 through a pipeline, the air outlet of the steam turbine 1 is connected with the air inlet of the condenser 2 through a pipeline, and the air outlet of the condenser 2 is connected with the water inlet 31 through a pipeline; pressure vessel 3 includes for water cavity 33 and reaction chamber 34, for water cavity 33 intussuseption is filled with feedwater, water inlet 31 and gas outlet 32 all are located for in the water cavity 33, reactor core 4 is located in the reaction chamber 34, the upper and lower both sides of reactor core 4 be equipped with respectively with the axial reflection stratum 43 that the chamber wall of reaction chamber 34 is connected, reactor core 4 includes uranium zirconium hydride fuel rod 42, heat pipe 44 and metallic matrix 45, heat pipe 44 is equipped with a plurality ofly and the interval inlays uniformly and establishes on metallic matrix 45, the lower extreme of heat pipe 44 is in with the setting the downside of reactor core 4 axial reflection stratum 43 is connected, the upper end of heat pipe 44 extends to in the water cavity 33, two adjacent be equipped with a plurality ofly between the heat pipe 44 uranium zirconium hydride fuel rod 42, the periphery of reactor core 4 is equipped with first radial reflection stratum 46, second radial reflection stratum 46 are equipped with from inside to outside in proper order to outside, The reactor core is provided with a first neutron absorption layer 48 and a shielding layer 49, a plurality of control drums 461 are arranged in the first radial reflection layer 46, the control drums 461 are annularly arranged outside the reactor core 4, the control drums 461 are driven to rotate by a driving unit, and specifically, the driving unit is arranged outside the pressure vessel 3 (not marked in the figure).

Therefore, the uranium zirconium hydride fuel rod 42 is subjected to nuclear fission to generate heat, the heat is transferred to the heat pipe 44 through the metal substrate 45, the feed water in the feed water cavity 33 is heated into steam under the action of the heat pipe 44, the steam is conveyed to the steam turbine 1 to drive the steam turbine 1 to do work and generate electricity, the reactor fission energy is converted into electric energy, the exhaust steam generated after the steam turbine 1 does work is conveyed to the steam turbine 1 through a pipeline, the exhaust steam is condensed into supercooled water in the condenser 2 and conveyed into the feed water cavity 33 through the water inlet 31, so that a Rankine cycle is formed, the reactor core structure material has low thermal stress and high inherent safety, is convenient to use, can be applied to various types of miniature nuclear power systems, has high inherent safety and high thermal efficiency, and is subjected to heat transfer through the heat pipe 44 and has high inherent safety; the first radial reflecting layer 46 and the axial reflecting layer 43 can reflect neutrons of nuclear fission to prevent neutron leakage, so that more moderated neutrons return to a reactor core, the fission rate of the uranium zirconium hydride fuel rod 42 is increased, the thermal power of the reactor is increased, the first neutron absorbing layer 48 has an absorbing effect on the moderated neutrons, the fission rate of the uranium zirconium hydride fuel rod 42 is decreased, the thermal power of the reactor is reduced, and the reactivity of the reactor can be controlled through the cooperation of the first radial reflecting layer 46, the axial reflecting layer 43 and the neutron absorbing layer with the control rotary drum 461, so that the control of the in-reactor thermal power is achieved.

Illustratively, the heat pipe 44 is a medium-temperature heat pipe 44, the working fluid in the heat pipe 44 is mercury, diphenyl ether or naphthalene, and the working temperature is 500-.

Illustratively, the uranium zirconium hydride fuel rods 42 are composed of zirconium hydride crystals as moderator and enriched uranium as fuel, and specifically, the uranium zirconium hydride fuel elements are composed of uranium zirconium hydride fuel pellets, compression springs, gaps and cladding, so that the enriched uranium undergoes a continuous fission reaction under the action of moderated neutrons to generate fission energy to provide heat for the reactor.

Illustratively, the control drum 461 comprises a second radial reflection layer 4611 and a second neutron absorption layer 4612, the second neutron absorption layer 4612 is disposed on the edge of the second radial reflection layer 4611 in a circular arc shape, the second radial reflection layer 4611 is a solid cylindrical structure, and the cross section of the metal substrate 45 is a polygon, preferably a hexagonal hole.

Illustratively, in order to facilitate the opening and closing of the pipeline, a first valve 5 is arranged on the pipeline between the air outlet 32 and the air inlet end of the steam turbine 1.

Illustratively, a water supply pump 6 is arranged on a pipeline between the air outlet end of the condenser 2 and the water inlet 31, and particularly, a second valve 7 is arranged between the water supply pump 6 and the water inlet 31, so that the supercooled water can be smoothly conveyed into the water supply cavity 33.

In the description of the present invention, it is to be understood that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are used in a generic sense, e.g., fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases to those skilled in the art.

The foregoing is only a preferred embodiment of the present invention, and it should be noted that, for those skilled in the art, a plurality of modifications and replacements can be made without departing from the technical principle of the present invention, and these modifications and replacements should also be regarded as the protection scope of the present invention.

Claims

1. A reactor system with high inherent safety is characterized by comprising a steam turbine, a condenser, a pressure vessel and a reactor core, wherein the pressure vessel is provided with a water inlet positioned at the upper part and a gas outlet positioned at the top part, the gas outlet is connected with the gas inlet end of the steam turbine through a pipeline, the gas outlet end of the steam turbine is connected with the gas inlet end of the condenser through a pipeline, and the gas outlet end of the condenser is connected with the water inlet through a pipeline;

the pressure vessel includes for water cavity and reaction chamber, it has the feedwater to fill in the for water cavity, water inlet and gas outlet all are located for water cavity, the reactor core is located the reaction chamber, the upper and lower both sides of reactor core be equipped with respectively with the axial reflection layer that the chamber wall of reaction chamber is connected, the reactor core includes uranium zirconium hydride fuel rod, heat pipe and metal matrix, the heat pipe is equipped with a plurality ofly and the interval inlays to be established on the metal matrix, the lower extreme of heat pipe is in with the setting the axial reflection layer of the downside of reactor core is connected, the upper end of heat pipe extends to in the for water cavity, two adjacent be equipped with a plurality ofly between the heat pipe the uranium zirconium hydride fuel rod, the periphery of reactor core is equipped with first radial reflection layer, first neutron absorbing layer and shielding layer from inside to outside in proper order, be equipped with the control rotary drum in the first radial reflection layer, the control rotary drum is provided with a plurality of spacing rings and arranged outside the reactor core, and the control rotary drum is driven by the driving unit to rotate.

2. The intrinsically safe reactor system of claim 1, wherein the working fluid in the heat pipe is mercury, diphenyl ether, or naphthalene.

3. The intrinsically safe reactor system of claim 1, wherein the uranium zirconium hydride fuel rods consist of zirconium hydride crystals as moderator and enriched uranium as fuel.

4. The intrinsically safe reactor system of claim 1, wherein the heat pipes are medium temperature heat pipes.

5. The intrinsically safe reactor system of claim 1, wherein the control drum comprises a second radially reflective layer and a second neutron absorbing layer, the second neutron absorbing layer being radiused to an edge of the second radially reflective layer.

6. The intrinsically safe reactor system of claim 5, wherein the second radially reflective layer is a solid cylindrical structure.

7. The intrinsically safe reactor system of claim 1, wherein a first valve is provided in a conduit between the outlet port and the inlet end of the turbine.

8. The reactor system with high intrinsic safety according to claim 1, wherein a feed water pump is provided on the pipe between the gas outlet end of the condenser and the water inlet.

9. The intrinsically safe reactor system of any one of claims 1 to 8, wherein the metal matrix has a polygonal cross-section.