CN110783010A - Thermoelectric power generation unit, molten salt reactor, and operation method and application thereof - Google Patents

Thermoelectric power generation unit, molten salt reactor, and operation method and application thereof Download PDF

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Publication number
CN110783010A
CN110783010A CN201911059455.XA CN201911059455A CN110783010A CN 110783010 A CN110783010 A CN 110783010A CN 201911059455 A CN201911059455 A CN 201911059455A CN 110783010 A CN110783010 A CN 110783010A
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end sleeve
heat pipe
heat
cold end
hot end
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陈兴伟
戴叶
崔德阳
于世和
邹杨
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Shanghai Institute of Applied Physics of CAS
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Shanghai Institute of Applied Physics of CAS
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D7/00Arrangements for direct production of electric energy from fusion or fission reactions
    • G21D7/04Arrangements for direct production of electric energy from fusion or fission reactions using thermoelectric elements or thermoionic converters
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

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  • Chemical & Material Sciences (AREA)
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  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a temperature difference power generation unit, a molten salt reactor, an operation method and application thereof. The thermoelectric power generation unit is used for a heat pipe condensation end and comprises a hot end sleeve and a cold end sleeve; the hot end sleeve is sleeved outside the condensation end of the heat pipe, the outer side wall of the hot end sleeve is a plane, and the bottom of each hot end sleeve is connected with the bottom of the adjacent hot end sleeve to form a hot end sleeve; each hot end sleeve is sleeved with a cold end sleeve which is matched with the hot end sleeve and provided with an inner cavity, the bottom of each cold end sleeve is communicated with the bottom of the cold end sleeve adjacent to the cold end sleeve to form a cold end sleeve with an inner cavity, and the cold end sleeve is provided with a cooling medium inlet and a cooling medium outlet; a thermoelectric generation piece is pasted between the outer side wall of the hot end sleeve and the inner side wall of the cold end sleeve; the outer side wall of the hot end sleeve is attached to the inner side wall of the cold end sleeve at the position where the thermoelectric generation sheet is not attached. The thermoelectric power generation unit can improve the heat exchange capacity.

Description

Thermoelectric power generation unit, molten salt reactor, and operation method and application thereof
Technical Field
The invention relates to a thermoelectric power generation unit, a molten salt reactor, an operation method and application thereof.
Background
With the development of science and technology, people are accelerated in exploring special environments such as outer space, deep sea and the like, and the traditional energy system is difficult to meet the use requirement of large-scale special equipment for long-term work due to the reasons of large size, poor cruising ability or poor adaptability to severe working environments such as high and low temperature, vacuum, radiation, impact, vibration and the like. The technical development of a safe and reliable nuclear power supply which is not influenced by the environment and has long service life is increasingly paid attention.
The stack types currently considered internationally as being suitable for particular environments include gas-cooled stack types, which require operating pressures that result in systems of large mass and size, and liquid-cooled stack types, which limit their use in particular environments. The molten salt reactor (one of liquid cooling reactor types) is one of important reactor types of the fourth generation advanced reactor, takes high boiling point molten salt as nuclear fuel, and has the advantages of high power density, high output temperature, high thermoelectric efficiency, simple structure, simple and easy operation, safety, reliability and the like. The application of the molten salt reactor to an energy system has great advantages and is an ideal energy source for outer space and deep sea exploration tasks.
Chinese patent document CN109243653A, published japanese patent No. 2019.01.18, discloses a nuclear reactor which converts thermal energy and electric energy using heat pipes, thermocouple conversion elements, and cooling water. However, the inventor of the present invention hopes to point out that, in the technical solution, the thermocouple conversion elements are arranged at intervals, the cooling water channel is arranged between the thermocouple conversion elements, and the heat pipe is inserted into the thermocouple conversion elements, so that the heat exchange capability of the thermoelectric power generation unit with the structure is not ideal.
Disclosure of Invention
The invention aims to solve the technical problem of providing a novel temperature difference power generation unit, a molten salt reactor, an operation method and application thereof in order to overcome the defect that the temperature difference power generation unit of the reactor for the condensation end of a heat pipe in the prior art is not ideal enough in heat exchange capacity.
The invention solves the technical problems through the following technical scheme:
the invention provides a temperature difference power generation unit, which is used for a heat pipe condensation end and comprises a hot end sleeve and a cold end sleeve; the hot end sleeves correspond to the condensation ends of the heat pipes one by one; the hot end sleeve is used for being sleeved outside the condensation end of the heat pipe and is suitable for the condensation end of the heat pipe, the outer side wall of the hot end sleeve is a plane, and the bottom of each hot end sleeve is connected with the bottom of the adjacent hot end sleeve to form a hot end sleeve; each hot end sleeve is sleeved with a cold end sleeve which is matched with the hot end sleeve and provided with an internal cavity, the bottom of each cold end sleeve is communicated with the bottom of the cold end sleeve adjacent to the cold end sleeve to form a cold end sleeve with an internal cavity, and the cold end sleeve is provided with a cooling medium inlet and a cooling medium outlet; thermoelectric generation pieces are attached between the outer side wall of the hot end sleeve and the inner side wall of the cold end sleeve; the outer side wall of the hot end sleeve is attached to the inner side wall of the cold end sleeve at the position where the thermoelectric generation piece is not attached.
In the invention, the shape of the outer side wall of the hot end sleeve is preferably the same as that of the outer side wall of the regular hexagonal prism.
In the present invention, the material of the thermal end sleeve can be a metal material with good thermal conductivity, preferably copper, which is conventionally used in the field.
In the present invention, preferably, the bottom surface of the heat end sleeve is a horizontal surface.
In the present invention, the material of the cold end sleeve can be a material with better thermal conductivity, which is conventionally used in the field, and is preferably copper.
In the invention, the inner cavity of the cold end sleeve can be internally provided with baffle plates or fins according to the heat exchange requirement of the condensation end of the heat pipe.
In the present invention, preferably, the bottom surface of the cold end sleeve is a horizontal surface.
In the present invention, preferably, the cooling medium inlet is disposed on a bottom side wall of the cold end sleeve, and the cooling medium outlet is disposed on a top side wall of the cold end sleeve, so as to implement countercurrent heat exchange.
In the invention, the thermoelectric generation piece can be an energy-saving pieceThe high-temperature resistant material conventionally used for the field is preferably a cobalt-based oxide, more preferably a Ca-Co-O-based thermoelectric material, the component of which is Ca 3Co 4O 9
In the invention, the thermoelectric generation piece and the hot end sleeve can be coated with high-temperature-resistant inorganic glue for enhancing heat conduction, and the inorganic glue can be an aluminosilicate adhesive for example. Preferably, the aluminosilicate adhesive is JL-767C, and the manufacturer is Dongguan adhesive product Co.
In the invention, the thermoelectric generation piece and the cold end sleeve can be coated with high-temperature-resistant inorganic glue for enhancing heat conduction, and the inorganic glue can be an aluminosilicate adhesive for example. Preferably, the aluminosilicate adhesive is JL-767C, and the manufacturer is Dongguan adhesive product Co.
The invention also provides a molten salt reactor, which comprises fuel salt, a heat pipe, a reactor core container, a reflecting layer and a shielding layer; the reflecting layer and the shielding layer are sequentially arranged outside the reactor core container; the fuel salt is filled in the core vessel; one end of the heat pipe is inserted into the fuel salt, and the other end of the heat pipe is used as a condensation end of the heat pipe and extends out of the shielding layer; the condensation end of the heat pipe is provided with the temperature difference power generation unit.
In the present invention, preferably, the molten salt reactor is a molten salt reactor used in the deep sea exploration field. In this case, preferably, the cooling medium inlet is a cooling water inlet, and the cooling medium outlet is a cooling water outlet.
In the present invention, the fuel salt may be a molten salt containing nuclear fuel, which is conventional in the art, and may be, for example, a high boiling point molten salt, preferably a fluorine salt or a chlorine salt. The fuel salt is preferably LiF-UF 4
In the invention, the material of the heat pipe can be a conventional high-temperature-resistant, corrosion-resistant and irradiation-resistant material in the field, preferably a Mo-Re alloy or a Hastelloy alloy, and more preferably a Hastelloy alloy.
In the present invention, the heat pipe may be a heat pipe conventionally used in the art, which is generally a section of closed pipe containing a working medium, and may be in various shapes, such as a bent pipe or a straight pipe, preferably a cylindrical straight pipe.
In the present invention, the working medium inside the heat pipe may be a working medium conventionally used in the art, such as alkali metal (lithium, sodium, potassium or cesium) or silver, preferably sodium or potassium, more preferably sodium.
In the invention, the arrangement mode of the heat pipes refers to the arrangement mode of the tube arrays in the shell-and-tube heat exchanger, and preferably is a regular triangle arrangement mode.
In the invention, the material of the reactor core container can be a high-temperature-resistant, corrosion-resistant and irradiation-resistant material which is conventional in the field, preferably Mo-Re alloy or Hastelloy, and more preferably Hastelloy.
In the present invention, the material of the reflective layer may be a material with strong neutron reflection capability, which is conventionally used in the art, and is preferably beryllium oxide.
In the invention, a control drum can be arranged in the reflecting layer according to the conventional arrangement mode in the field, and the material of the control drum can be a material with strong neutron reflection capability, which is conventionally used in the field, and is preferably beryllium oxide. Wherein, a neutron absorber is arranged on one side of the control drum according to the routine in the field, and the material of the neutron absorber can be a material with strong neutron absorption capacity, preferably boron carbide.
In the invention, the outer side of the shielding layer is preferably provided with a heat insulation layer, the heat pipe condensation end, the heat end sleeve and the cold end sleeve are all positioned in the heat insulation layer, and the heat insulation layer is arranged for reducing the heat loss of the system. The heat-insulating layer is preferably provided with an inner layer and an outer layer, the inner layer is made of aluminum silicate fibers, and the outer layer is made of a nano heat-insulating material.
In a preferred embodiment of the present invention, the heat pipes are cylindrical straight pipes, and the arrangement of the heat pipes is a regular triangle arrangement; the shape of the outer side wall of the hot end sleeve is the same as that of the outer side wall of the regular hexagonal prism; the bottom surface of the heat end sleeve is vertical to the longitudinal axis of the heat pipe; the bottom surface of the cold end sleeve is vertical to the longitudinal axis of the heat pipe; the cooling medium inlet is arranged on the side wall of the bottom of the cold end sleeve, and the cooling medium outlet is arranged on the side wall of the top of the cold end sleeve.
In a more preferred embodiment of the present invention, the heat pipe is made of hastelloy, and the working medium inside the heat pipe is sodium; the material of the hot end sleeve is copper; the cold end sleeve is made of copper; the heat pipe is characterized in that a heat insulation layer is arranged on the outer side of the shielding layer, and the heat pipe condensation end, the heat end sleeve and the cold end sleeve are all positioned in the heat insulation layer; the thermoelectric generation piece is a Ca-Co-O-based thermoelectric material, and the component of the thermoelectric generation piece is Ca 3Co 4O 9
In a further preferred embodiment of the present invention, the fuel salt is LiF-UF 4(ii) a The reactor core container is made of hastelloy; the reflecting layer is made of beryllium oxide; a control drum is arranged in the reflecting layer, and the control drum is made of beryllium oxide; a neutron absorber is arranged on one side of the control drum, and the neutron absorber is made of boron carbide.
The invention also provides an operation method of the molten salt reactor, which comprises the following steps: the heat pipe with the heat transfer of fuel salt extremely outside the heat pipe condensation end the hot pot end cover, coolant in the cooling jacket constantly cools off the cold pot end cover, the thermoelectric generation piece utilizes the difference in temperature at its both ends to produce the electromotive force, converts heat energy into electric energy.
In the present invention, the skilled person knows that the temperature difference should reach more than 10 ℃, so that the generated energy can reach the available level. The inventors of the present invention have found that the temperature difference is preferably 250 ℃ or more, more preferably 325.9 ℃ or more, for example 480.6 ℃ or more.
In the present invention, the heat transfer coefficient on the cooling medium side is preferably 1170W/(m) 2K) or more, more preferably 1221W/(m) 2K) or more, more preferably 2700W/(m) 2K) above.
In the present invention, preferably, the temperature difference is 480.6 ℃ or more, and the thermoelectric generation element is a Ca-Co-O-based thermoelectric material containing Ca as a component 3Co 4O 9The heat exchange coefficient of one side of the cooling medium is 2700W/(m) 2K) toThe above. By adopting the technical scheme, the thermoelectric conversion efficiency can be greatly improved.
The invention also provides application of the molten salt reactor as a power supply in the field of outer space exploration and/or deep sea exploration.
In the present invention, preferably, the field is a deep sea exploration field.
In the invention, in the phrase "the hot end sleeve fits the hot end condensation end", the fitting refers to that the outer wall surface of the hot end condensation end of the heat pipe fits the inner wall surface of the hot end sleeve.
In the invention, each hot end sleeve is sleeved with a cold end sleeve which is matched with the hot end sleeve and provided with an internal cavity, wherein the matching refers to that the inner wall surface of the cold end sleeve is attached to the hot end sleeve which is attached with the thermoelectric generation piece.
On the basis of the common knowledge in the field, the above preferred conditions can be combined randomly to obtain the preferred embodiments of the invention.
The reagents and starting materials used in the present invention are commercially available.
The positive progress effects of the invention are as follows: compared with the temperature difference power generation unit with the existing structure, the temperature difference power generation unit enables the condensation end of the heat pipe to form a unique heat exchange structure, and the heat exchange capacity is further improved.
Drawings
FIG. 1 is a longitudinal sectional view of a molten salt stack of example 1;
FIG. 2 is a view taken along line A-A of FIG. 1;
in FIG. 3, FIG. a is a front view of a heat pipe in embodiment 1, and FIG. b is a top view of the heat pipe in embodiment 1;
in fig. 4, fig. a is a front view of the hot end cap of example 1 along a longitudinal section thereof, and fig. b is a top view of the hot end cap of example 1 along a cross-section perpendicular to the longitudinal section thereof;
in fig. 5, a is a front view of the thermoelectric generation element-attached hot side jacket of example 1 along a longitudinal section thereof, and b is a top view of the thermoelectric generation element-attached hot side jacket of example 1 along a cross section perpendicular to the longitudinal section thereof;
in fig. 6, a is a front view formed by sleeving the hot end sleeve adhered with the thermoelectric generation sheet shown in fig. 5 on a heat pipe, and a top view formed by sleeving the hot end sleeve adhered with the thermoelectric generation sheet shown in fig. 5 on the heat pipe;
in FIG. 7, FIG. a is a front view of the cold end sleeve of embodiment 1 along a longitudinal section thereof, and FIG. b is a top view of the cold end sleeve of embodiment 1;
FIG. 8 is a front view of the cold end sleeve of FIG. 7 in the integrated configuration of FIG. 6;
FIG. 9 is a top view of the cold end sleeve of FIG. 7 in the integrated configuration of FIG. 6;
description of reference numerals:
fuel salt 1
Heat pipe 2
Core vessel 3
Reflective layer 4
Control drum 41
Neutron absorber 411
Shielding layer 5
Hot end sleeve 6
Hot end sleeve 61
Cold end sleeve 7
Cold end sleeve 71
Cooling medium inlet 72
Cooling medium outlet 73
Thermoelectric power generation piece 8
Insulating layer 9
Detailed Description
The invention is further illustrated by the following examples, which are not intended to limit the scope of the invention. The experimental methods without specifying specific conditions in the following examples were selected according to the conventional methods and conditions, or according to the commercial instructions.
In the description of the present invention, it is to be understood that the terms "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc., indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus, are not to be construed as limiting the present invention.
Example 1
(1) Molten salt reactor
As shown in fig. 1 to 9, the molten salt reactor includes fuel salt 1, heat pipes 2, a core vessel 3, a reflective layer 4, and a shield layer 5; a reflecting layer 4 and a shielding layer 5 are sequentially arranged outside the reactor core container 3; the fuel salt 1 is filled in the reactor core container 3; one end of the heat pipe 2 is inserted into the fuel salt 1, and the other end of the heat pipe 2 is used as a condensation end of the heat pipe and extends out of a shielding layer 5 of the molten salt pile; a hot end sleeve 61 which is suitable for the condensation end of each heat pipe is sleeved outside the condensation end of each heat pipe, the outer side wall of each hot end sleeve 61 is a plane, and the bottom of each hot end sleeve is connected with the bottom of the adjacent hot end sleeve to form a hot end sleeve 6; each hot end sleeve is sleeved with a cold end sleeve 71 which is matched with the hot end sleeve and provided with an internal cavity, the bottom of each cold end sleeve is communicated with the bottom of the cold end sleeve adjacent to the cold end sleeve to form a cold end sleeve 7 with an internal cavity, and the cold end sleeve 7 is provided with a cooling medium inlet 72 and a cooling medium outlet 73; a thermoelectric generation piece 8 is pasted between the outer side wall of the hot end sleeve 6 and the inner side wall of the cold end sleeve 7; the outer side wall of the hot end sleeve 6 is attached to the inner side wall of the cold end sleeve 7 at the position where the thermoelectric generation piece is not attached.
Wherein the fuel salt 1 is LiF-UF 4(ii) a The heat pipe 2 is made of hastelloy; the heat pipe 2 is a section of closed straight pipe for accommodating working medium; the working medium in the heat pipe 2 is sodium; the arrangement mode of the heat pipes 2 is a regular triangle arrangement mode, and the center distance is 5 cm; the reactor core container 3 is made of hastelloy; the material of the reflecting layer 4 is beryllium oxide; a control drum 41 is arranged in the reflecting layer 4, and the control drum 41 is made of beryllium oxide; a neutron absorber 411 is arranged on one side of the control drum 41, and the neutron absorber 411 is made of boron carbide; the outer side of the shielding layer 5 is provided with a heat-insulating layer 9, and the condensation end of the heat pipe, the hot end sleeve 6 and the cold end sleeve 7 are all positioned in the heat-insulating layer 9;
the shape of the outer side wall of the hot end sleeve 61 is the same as that of the outer side wall of a regular hexagonal prism; the material of the hot end sleeve 6 is copper; the bottom surface of the hot end sleeve 6 is perpendicular to the longitudinal axis of the heat pipe 2(ii) a The cold end sleeve 7 is made of copper; the bottom surface of the cold end sleeve 7 is vertical to the longitudinal axis of the heat pipe 2; the cooling medium inlet 72 is arranged on the side wall of the bottom of the cold end sleeve 7, and the cooling medium outlet 73 is arranged on the side wall of the top of the cold end sleeve 7, so that the countercurrent heat exchange can be realized; the cooling medium inlet is a cooling water inlet, and the cooling medium outlet is a cooling water outlet; the thermoelectric generation piece 8 is a Ca-Co-O based thermoelectric material with the component of Ca 3Co 4O 9
Wherein, aluminosilicate adhesive is coated between the thermoelectric generation piece 8 and the hot end sleeve 6, the model is JL-767C, and the manufacturer is the poly-strength adhesive product company Limited in Dongguan.
Wherein, aluminosilicate adhesive is coated between the thermoelectric generation piece 8 and the cold end sleeve 7, the model is JL-767C, and the manufacturer is the poly-strength adhesive product company Limited in Dongguan.
The number of the heat pipes 2 is 37, the outer diameter of each heat pipe 2 is 32mm, the distance between the heat pipes is 50mm, the length of a condensation end of each heat pipe is 4cm, the side length of the top surface of the hot end sleeve 61 is 20.8mm, the side length of the outer top surface of the cold end sleeve 71 is 26.5mm, the side length of the inner top surface of the cold end sleeve 71 is 25.4mm, the thickness of each thermoelectric generation piece is 4mm, and the thickness of the cold end sleeve is 1 mm; the inner diameter of the reactor core container is 35cm, the inner height of the reactor core container is 62cm, and the wall thickness of the reactor core container 3 is 2 cm; the thickness of the reflecting layer 4 is 12cm, the thickness of the shielding layer 5 is 10cm, and the thickness of the insulating layer 9 is 10 cm; each of six outer side surfaces of the hot end sleeve 61 is respectively bonded with 2 thermoelectric generation pieces 8, and the length and the width of each thermoelectric generation piece are 20mm and 20 mm.
(2) Method of operation
Rotating the control drum in the molten salt reactor to enable the neutron absorber to be far away from fuel salt, enabling the molten salt reactor to reach critical state, and keeping a certain thermal power to operate; heating and melting the fuel salt; after the fuel salt is melted, rotating the control drum to slowly heat up to 50 kW; and finally, adjusting the heat dissipation power of the condensation end of the heat pipe to ensure that the heat brought out by the heat pipe is matched with the heat generated by the reactor core, and the reactor operates stably.
The heat pipe transfers the heat of the fuel salt to the hot end sleeve outside the condensation end of the heat pipe, the cooling medium continuously cools the cold end sleeve, and the thermoelectric generation piece generates electromotive force by utilizing the temperature difference at the two ends of the thermoelectric generation piece to convert the heat energy into electric energy.
Wherein the flow rate of the cooling water is 1kg/s, the inlet water temperature of the cooling water inlet is 300K, and the outlet water temperature of the cooling water outlet is 315.5K; the reactor core temperature is 973K, the hot end temperature of the thermoelectric generation piece is 946.6K, the cold end temperature of the thermoelectric generation piece is 466K, and the temperature difference between the hot end and the cold end of the thermoelectric generation piece is 480.6K.
The technical effects are as follows: through FLUENT heat transfer analysis, the heat exchange coefficient of one side of the cooling water is 2700W/(m) 2K), the thermoelectric generation efficiency can reach more than 12%. By MCNP simulation analysis, the residual reactivity of the reactor core is 1.003 and is more than 1 after the molten salt reactor operates for 10 years under the full power of 50kW, which indicates that the reactor can also operate, so the molten salt reactor can operate for more than 10 years.
Example 2
(1) Molten salt reactor
The power of the molten salt reactor is 10kw, the inner diameter of the reactor core container is 30cm, the distance between the heat pipes is adjusted to 60mm, the number of the heat pipes is 19, and the rest is the same as the molten salt reactor in the embodiment 1.
(2) Method of operation
The method is carried out in the molten salt reactor, wherein the flow of cooling water is 0.2kg/s, the inlet water temperature of a cooling water inlet is 300K, and the outlet water temperature of a cooling water outlet is 330.2K; the operation method is the same as that of the embodiment 1 except that the temperature of the reactor core is 873K, the temperature of the hot end of the thermoelectric generation piece is 833.2K, the temperature of the cold end of the thermoelectric generation piece is 517.3K, and the temperature difference between the hot end and the cold end of the thermoelectric generation piece is 325.9K.
The technical effects are as follows: the heat transfer coefficient of the cooling water side is 1221W/(m) through FLUENT heat transfer analysis 2K), the thermoelectric generation efficiency can reach more than 10%. By MCNP simulation analysis, the molten salt reactor can operate for more than 8.5 years under the full power of 10 kW.
Comparative example 1
(1) Molten salt reactor
The structure of the thermoelectric power generation unit is the same as that of Chinese patent document CN109243653A mentioned in the background art, 19 heat pipes are inserted in a thermocouple conversion element (comprising a copper plate and a thermoelectric power generation sheet attached between the copper plate and a cooling water channel), cooling water is introduced into the cooling water channel, the cooling water channel is composed of two copper plates, the thickness of the copper plate forming the cooling water channel is 1mm, and the width of the cooling water channel is 7.1 mm; the temperature difference between the hot end and the cold end of the thermoelectric generation piece is 338K, and the other parameters are the same as those of the molten salt reactor in the embodiment 2.
(2) Method of operation
The operation of the reactor was the same as that of example 2.
The technical effects are as follows: through FLUENT heat transfer analysis, the heat exchange coefficient of the cooling water side is 1026W/(m) 2·k)。
It can be seen that the thermoelectric generation unit used in the molten salt reactor of example 2 has a heat exchange coefficient on the cooling water side increased by 19% as compared with that of comparative example 1. The thermoelectric power generation unit disclosed by the invention forms a unique heat exchange structure at the condensation end of the heat pipe, and the structure is superior to that of the comparative example 1, so that the heat exchange capability can be further improved, and the thermoelectric power generation unit is more suitable for special environments such as outer space and deep sea and has great application potential.
While specific embodiments of the invention have been described above, it will be appreciated by those skilled in the art that this is by way of example only, and that the scope of the invention is defined by the appended claims. Various changes and modifications to these embodiments may be made by those skilled in the art without departing from the spirit and scope of the invention, and these changes and modifications are within the scope of the invention.

Claims (10)

1. A temperature difference power generation unit is used for a heat pipe condensation end and is characterized by comprising a hot end sleeve and a cold end sleeve; the hot end sleeves correspond to the condensation ends of the heat pipes one by one; the hot end sleeve is used for being sleeved outside the condensation end of the heat pipe and is suitable for the condensation end of the heat pipe, the outer side wall of the hot end sleeve is a plane, and the bottom of each hot end sleeve is connected with the bottom of the adjacent hot end sleeve to form a hot end sleeve; each hot end sleeve is sleeved with a cold end sleeve which is matched with the hot end sleeve and provided with an internal cavity, the bottom of each cold end sleeve is communicated with the bottom of the cold end sleeve adjacent to the cold end sleeve to form a cold end sleeve with an internal cavity, and the cold end sleeve is provided with a cooling medium inlet and a cooling medium outlet; thermoelectric generation pieces are attached between the outer side wall of the hot end sleeve and the inner side wall of the cold end sleeve; the outer side wall of the hot end sleeve is attached to the inner side wall of the cold end sleeve at the position where the thermoelectric generation piece is not attached.
2. The thermoelectric power generation unit of claim 1, wherein the shape of the outer sidewall of the hot end sleeve is the same as the shape of the outer sidewall of a regular hexagonal prism;
and/or the material of the hot end sleeve is copper;
and/or the bottom surface of the hot end sleeve is a horizontal surface.
3. The thermoelectric power generation unit of claim 1, wherein the cold end sleeve is made of copper;
and/or the bottom surface of the cold end sleeve is a horizontal plane;
and/or the cooling medium inlet is arranged on the side wall of the bottom of the cold end sleeve, and the cooling medium outlet is arranged on the side wall of the top of the cold end sleeve.
4. The thermoelectric generation unit of claim 1, wherein the thermoelectric generation sheet is a cobalt-based oxide, preferably a Ca-Co-O-based thermoelectric material, the component of which is Ca 3Co 4O 9
And/or an aluminosilicate adhesive is coated between the thermoelectric generation piece and the hot end sleeve, and the type of the aluminosilicate adhesive is preferably JL-767C;
and/or an aluminosilicate adhesive is coated between the thermoelectric generation piece and the cold end sleeve, and the type of the aluminosilicate adhesive is preferably JL-767C.
5. A molten salt reactor comprising fuel salt, heat pipes, a core vessel, a reflective layer and a shielding layer; the reflecting layer and the shielding layer are sequentially arranged outside the reactor core container; the fuel salt is filled in the core vessel; one end of the heat pipe is inserted into the fuel salt, and the other end of the heat pipe is used as a condensation end of the heat pipe and extends out of the shielding layer; the thermoelectric power generation unit is characterized in that the condensation end of the heat pipe is provided with the thermoelectric power generation unit as claimed in any one of claims 1 to 4.
6. The molten salt stack of claim 5, wherein the fuel salt is a molten salt containing nuclear fuel, the molten salt being a fluoride or chloride salt; the fuel salt is preferably LiF-UF 4
And/or the heat pipe is made of Mo-Re alloy or Hastelloy, preferably Hastelloy;
and/or the heat pipe is a cylindrical straight pipe;
and/or the working medium in the heat pipe is sodium or potassium, preferably sodium;
and/or the arrangement mode of the heat pipes is a regular triangle arrangement mode.
7. The molten salt reactor of claim 5, wherein the heat pipes are cylindrical straight pipes, and the arrangement of the heat pipes is a regular triangle arrangement; the shape of the outer side wall of the hot end sleeve is the same as that of the outer side wall of the regular hexagonal prism; the bottom surface of the heat end sleeve is vertical to the longitudinal axis of the heat pipe; the bottom surface of the cold end sleeve is vertical to the longitudinal axis of the heat pipe; the cooling medium inlet is arranged on the side wall of the bottom of the cold end sleeve, and the cooling medium outlet is arranged on the side wall of the top of the cold end sleeve; preferably, the heat pipe is made of hastelloy, and the working medium in the heat pipe is sodium; the material of the hot end sleeve is copper; the cold end sleeve is made of copper; the heat pipe is characterized in that a heat insulation layer is arranged on the outer side of the shielding layer, and the heat pipe condensation end, the heat end sleeve and the cold end sleeve are all positioned in the heat insulation layer; the thermoelectric generation piece is a Ca-Co-O-based thermoelectric material, and the component of the thermoelectric generation piece is Ca 3Co 4O 9
8. A method of operating a molten salt reactor, the method being carried out in a molten salt reactor according to any one of claims 5 to 7, the method comprising the steps of: the heat pipe with the heat transfer of fuel salt extremely outside the heat pipe condensation end the hot pot end cover, coolant in the cooling jacket constantly cools off the cold pot end cover, the thermoelectric generation piece utilizes the difference in temperature at its both ends to produce the electromotive force, converts heat energy into electric energy.
9. Method of operating a molten salt reactor according to claim 8, characterized in that the temperature difference is above 325.9 ℃, preferably above 480.6 ℃;
alternatively, the heat transfer coefficient on the cooling medium side is 1221W/(m) 2K) or more, preferably 2700W/(m) 2K) above;
or the temperature difference is above 480.6 ℃, the thermoelectric generation piece is a Ca-Co-O-based thermoelectric material, and the component of the thermoelectric generation piece is Ca 3Co 4O 9The heat exchange coefficient of one side of the cooling medium is 2700W/(m) 2K) above.
10. Use of a molten salt stack as claimed in any one of claims 5 to 7 as a power source in the field of outer space exploration and/or deep sea exploration.
CN201911059455.XA 2019-11-01 2019-11-01 Thermoelectric power generation unit, molten salt reactor, and operation method and application thereof Pending CN110783010A (en)

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Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111478624A (en) * 2020-04-09 2020-07-31 中国科学院上海应用物理研究所 Hot end seat, thermoelectric power generation system, liquid reactor and operation method and application thereof
CN112349436A (en) * 2020-11-06 2021-02-09 西安交通大学 Liquid metal cooling wire winding positioning molten salt reactor core
US11931763B2 (en) 2019-11-08 2024-03-19 Abilene Christian University Identifying and quantifying components in a high-melting-point liquid
US12012827B1 (en) 2023-09-11 2024-06-18 Natura Resources LLC Nuclear reactor integrated oil and gas production systems and methods of operation
US12018779B2 (en) 2021-09-21 2024-06-25 Abilene Christian University Stabilizing face ring joint flange and assembly thereof

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11931763B2 (en) 2019-11-08 2024-03-19 Abilene Christian University Identifying and quantifying components in a high-melting-point liquid
CN111478624A (en) * 2020-04-09 2020-07-31 中国科学院上海应用物理研究所 Hot end seat, thermoelectric power generation system, liquid reactor and operation method and application thereof
CN111478624B (en) * 2020-04-09 2021-07-16 中国科学院上海应用物理研究所 Hot end seat, thermoelectric power generation system, liquid reactor and operation method and application thereof
CN112349436A (en) * 2020-11-06 2021-02-09 西安交通大学 Liquid metal cooling wire winding positioning molten salt reactor core
CN112349436B (en) * 2020-11-06 2021-10-19 西安交通大学 Liquid metal cooling wire winding positioning molten salt reactor core
US12018779B2 (en) 2021-09-21 2024-06-25 Abilene Christian University Stabilizing face ring joint flange and assembly thereof
US12012827B1 (en) 2023-09-11 2024-06-18 Natura Resources LLC Nuclear reactor integrated oil and gas production systems and methods of operation

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