CN112992389B - Molten salt fast reactor - Google Patents

Molten salt fast reactor Download PDF

Info

Publication number
CN112992389B
CN112992389B CN202110182330.7A CN202110182330A CN112992389B CN 112992389 B CN112992389 B CN 112992389B CN 202110182330 A CN202110182330 A CN 202110182330A CN 112992389 B CN112992389 B CN 112992389B
Authority
CN
China
Prior art keywords
molten salt
fast reactor
coolant
fuel
salt fast
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN202110182330.7A
Other languages
Chinese (zh)
Other versions
CN112992389A (en
Inventor
李晓晓
邹杨
傅瑶
崔德阳
戴叶
陈兴伟
卢恒
陈金根
蔡翔舟
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Shanghai Institute of Applied Physics of CAS
Original Assignee
Shanghai Institute of Applied Physics of CAS
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Shanghai Institute of Applied Physics of CAS filed Critical Shanghai Institute of Applied Physics of CAS
Priority to CN202110182330.7A priority Critical patent/CN112992389B/en
Publication of CN112992389A publication Critical patent/CN112992389A/en
Application granted granted Critical
Publication of CN112992389B publication Critical patent/CN112992389B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/44—Fluid or fluent reactor fuel
    • G21C3/54—Fused salt, oxide or hydroxide compositions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Abstract

The invention discloses a molten salt fast reactor. The molten salt fast reactor comprises an active area, wherein the active area comprises a fuel salt area and a cooling area; the coolant in the cooling zone is supercritical carbon dioxide. The molten salt fast reactor can realize higher reactor core outlet temperature and higher maximum output thermal power, can monitor reactivity in the reactor in real time, has small corrosion of the coolant to reactor core structural materials, reduces reactor core maintenance work, and improves the compactness and the economical efficiency of the molten salt fast reactor.

Description

Molten salt fast reactor
Technical Field
The invention relates to a molten salt fast reactor.
Background
In the six types of the reactor recommended by the advanced nuclear energy system of the fourth generation, the molten salt reactor is the only liquid fuel reactor and has the characteristics of inherent safety, high economy, high thermal efficiency, highest-level sustainable development and nuclear diffusion prevention and the like. The liquid fuel molten salt reactor can be designed into a thermal reactor (namely a molten salt thermal reactor) and also can be designed into a fast reactor (namely a molten salt fast reactor). The molten salt fast reactor does not need to add a moderator, has higher proliferation and transmutation performance, reduces impurities generated by irradiation of reactor core structural materials and maintenance work of the reactor core, and improves the operation economy.
Currently, molten salt fast reactors are usually designed as a tank type structure (such as MOSART and MSFR), in which fuel salt is used as nuclear fuel and coolant at the same time. Although fuel salt can absorb much heat, heat transfer is too slow, limiting the exit temperature of the molten salt stack, such as the core exit temperatures of MOSART and MSFR at 720 ℃ and 750 ℃, respectively. The core of the reactor only adopts one fluid, and the optimal temperature for process heating cannot be reached. For this reason, the solid physics research in berlin, germany, proposed a dual flow molten salt reactor (DFR) that uses liquid molten salt as the nuclear fuel and molten lead as the coolant, which can make the reactor have higher core exit problems (1127 ℃). However, because the DFR adopts liquid molten lead as a coolant, there are many technical problems, such as opacity of the liquid lead (which means opacity to γ and neutrons, and thus real-time detection of reactivity in the reactor is impossible), great pump load caused by high density of the lead coolant, corrosion and erosion of structural materials caused by the liquid molten lead under high-temperature and high-speed working conditions, and the like.
Therefore, there is a need in the art to develop a liquid molten salt reactor that has a high core outlet temperature, can monitor reactivity in the reactor in real time, and uses a coolant that has little corrosion to the core structural material.
Disclosure of Invention
The invention aims to overcome the technical problems that the core outlet temperature of a molten salt fast reactor in the prior art is generally lower, and when liquid molten lead is used as a coolant, the core outlet temperature is higher, but the defects of opaqueness, high density, high corrosivity and the like of the liquid molten lead exist. The invention provides a molten salt fast reactor for overcoming the defects. The molten salt fast reactor can realize higher reactor core outlet temperature and higher maximum output thermal power, can monitor reactivity in the reactor in real time, has small corrosion of the coolant to reactor core structural materials, reduces reactor core maintenance work, and improves the compactness and the economical efficiency of the molten salt fast reactor.
The invention solves the technical problems through the following technical scheme.
The invention provides a molten salt fast reactor, which comprises an active area, a cooling area and a control area, wherein the active area comprises a fuel salt area and a cooling area; the coolant in the cooling zone is supercritical carbon dioxide.
In the invention, the heat exchange area per unit volume of the cooling zone can be 2-358 m2/m3Preferably 37 to 290m2/m3More preferably 47 to 162m2/m3More preferably 130 to 162m2/m3. The unit volume heat exchange area refers to the average heat exchange area per cubic meter of the cooling zone.
In the present invention, in the active region, the volume ratio of the fuel salt region to the cooling region may be (3 to 25): 1, preferably (3 to 20): 1, more preferably (8 to 20): 1.
in the present invention, the shape of the active region may be conventional in the art and may be generally a hollow cylinder or a hollow hexagonal prism. The active region may have an equivalent diameter of 20 to 200cm, preferably 100 to 200cm, more preferably 145 to 200cm. The active region may have an equivalent height of 20 to 200cm, preferably 134 to 200cm, more preferably 145 to 200cm.
In the present invention, the active area may comprise an inner core shell, as is conventional in the art. The shape of the inner core shell may be conventional in the art and may be generally a hollow cylinder, a hollow sphere, or a hollow hexagonal prism. The wall thickness of the inner core shell may be conventional in the art, and is preferably 0.5 to 8cm, more preferably 2 to 8cm. The material of the inner core shell may be a nickel-based alloy, a molybdenum-based alloy, a rhenium-based alloy, a niobium-based alloy, or a zirconium-based alloy, and preferably an alloy consisting of any two or more of nickel, molybdenum, rhenium, niobium, and zirconium, such as a nickel-molybdenum alloy, a molybdenum-rhenium alloy, or a niobium-zirconium alloy.
In the present invention, the cooling zone may be a coolant flow channel as is conventional in the art, preferably a first coolant tube disposed within the active zone. Wherein the shape of the cross section of the first coolant pipe may be conventional in the art, and preferably is a hollow circle, a hollow hexagon, or a hollow quadrangle. The equivalent radius of the cross section of the first coolant tube may be conventional in the art, and is preferably 0.2 to 0.8cm, more preferably 0.5 to 0.8cm. The wall thickness of the first coolant tube may be 0.1 to 1cm, preferably 0.1cm. The tube wall material of the first coolant tube may be a structural material conventionally used in the art, preferably one or more of silicon carbide, carbon-carbon composite, nickel-based alloy, molybdenum-rhenium alloy, and niobium-zirconium alloy, and more preferably silicon carbide.
Wherein, the distance between the centers of two adjacent first coolant tubes may be greater than or equal to the equivalent diameter of the cross section of the first coolant tube, preferably 0.8 to 20cm, more preferably 1.5 to 3.92cm, and still more preferably 1.5 to 3.5cm, for example 2.1cm, as is conventional in the art. The first coolant tubes may be arranged in a triangular grid, a quadrangular grid, or a circular grid.
Wherein the number of the first coolant tube may be conventional in the art, preferably is 500 to 55000, more preferably is 590 to 55000, further more preferably is 1557 to 55000, still further more preferably is 2961 to 16123, for example 2056.
In the present invention, the fuel salt zone may be a space (fuel salt chamber) or a channel (e.g., fuel salt tube) for loading fuel salt as is conventional in the art. The fuel salt zone may be in flow communication or not.
Wherein the fuel salt chamber is a hollow region of the active zone, i.e., a hollow region of the inner core shell.
Wherein, the shape of the cross section of the fuel salt pipe can be conventional in the field, and is preferably a hollow circle, a hollow hexagon or a hollow quadrangle. The equivalent radius of the cross section of the fuel salt tube may be conventional in the art, preferably 0.2 to 0.8cm. The distance between the centers of two adjacent fuel salt tubes may be larger than the equivalent diameter of the cross section of the fuel salt tube as is conventional in the art, preferably 0.8 to 20cm, more preferably 2.1 to 20cm. A number of the fuel salt tubes may be arranged in a triangular grid, a quadrilateral grid, or a circular grid. The number of fuel salt tubes may be 500 to 55000, preferably 1714 to 55000.
As is conventional in the art, in the present invention, the fuel salt zone and the cooling zone are not in communication with each other. The relative positions of the fuel salt zone and the cooling zone may be spatially arranged as is conventional in the art, such that the cooling zone may cool the fuel salt zone.
In a preferred embodiment, the cooling zone is disposed in the fuel salt zone. Specifically, the fuel salt zone may be a fuel salt chamber in which the first coolant pipe is disposed.
In another preferred embodiment, the active region includes a substrate, and the fuel salt region and the cooling region are disposed in the substrate. Specifically, in the substrate, the first coolant pipe and the fuel salt pipe are provided, and the first coolant pipe and the fuel salt pipe are arranged adjacently at intervals, or the first coolant pipe is nested in the fuel salt pipe, or the fuel salt pipe is nested in the first coolant pipe. Wherein, the material of the substrate can be one or more of silicon carbide, carbon-carbon composite material, nickel-based alloy, molybdenum-rhenium alloy and niobium-zirconium alloy, and preferably silicon carbide.
In the invention, the molten salt fast reactor can further comprise a reactor core shell, and the active region is arranged inside the reactor core shell.
The core shell may be made of a material conventional in the art, preferably a nickel-based alloy, a molybdenum-based alloy, a rhenium-based alloy, a niobium-based alloy, or a zirconium-based alloy, more preferably an alloy consisting of any two or more of nickel, molybdenum, rhenium, niobium, and zirconium, and still more preferably a nickel-molybdenum alloy.
Wherein the wall thickness of the core housing may be 1-5 cm, preferably 3cm.
The shape of the core shell may be conventional in the art, and may be generally a hollow cylinder, a hollow sphere, or a hollow cuboid.
In the present invention, the fuel salt filled in the fuel salt zone may be a mixture of nuclear fuel and carrier salt as is conventional in the art.
Wherein the molar percentage of the nuclear fuel in the fuel salt may be conventional in the art, preferably 10% to 50%, more preferably 20% to 30%, and still more preferably 22%.
Wherein the nuclear fuel can be a compound containing one or more of thorium, uranium, plutonium and transuranic elements, preferably a compound containing uranium, which is conventionally used in the art,more preferably UF4。
The fissile nuclide in the nuclear fuel can be a fissile nuclide which is conventionally considered by a person skilled in the art to cause nuclear fission by bombardment with neutrons of any energy, preferably one or more of U-235, U-233, pu-239, pu-241, cm-243 and Cm-245, and more preferably U-235.
The mass percentage of the fissile nuclide in the nuclear fuel can be conventional in the field, and is preferably 10% -93%, and more preferably 19.75%.
Among them, the carrier salt may be a fluoride salt or a chloride salt conventionally used in the art. Wherein, the fluorine salt is preferably one or more of LiF, liBeF and LiNaKF, and more preferably LiF. When the fluoride salt contains Li, the enrichment degree of Li-7 in the fluoride salt can be conventional in the field, and is preferably 99-99.99%, and more preferably 99.95-99.99%. The chloride salt is preferably sodium chloride and/or potassium chloride; the enrichment degree of Cl-37 in the chlorine salt can be conventional in the field, and is preferably 24.23-100%. The enrichment may be an atomic fraction conventionally recognized by those skilled in the art, such as the enrichment of Li-7 being the percentage of the atomic number of Li-7 to the atomic number of the lithium element (including Li-6 and Li-7).
In the present invention, the working pressure of the coolant may be conventional in the art, and is preferably 8 to 30MPa, more preferably 15 to 25MPa, and still more preferably 20 to 25MPa.
In the present invention, a coolant inlet and a coolant outlet may be further provided on the sidewall of the core casing, and both the coolant inlet and the coolant outlet are communicated with the cooling zone.
Wherein, the coolant outlet can be connected with the thermoelectric conversion device according to the routine in the field, or the coolant outlet is connected with the thermoelectric conversion device through a heat exchanger. The thermoelectric conversion device is preferably a supercritical carbon dioxide thermoelectric conversion device. The thermoelectric conversion device converts heat energy into electric energy, and a stable nuclear power supply is provided for equipment. When the molten salt fast reactor is directly connected with the supercritical carbon dioxide thermoelectric conversion device, an intermediate heat exchanger is omitted, the compactness of a nuclear power system is favorably improved, and meanwhile, the heat efficiency of the straight-through Brayton cycle can reach more than 45 percent, for example, 45 to 60 percent.
In the present invention, a fuel salt inlet and a fuel salt outlet may be further provided on the sidewall of the core shell, and the fuel salt inlet and the fuel salt outlet are communicated with the fuel salt region.
Wherein the fuel salt inlet may be connected to a fuel salt treatment plant as is conventional in the art. The connection with the fuel salt treatment plant can realize the on-line and non-stop replacement of the fuel salt.
In the present invention, a reflective layer may be further disposed between the core casing and the active region.
The material of the reflecting layer can be a strong neutron reflecting material conventionally used in the art, and can be one or more of graphite, beryllium and beryllium oxide, and preferably beryllium oxide.
The thickness of the reflective layer can be conventional in the art, and is preferably 10-50 cm, and more preferably 20-50 cm.
In a preferred embodiment, the active area is in the shape of a hollow cylinder, the core shell is in the shape of a hollow cylinder, and the diameter of the reflective layer between the upper wall of the core shell and the upper wall of the active area is the same as the inner diameter of the core shell.
In a preferred embodiment, the active region is shaped as a hollow cylinder, the core housing is shaped as a hollow cylinder, and the diameter of the reflective layer between the lower wall of the core housing and the lower wall of the active region is the same as the inner diameter of the core housing.
In a preferred embodiment, the height of the reflective layer between the sidewall of the core shell and the sidewall of the active region is the same as the height of the active region.
Wherein a control drum may be further provided in the reflective layer between the sidewall of the core housing and the sidewall of the active zone. The control drum is used for controlling the reactivity of the active zone and for shutdown.
Wherein the cross-sectional diameter of the control drum can be 6-40 cm, preferably 14cm.
Wherein the control drum may be coated with a neutron absorber within 60 to 180 of its circumference, preferably within 120 of its circumference, as is conventional in the art.
Wherein, the height of the neutron absorber can be less than or equal to the height of the active region, preferably equal to the height of the active region.
Wherein the material of the neutron absorber may be conventional in the art, preferably boron carbide. When the material of the neutron absorber is boron carbide, the enrichment degree of boron-10 in the boron carbide is greater than or equal to 30%, preferably greater than or equal to 80%.
Preferably, the thickness of the neutron absorber is adjusted as is conventional in the art based on the location of the control drums, the number of control drums, and the reactivity and shutdown requirements, and may generally be greater than or equal to 3.0cm, preferably 4cm.
In the present invention, a second coolant pipe is provided in the reflective layer between the core shell and the active region, and the coolant in the second coolant pipe is supercritical carbon dioxide.
Preferably, the second coolant tube is in communication with the first coolant tube; more preferably, a chamber is further provided between the reflective layer and the active region, and the second coolant pipe and the first coolant pipe communicate through the chamber.
Preferably, the port of the second coolant tube is a coolant inlet.
In a preferred embodiment of the present invention, the second coolant tubes are disposed in the reflective layer between the sidewall of the core shell and the sidewall of the active zone; an upper cavity chamber is arranged above the active area, and a lower cavity chamber is arranged below the active area; the cooling region is a first coolant pipe arranged in the active region, and the upper end of each first coolant pipe penetrates through the upper wall of the active region and is communicated with the upper chamber; the lower end of each first coolant tube passes through the lower wall of the active zone and communicates with the lower chamber; the coolant flows through the coolant inlet, the second coolant tube, the lower chamber, the first coolant tube, the upper chamber, and the coolant outlet in this order.
Wherein, the thickness of the upper chamber along the longitudinal direction can be conventional in the field, and is preferably 1-10 cm.
The cross-sectional diameter of the upper cavity may be 30-260 cm, and preferably, the cross-sectional diameter of the upper cavity is the same as the inner diameter of the core shell.
Wherein the thickness of the lower chamber along the longitudinal direction can be conventional in the art, and is preferably 1-10 cm.
The cross-sectional diameter of the lower cavity may be 30-260 cm, and preferably, the cross-sectional diameter of the lower cavity is the same as the inner diameter of the core shell.
In the invention, the outlet temperature of the molten salt fast reactor can be generally 850-1350 ℃, preferably 950-1350 ℃, more preferably 1050-1350 ℃, and further more preferably 1150-1350 ℃.
In the present invention, the coolant may be fed and discharged in a conventional manner in the art, and may be generally fed downward and upward, fed lateral, or fed upward and downward.
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 positive progress effects of the invention are as follows:
1. the invention adopts supercritical carbon dioxide as an independent coolant, and has no boiling crisis in a single-phase state; the molten salt fast reactor has stable chemical properties, has low erosion rate to structural materials, reduces the maintenance work of a reactor core, and improves the operation economy of the molten salt fast reactor; compared with liquid metal (lead and the like), the material has a harder neutron energy spectrum, and can obtain higher multiplication performance;
2. the supercritical carbon dioxide coolant has high operating pressure (8-30 MPa), increases the density of the coolant, is close to liquid, has high heat transfer efficiency, and is beneficial to the compact design of a molten salt fast reactor; the molten salt fast reactor can be directly connected with a supercritical carbon dioxide thermoelectric conversion device, an intermediate heat exchanger is omitted, the compactness of a nuclear power system is favorably improved, and meanwhile, the heat efficiency of the straight-through Brayton cycle can be up to more than 45 percent, for example, up to 45 to 60 percent;
3. the molten salt fast reactor has higher core outlet temperature and higher maximum output thermal power, and is particularly suitable for providing stable nuclear power supply for high-power equipment executing short-term tasks (short-term tasks in the order of less than 1 year, particularly days or months).
Drawings
FIG. 1 is a longitudinal sectional view of a molten salt fast reactor according to example 1 of the present invention;
FIG. 2 is a cross-sectional view of a molten salt fast reactor of example 1 of the present invention;
FIG. 3 is a longitudinal section of a molten salt fast reactor of example 2 of the invention;
FIG. 4 is a cross-sectional view of a molten salt fast reactor of example 2 of the present invention.
Reference numerals
The device comprises an active area 1, a fuel salt area 11, a cooling area 12, an inner core shell 13, a substrate 14, a second coolant pipe 15, an outer core shell 2, a coolant inlet 3, a coolant outlet 4, a reflecting layer 5, a control drum 6, an upper chamber 7 and a lower chamber 8.
Detailed Description
The invention is further illustrated by the following examples, which are not intended to limit the scope of the invention.
Example 1
Example 1 molten salt fast reactor (pool type)
As shown in fig. 1 and 2, a molten salt fast reactor comprises an active region 1, wherein the active region 1 comprises a fuel salt region 11 and a cooling region 12; the coolant in the cooling zone 12 is supercritical carbon dioxide;
the total heat exchange area of cooling zone 12 is 138.44m2(ii) a The heat exchange area per unit volume of the cooling zone is 131.55m2/m3；
In the active region 1, the volume ratio of the fuel salt region 11 to the cooling region 12 is 6;
the cross section of the active region 1 is hollow and round; the equivalent diameter of the active region 1 is 100cm, and the equivalent height of the active region 1 is 134cm;
the active region 1 comprises an inner core shell 13, and the inner core shell 13 is in a hollow cylinder shape;
the wall thickness of the reactor core inner shell 13 is 2cm, and the material is nickel-molybdenum alloy;
the cooling zone 12 is a flow passage of a coolant, specifically, a first coolant pipe disposed in the active zone 1; the cross section of the first coolant pipe is in a hollow circular shape; the equivalent radius of the cross section of the first coolant pipe is 0.4cm; the pipe wall material of the first coolant pipe is silicon carbide; the center distance between two adjacent first coolant pipes is 1.05cm; the first coolant pipes are arranged in a triangular grid; the number of first coolant tubes is 2056; the wall thickness of the first coolant tube is 0.1cm;
the fuel salt region 11 is a space (fuel salt chamber) for loading fuel salt, and the fuel salt chamber is a hollow region of the active region 1, namely a hollow region of the inner core shell 13; in the present embodiment, the fuel salt zone 11 circulates, and in other embodiments, the fuel salt zone 11 may not circulate;
the fuel salt area 11 and the cooling area 12 are not communicated with each other; the cooling zone 12 is arranged in the fuel salt zone 11;
the molten salt fast reactor also comprises a reactor core shell 2, and the active region 1 is arranged inside the reactor core shell 2;
the material of the reactor core shell 2 is nickel-molybdenum alloy; the wall thickness of the reactor core shell 2 is 3cm; the core housing 2 is a hollow cylinder in shape;
the fuel salt filled in the fuel salt area 11 is a mixture of nuclear fuel and carrier salt; wherein the fuel salt comprises 22 mole percent of nuclear fuel, and the nuclear fuel is UF4The type of the fissile nuclide in the nuclear fuel is U-235, and the mass percent of the U-235 is 19.75 percent; wherein the carrier salt is LiF, and the enrichment degree of Li-7 is 99.95%;
the working pressure of the coolant is 20MPa;
the side wall of the reactor core shell 2 is further provided with a coolant inlet 3 and a coolant outlet 4, and the coolant inlet 3 and the coolant outlet 4 are both communicated with a cooling area 12;
the coolant outlet 4 is connected with a supercritical carbon dioxide thermoelectric conversion device (not shown in the figure); in other embodiments, a heat exchanger is provided between the coolant outlet 4 and the supercritical carbon dioxide thermoelectric conversion device; the heat energy is converted into electric energy through the thermoelectric conversion device, so that a stable nuclear power supply can be provided for equipment;
the side wall of the reactor core shell 2 is also provided with a fuel salt inlet (not shown) and a fuel salt outlet (not shown); the fuel salt inlet and the fuel salt outlet are communicated with the fuel salt area 11;
wherein, the fuel salt inlet is connected with the fuel salt treatment plant, and the fuel salt treatment plant can realize the on-line and non-stop fuel salt replacement;
a reflecting layer 5 is further arranged between the reactor core shell 2 and the active region 1; the material of the reflecting layer 5 is beryllium oxide; the thickness of the reflecting layer 5 is 20cm; the height of the reflecting layer 5 between the side wall of the reactor core shell 2 and the side wall of the active region 1 is the same as that of the active region 1;
six control drums 6 are also symmetrically disposed in the reflective layer 5 between the side wall of the core shell 2 and the side wall of the active region 1. A neutron absorber (not shown) is coated in the range of 120 degrees of the circumference of the control drum 6; the height of the neutron absorber is the same as that of the active region 1; the neutron absorber is made of boron carbide, wherein the enrichment degree of boron-10 in the boron carbide is 90%;
the control drum 6 is used for adjusting the distance between the neutron absorber and the active area 1 and further controlling the reactivity and stopping the reactor; the cross-sectional diameter of the control drum 6 is 14cm;
the thickness of the neutron absorber is 4.0cm;
a second coolant pipe 15 is provided in the reflecting layer 5 between the side wall of the core shell 2 and the side wall of the active region 1; an upper chamber 7 is arranged above the active region 1, a lower chamber 8 is arranged below the active region 1, and the upper end of each first coolant pipe penetrates through the upper wall of the active region 1 and is communicated with the upper chamber 7; the lower end of each first coolant pipe passes through the lower wall of the active zone 1 and communicates with the lower chamber 8; the coolant flows through the coolant inlet 3, the second coolant pipe 15, the lower chamber 8, the first coolant pipe, the upper chamber 7, and the coolant outlet 4 in this order;
wherein the position of the second coolant pipe 15 is staggered from the position of the control drum 6;
wherein, the thickness of the upper chamber 7 along the longitudinal direction is 1.5cm; the diameter of the cross section of the upper chamber 7 is the same as the inner diameter of the core shell 2;
wherein the thickness of the lower chamber 8 along the longitudinal direction is 2.5cm, and the diameter of the cross section of the lower chamber 8 is the same as the inner diameter of the reactor core shell 2;
the maximum output thermal power of the molten salt fast reactor is 100MWth, the inlet temperature is 808 ℃, and the outlet temperature is 1050 ℃.
EXAMPLE 2 molten salt fast reactor (pipe type)
As shown in fig. 3 and fig. 4, compared with the embodiment 1, the difference is only that, in the molten salt fast reactor of the embodiment, the active region 1 further includes a substrate 14, the fuel salt region 11 and the cooling region 12 are disposed in the substrate 14, the fuel salt region 11 is a fuel salt pipe disposed in the active region 1, and the fuel salt pipes are communicated with each other; the number of the first coolant pipes is 286; the material of the substrate 14 is silicon carbide; the cross section of the fuel salt pipe is hollow and round;
the fuel salt pipe and the first coolant pipe are adjacently and crossly arranged and are not communicated with each other; in other embodiments, the first coolant tube may be nested in the fuel salt tube, or the fuel salt tube may be nested in the first coolant tube;
the equivalent radius of the cross section of each fuel salt pipe is 0.4cm, the center distance between every two adjacent fuel salt pipes is 1.05cm, and the fuel salt pipes are arranged according to a triangular grid; the number of fuel salt tubes is 1714;
the volume ratio of fuel salt to coolant is 6.
Example 3
The only difference compared to example 1 is that the active region 1 has an equivalent diameter of 145cm and an equivalent height of 145cm;
the equivalent radius of the cross section of each first coolant pipe is 0.4cm, the center distance between every two adjacent first coolant pipes is 1.75cm, the plurality of first coolant pipes are arranged in a triangular grid, and the number of the first coolant pipes is 1557; the wall thickness of the first coolant tube is 0.1cm;
first of allThe total heat exchange area of the coolant pipe is 113.39m2(ii) a The heat exchange area per unit volume of the cooling zone was 47.35m2/m3(ii) a In the active zone 1, the volume ratio of the fuel salt zone 11 to the cooling zone 12 is 20:1;
the maximum output thermal power of the molten salt fast reactor is 150MWth, the inlet temperature is 808 ℃, and the outlet temperature is 1050 ℃.
Example 4
Compared with example 1, the difference is only that the active region 1 has an equivalent diameter of 200cm and an equivalent height of 200cm;
the equivalent radius of the cross section of the first coolant pipe is 0.4cm, the distance between the centers of two adjacent first coolant pipes is 1.75cm, a plurality of first coolant pipes are arranged according to a triangular grid, and the number of the first coolant pipes is 2961; the wall thickness of the first coolant tube is 0.1cm;
the total heat exchange area of the first coolant pipe was 297.55m2(ii) a The heat exchange area per unit volume of the cooling zone was 47.35m2/m3(ii) a In the active region 1, the volume ratio of the fuel salt region 11 to the cooling region 12 is 20:1;
the maximum output thermal power of the molten salt fast reactor is 400MWth, the inlet temperature is 899 ℃, and the outlet temperature is 1150 ℃.
Example 5
Compared with example 1, the difference is only that the active region 1 has an equivalent diameter of 200cm and an equivalent height of 200cm;
the equivalent radius of the cross section of the first coolant pipe is 0.25cm, the distance between the centers of two adjacent first coolant pipes is 0.75cm, a plurality of first coolant pipes are arranged according to a triangular grid, and the number of the first coolant pipes is 16123; the wall thickness of the first coolant tube is 0.1cm;
the total heat exchange area of the first coolant pipe is 1012.5m2(ii) a The heat exchange area per unit volume of the cooling zone is 161.14m2/m3(ii) a In the active zone 1, the volume ratio of the fuel salt zone 11 to the cooling zone 12 is 8:1;
the maximum output thermal power of the molten salt fast reactor is 1000MWth, the inlet temperature is 1080 ℃, and the outlet temperature is 1350 ℃.
Example 6
Compared to example 1, the difference is only that the active region 1 has an equivalent diameter of 100m and an equivalent height of 134cm;
the equivalent radius of the cross section of each first coolant pipe is 0.4cm, the distance between the centers of two adjacent first coolant pipes is 1.96cm, a plurality of first coolant pipes are arranged in a triangular grid, and the number of the first coolant pipes is 590; the wall thickness of the first coolant tube is 0.1cm;
the total heat exchange area of the first coolant pipe is 39.73m2(ii) a The heat exchange area per unit volume of the cooling zone is 37.75m2/m3(ii) a In the active region 1, the volume ratio of the fuel salt region 11 to the cooling region 12 is 25:1;
the maximum output thermal power of the molten salt fast reactor is 60MWth, the inlet temperature is 627 ℃, and the outlet temperature is 850 ℃.
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 or modifications to these embodiments may be made by those skilled in the art without departing from the principle and spirit of this invention, and these changes and modifications are within the scope of this invention.

Claims (85)

1. A molten salt fast reactor, characterized in that it comprises an active zone comprising a fuel salt zone and a cooling zone; the coolant in the cooling zone is supercritical carbon dioxide, the molten salt fast reactor further comprises a reactor core shell, and a coolant inlet and a coolant outlet are formed in the side wall of the reactor core shell;
a reflecting layer is arranged between the core shell and the active region, a second coolant pipe is arranged in the reflecting layer, and a port of the second coolant pipe is a coolant inlet; the cooling zone is a first coolant tube disposed within the active zone, the second coolant tube being in communication with the first coolant tube; an upper cavity chamber is arranged above the active area, and a lower cavity chamber is arranged below the active area; the upper end of each first coolant pipe penetrates through the upper wall of the active region and is communicated with the upper chamber; the lower end of each of the first coolant tubes passes through the lower wall of the active zone and communicates with the lower chamber; the coolant flows through the coolant inlet, the second coolant tube, the lower chamber, the first coolant tube, the upper chamber, and the coolant outlet in this order.
2. The molten salt fast reactor as claimed in claim 1, characterized in that the heat exchange area per unit volume of the cooling zone is 2 to 358m2/m3；
And/or in the active area, the volume ratio of the fuel salt area to the cooling area is (3 to 25): 1;
and/or the active region is in the shape of a hollow cylinder or a hollow hexagonal prism;
and/or the equivalent diameter of the active region is 20 to 200cm;
and/or the equivalent height of the active region is 20 to 200cm;
and/or, the active region comprises an inner core shell;
and/or the fuel salt area and the cooling area are not communicated with each other;
and/or the working pressure of the coolant is 8 to 30MPa;
and/or the coolant enters and exits in a mode of lower entering and upper exiting, side entering and side exiting or upper entering and lower exiting.
3. The molten salt fast reactor of claim 2, characterized in that the heat exchange area per unit volume of the cooling area is 37 to 290m2/m3。
4. The molten salt fast reactor of claim 3, characterized in that the heat exchange area per unit volume of the cooling zone is 47 to 162m2/m3。
5. The molten salt fast reactor of claim 4, characterized in that the heat exchange area per unit volume of the cooling zone is 130 to 162m2/m3。
6. The molten salt fast reactor according to claim 2, characterized in that in the active zone, the volume ratio of the fuel salt zone and the cooling zone is (3 to 20): 1.
7. the molten salt fast reactor according to claim 6, characterized in that in the active zone, the volume ratio of the fuel salt zone and the cooling zone is (8 to 20): 1.
8. the molten salt fast reactor of claim 2, characterized in that the active area has an equivalent diameter of 100 to 200cm.
9. The molten salt fast reactor of claim 8, characterized in that the active zone has an equivalent diameter of 145 to 200cm.
10. The molten salt fast reactor of claim 2, characterized in that the active zone has an equivalent height of 134 to 200cm.
11. The molten salt fast reactor of claim 10, characterized in that the equivalent height of the active zone is 145 to 200cm.
12. The molten salt fast reactor of claim 2, wherein the inner core shell is in the shape of a hollow cylinder, a hollow sphere, or a hollow hexagonal prism.
13. The molten salt fast reactor of claim 2, wherein the wall thickness of the inner core shell is 0.5-8cm.
14. The molten salt fast reactor of claim 13, wherein the wall thickness of the inner core shell is 2 to 8cm.
15. The molten salt fast reactor of claim 2, characterized in that the material of the inner core shell is a nickel-based alloy, a molybdenum-based alloy, a rhenium-based alloy, a niobium-based alloy or a zirconium-based alloy.
16. The molten salt fast reactor of claim 15, wherein the material of the inner core shell is an alloy consisting of any two or more of nickel, molybdenum, rhenium, niobium and zirconium.
17. The molten salt fast reactor of claim 16, wherein the material of the inner core shell is a nickel-molybdenum alloy, a molybdenum-rhenium alloy or a niobium-zirconium alloy.
18. The molten salt fast reactor of claim 2, characterized in that the working pressure of the coolant is 15 to 25mpa.
19. The molten salt fast reactor of claim 18, characterized in that the working pressure of the coolant is 20 to 25mpa.
20. The molten salt fast reactor of claim 1, characterized in that the shape of the cross section of the first coolant tube is a hollow circle, a hollow hexagon or a hollow quadrilateral.
21. The molten salt fast reactor of claim 20, characterized in that the equivalent radius of the cross section of the first coolant tube is 0.2 to 0.8cm.
22. The molten salt fast reactor of claim 21, characterized in that the equivalent radius of the cross section of the first coolant tube is 0.5 to 0.8cm.
23. The molten salt fast reactor of claim 20, characterized in that the wall thickness of the first coolant tube is 0.1 to 1cm.
24. The molten salt fast reactor of claim 23, wherein the first coolant tube has a wall thickness of 0.1cm.
25. The molten salt fast reactor of claim 20, wherein the tube wall material of the first coolant tube is one or more of silicon carbide, carbon-carbon composite, nickel-based alloy, molybdenum-rhenium alloy, and niobium-zirconium alloy.
26. The molten salt fast reactor of claim 25, wherein the material of the tube wall of the first coolant tube is silicon carbide.
27. The molten salt fast reactor of claim 20, wherein the center distance between two adjacent first coolant tubes is 0.8-20cm.
28. The molten salt fast reactor of claim 27, wherein the distance between centers of two adjacent first coolant tubes is 1.5 to 3.92cm.
29. The molten salt fast reactor of claim 28, wherein the distance between centers of two adjacent first coolant tubes is 1.5 to 3.5cm.
30. The molten salt fast reactor of claim 20, wherein the first coolant tubes are arranged in a triangular grid, a quadrilateral grid, or a circular grid.
31. The molten salt fast reactor of claim 20, characterized in that the number of the first coolant tubes is 500 to 55000.
32. The molten salt fast reactor of claim 20, characterized in that the number of the first coolant tubes is 590 to 55000.
33. A molten salt fast reactor as claimed in claim 20, characterised in that the number of the first coolant tubes is 1557 to 55000.
34. The molten salt fast reactor of claim 20, wherein the number of the first coolant tubes is 2961 to 16123.
35. A molten salt fast reactor as claimed in claim 1, characterised in that the fuel salt zone is a fuel salt chamber or a fuel salt tube.
36. The molten salt fast reactor of claim 35, characterized in that the fuel salt chamber is a hollow region of the active zone;
and/or the cross section of the fuel salt pipe is in the shape of a hollow circle, a hollow hexagon or a hollow quadrangle;
and/or the equivalent radius of the cross section of the fuel salt tube is 0.2 to 0.8cm;
and/or the central distance between two adjacent fuel salt pipes is 0.8 to 20cm.
37. The molten salt fast reactor of claim 36, wherein the distance between the centers of two adjacent fuel salt pipes is 2.1-20cm.
38. The molten salt fast reactor of claim 35, wherein a number of the fuel salt tubes are arranged in a triangular grid, a quadrilateral grid or a circular grid.
39. The molten salt fast reactor of claim 35, characterized in that the number of fuel salt tubes is 500 to 55000.
40. The molten salt fast reactor of claim 35, characterized in that the number of fuel salt tubes is 1714 to 55000.
41. The molten salt fast reactor of claim 35, wherein the cooling zone is disposed in the fuel salt zone, the fuel salt zone being a fuel salt chamber in which the first coolant tube is disposed;
alternatively, the active region comprises a substrate, the fuel salt region and the cooling region being disposed in the substrate.
42. The molten salt fast reactor of claim 41, characterized in that in the substrate, the first coolant tubes and the fuel salt tubes are provided, the first coolant tubes and the fuel salt tubes are adjacently arranged at intervals, or the first coolant tubes are nested in the fuel salt tubes, or the fuel salt tubes are nested in the first coolant tubes.
43. The molten salt fast reactor of claim 41, characterized in that the substrate material is one or more of silicon carbide, carbon-carbon composite, nickel-based alloy, molybdenum-rhenium alloy and niobium-zirconium alloy.
44. A molten salt fast reactor as claimed in claim 42, characterised in that the material of the substrate is silicon carbide.
45. A molten salt fast reactor as claimed in claim 1, characterised in that the fuel salt filled in the fuel salt zone is a mixture of nuclear fuel and carrier salt.
46. The molten salt fast reactor of claim 45, wherein the mole percent of the nuclear fuel in the fuel salt is 10% to 50%.
47. The molten salt fast reactor of claim 46, wherein a mole percentage of the nuclear fuel in the fuel salt is 20% to 30%.
48. The molten salt fast reactor of claim 47, characterized in that the molar percentage of the nuclear fuel in the fuel salt is 22%.
49. The molten salt fast reactor of claim 45, wherein the nuclear fuel is a compound containing one or more of thorium, uranium, plutonium and transuranics;
and/or the fissile nuclides in the nuclear fuel are one or more of U-235, U-233, pu-239, pu-241, cm-243 and Cm-245;
and/or the mass percentage of the fissile nuclide in the nuclear fuel is 10% -93%.
50. The molten salt fast reactor of claim 49, wherein the nuclear fuel is a compound containing uranium.
51. The molten salt fast reactor of claim 50, wherein the nuclear fuel is UF4。
52. The molten salt fast reactor of claim 49, wherein the fissile nuclear species in the nuclear fuel is U-235.
53. The molten salt fast reactor of claim 49, wherein a mass percentage of fissile species in the nuclear fuel is 19.75%.
54. The molten salt fast reactor of claim 45, characterized in that the carrier salt is a fluoride salt or a chloride salt.
55. A molten salt fast reactor as claimed in claim 54, characterised in that the fluoride salt is one or more of LiF, liBeF and LiNaKF;
and/or when the villiaumite contains Li element, the enrichment degree of Li-7 in the villiaumite is 99% -99.99%;
and/or the chloride salt is sodium chloride and/or potassium chloride;
and/or the enrichment degree of Cl-37 in the chloride salt is 24.23-100%.
56. The molten salt fast reactor of claim 55, characterized in that the fluorine salt is LiF.
57. The molten salt fast reactor of claim 55, wherein when the fluoride salt contains Li element, the enrichment degree of Li-7 in the fluoride salt is 99.95% -99.99%.
58. The molten salt fast reactor of claim 1, wherein the active region is disposed inside the core shell.
59. The molten salt fast reactor of claim 58, wherein the material of the core shell is an alloy consisting of any two or more of nickel, molybdenum, rhenium, niobium and zirconium,
and/or the wall thickness of the reactor core shell is 1 to 5cm
And/or the shape of the reactor core shell is a hollow cylinder, a hollow sphere or a hollow cuboid.
60. The molten salt fast reactor of claim 59, wherein the material of the core shell is a nickel molybdenum alloy.
61. The molten salt fast reactor of claim 59, wherein the core shell has a wall thickness of 3cm.
62. The molten salt fast reactor of claim 58, characterized in that the coolant outlet is connected with a thermoelectric conversion device, or the coolant outlet is connected with the thermoelectric conversion device through a heat exchanger;
and/or a fuel salt inlet and a fuel salt outlet are arranged on the side wall of the reactor core shell, and the fuel salt inlet and the fuel salt outlet are communicated with the fuel salt area;
and/or the material of the reflecting layer is one or more of graphite, beryllium and beryllium oxide.
63. The molten salt fast reactor of claim 62, characterized in that the thermoelectric conversion device is a supercritical carbon dioxide thermoelectric conversion device.
64. A molten salt fast reactor as claimed in claim 62, characterised in that the fuel salt inlet is connected to a fuel salt treatment plant.
65. The molten salt fast reactor of claim 62, wherein the material of the reflective layer is beryllium oxide.
66. The molten salt fast reactor of claim 62, wherein the reflective layer has a thickness of 10 to 50cm.
67. A molten salt fast reactor as claimed in claim 66, characterised in that the reflective layer has a thickness of 20 to 50cm.
68. The molten salt fast reactor of claim 62, wherein the active area is shaped as a hollow cylinder, the core shell is shaped as a hollow cylinder, and the diameter of the reflective layer between the upper wall of the core shell and the upper wall of the active area is the same as the inner diameter of the core shell;
and/or the active region is in the shape of a hollow cylinder, the core shell is in the shape of a hollow cylinder, and the diameter of the reflecting layer between the lower wall of the core shell and the lower wall of the active region is the same as the inner diameter of the core shell;
and/or the height of the reflecting layer between the side wall of the core shell and the side wall of the active region is the same as the height of the active region;
and/or a control drum is arranged in the reflecting layer between the side wall of the core shell and the side wall of the active area.
69. The molten salt fast reactor of claim 68, characterized in that the cross-sectional diameter of the control drum is 6 to 40cm;
and/or the control drum is covered with a neutron absorber within the range of 60-180 degrees of the circumference of the control drum;
and/or the height of the neutron absorber is less than or equal to the height of the active region.
70. The molten salt fast reactor of claim 69, wherein the cross-sectional diameter of the control drum is 14cm;
and/or the control drum is coated with a neutron absorber within 120 ° of its circumference.
71. The molten salt fast reactor of claim 69, wherein a height of the neutron absorber is equal to a height of the active zone.
72. The molten salt fast reactor of claim 69, wherein the neutron absorber material is boron carbide.
73. The molten salt fast reactor of claim 69, wherein the neutron absorber has a thickness of 3.0cm or more.
74. The molten salt fast reactor of claim 73, wherein the neutron absorber is 4cm thick.
75. The molten salt fast reactor of claim 72, wherein when the neutron absorber material is boron carbide, the boron-10 enrichment in boron carbide is greater than or equal to 30%.
76. The molten salt fast reactor of claim 72, wherein when the neutron absorber material is boron carbide, the boron-10 enrichment in boron carbide is greater than or equal to 80%.
77. The molten salt fast reactor of any one of claims 1 to 76, wherein the molten salt fast reactor comprises a core shell, and the active area is arranged inside the core shell.
78. A molten salt fast reactor as claimed in claim 77, characterised in that a chamber is provided between the reflective layer and the active region, the second coolant tubes and the first coolant tubes communicating through the chamber.
79. The molten salt fast reactor of claim 77, wherein the second coolant tubes are disposed in the reflective layer between the side walls of the core shell and the side walls of the active region.
80. A molten salt reactor as claimed in claim 77 in which the upper chamber is 1 to 10cm thick in the longitudinal direction.
81. The molten salt fast reactor as claimed in claim 77, characterized in that the cross-sectional diameter of the upper chamber is 30 to 260cm.
82. The molten salt fast reactor of claim 81 wherein the cross-sectional diameter of the upper chamber is the same as the inner diameter of the core shell.
83. A molten salt fast reactor as claimed in claim 77, characterised in that the lower chamber has a thickness in the longitudinal direction of 1 to 10cm.
84. A molten salt fast reactor as claimed in claim 77, wherein the cross-sectional diameter of the lower chamber is 30 to 260cm.
85. The molten salt fast reactor of claim 84, wherein a cross-sectional diameter of the lower chamber is the same as an inner diameter of the core shell.
CN202110182330.7A 2021-02-09 2021-02-09 Molten salt fast reactor Active CN112992389B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202110182330.7A CN112992389B (en) 2021-02-09 2021-02-09 Molten salt fast reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202110182330.7A CN112992389B (en) 2021-02-09 2021-02-09 Molten salt fast reactor

Publications (2)

Publication Number Publication Date
CN112992389A CN112992389A (en) 2021-06-18
CN112992389B true CN112992389B (en) 2022-11-01

Family

ID=76392906

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202110182330.7A Active CN112992389B (en) 2021-02-09 2021-02-09 Molten salt fast reactor

Country Status (1)

Country Link
CN (1) CN112992389B (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2023501357A (en) 2019-11-08 2023-01-18 アビリーン クリスチャン ユニバーシティ Identification and quantification of components in high melting point liquids
CN113658722B (en) * 2021-07-01 2024-02-06 中国科学院上海应用物理研究所 Molten salt reactor core structure
CN113851233A (en) * 2021-09-01 2021-12-28 中国科学院上海应用物理研究所 Radial shielding structure of molten salt reactor and molten salt reactor comprising same
CN113936820A (en) * 2021-09-15 2022-01-14 中国科学院上海应用物理研究所 Molten salt reactor core and molten salt reactor system

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1999059160A1 (en) * 1998-05-12 1999-11-18 Ansaldo Energia S.P.A. Cooling system for a nuclear reactor
WO2017162718A1 (en) * 2016-03-23 2017-09-28 Thoria As Molten salt reactor
CN111627572A (en) * 2020-06-04 2020-09-04 中国科学院上海应用物理研究所 Modularized molten salt reactor core and molten salt reactor

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2012135957A1 (en) * 2011-04-06 2012-10-11 Ottawa Valley Research Associates Ltd. Molten salt nuclear reactor
GB201318470D0 (en) * 2013-02-25 2013-12-04 Scott Ian R A practical molten salt fission reactor
CN105355247A (en) * 2015-11-19 2016-02-24 中国核动力研究设计院 Novel molten salt reactor energy transmission system with supercritical carbon dioxide
CN107945887B (en) * 2017-11-16 2019-10-01 中国科学院上海应用物理研究所 A kind of integrated small molten salt reactor
CN108511088B (en) * 2018-06-13 2023-07-28 中国科学院上海应用物理研究所 Heavy water moderated molten salt reactor core and heavy water moderated molten salt reactor system
CN112259263B (en) * 2020-10-26 2022-08-02 中国科学院上海应用物理研究所 Three-channel molten salt reactor core structure and three-channel molten salt reactor system

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1999059160A1 (en) * 1998-05-12 1999-11-18 Ansaldo Energia S.P.A. Cooling system for a nuclear reactor
WO2017162718A1 (en) * 2016-03-23 2017-09-28 Thoria As Molten salt reactor
CN111627572A (en) * 2020-06-04 2020-09-04 中国科学院上海应用物理研究所 Modularized molten salt reactor core and molten salt reactor

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
基于熔盐快堆的模型优化与Th-U增殖性能研究;李光超等;《核技术》;20170210(第02期);1-7 *

Also Published As

Publication number Publication date
CN112992389A (en) 2021-06-18

Similar Documents

Publication Publication Date Title
CN112992389B (en) Molten salt fast reactor
CN109509562B (en) Reactor core structure, molten salt pebble bed reactor, fuel management method of molten salt pebble bed reactor and reactor core loading method
US10878969B2 (en) Dual fluid reactor
US2961393A (en) Power breeder reactor
Forsberg et al. Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity
Huke et al. The Dual Fluid Reactor–A novel concept for a fast nuclear reactor of high efficiency
CN1319074C (en) Supercritical water nuclear reactor utilizing sleeve fuel assembly
EP2518733B1 (en) High-temperature gas-cooled reactor steam generating system and method
Swartz et al. Westinghouse eVinci™ heat pipe micro reactor technology development
US20220301732A1 (en) Nuclear reactor core architecture with enhanced heat transfer and safety
CN209496626U (en) Core structure and fused salt pebble bed reactor
US3211621A (en) Heterogeneous breeder or converter type neutronic reactor
RU2668230C1 (en) Fast neutron nuclear reactor with liquid metal coolant
CN112259263B (en) Three-channel molten salt reactor core structure and three-channel molten salt reactor system
Handwerk et al. Optimized core design of a supercritical carbon dioxide-cooled fast reactor
Wang et al. Neutron physics of the liquid‐fuel heat‐pipe reactor concept with molten salt fuel—Static calculations
US20140146934A1 (en) Compact Liquid Metal Cooled Spherical Fast Neutron Reactor Core Design
Holcomb et al. Current status of the advanced high temperature reactor
US2999057A (en) Homogeneous nuclear reactors
Guo et al. Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel
Li et al. Optimized core design and shield analysis of a medium temperature heat pipe cooled reactor
CN112216408A (en) Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system
CN216596965U (en) Fuel assembly and fused salt fast reactor body for isotope production
Mitachi et al. Characteristics of thorium molten-salt reactor with self-sustainability
CN213815564U (en) Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant