CN113270205A - Modularized pressure pipe type gas-cooled micro-reactor core - Google Patents
Modularized pressure pipe type gas-cooled micro-reactor core Download PDFInfo
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- CN113270205A CN113270205A CN202110332498.1A CN202110332498A CN113270205A CN 113270205 A CN113270205 A CN 113270205A CN 202110332498 A CN202110332498 A CN 202110332498A CN 113270205 A CN113270205 A CN 113270205A
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- 239000000463 material Substances 0.000 claims abstract description 17
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- 229910002804 graphite Inorganic materials 0.000 claims description 29
- 239000010439 graphite Substances 0.000 claims description 29
- 239000002826 coolant Substances 0.000 claims description 25
- 239000002574 poison Substances 0.000 claims description 10
- 231100000614 poison Toxicity 0.000 claims description 10
- 238000005253 cladding Methods 0.000 claims description 8
- 239000002245 particle Substances 0.000 claims description 8
- 239000008188 pellet Substances 0.000 claims description 8
- 239000011159 matrix material Substances 0.000 claims description 3
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Images
Classifications
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- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
-
- 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 modularized pressure tube type gas-cooled micro-reactor core, which comprises a fuel assembly, a reflecting layer and a control rod assembly, wherein the fuel assembly is arranged on the reflecting layer; the fuel assemblies are placed within a pressure tube such that the pressure tube serves as a pressure containment boundary for a core, the reflector layer and control rod assemblies being mounted outside the pressure tube. The invention has the beneficial effects that: the fuel assembly is placed into the pressure pipe, and the pressure pipe bears pressure to form modularization, so that the fuel assembly is convenient to install, and the problems of multiple high-temperature gas cooled reactor transportation elements, complex assembly and slow response and deployment are solved. The temperature of the reactor core outside the pressure tube is lower, so that the high-temperature resistance requirements of control rod components, tube-outside slowing materials and reflecting layer materials are reduced. The reactor core has excellent inherent safety, design flexibility, environmental adaptability and transportation and assembly convenience, and has great market potential in the fields of remote mountain power supply, aerospace, island power supply, deep sea power supply and the like.
Description
Technical Field
The invention belongs to the field of nuclear industry, and particularly relates to a modular pressure tube type gas-cooled micro-reactor core.
Background
Energy is an important basis for socioeconomic development, and increasingly prominent environmental pollution problems pose higher challenges to the optimization of energy structures. The nuclear energy is a clean, stable and high-power-density new energy source and is the best candidate for the base charge power. The safety of nuclear power is always the key point of common public concern and the direction of efforts of nuclear power researchers. Especially after the accident of the Japanese Fudao, the safe utilization of nuclear energy is more and more emphasized by people, and the design and research work of various advanced nuclear energy systems is accelerated.
High temperature gas cooled reactors, one of the advanced reactor types of the fourth generation nuclear power systems, are receiving attention due to their good intrinsic safety and high coolant outlet temperature. The excellent inherent safety is mainly reflected in that the adopted TRISO coated fuel particles can effectively prevent fission products from being released and the fuel from being corroded; the adopted graphite reactor core has large heat capacity, slow temperature transient state, capability of bearing high temperature and large emergency operation time allowance; the reactor core has small power density and strong temperature negative feedback, and can be shut down by means of the temperature negative feedback even if no emergency measures are taken under the accident condition.
In addition, the modular high-temperature gas cooled reactor can reduce a plurality of emergency facilities through reasonable design and optimization, simplify the design of a nuclear power plant, and has certain competitiveness in economy. Particularly, for remote areas where a power grid cannot reach, the diesel oil power generation cost is high, the pollution is large, the small modular high-temperature gas cooled reactor can safely, stably and cleanly supply power, and the energy requirements of the areas can be well met.
At present, the existing high-temperature gas cooled reactor design at home and abroad is based on a fixed non-moving reactor core. The core components need to be manufactured by previous machining at the factory and transported separately to the site of application. And a large number of components such as fuel assemblies, reflecting layers, control rods and the like need to be installed and debugged for a long time on site to reach a normal operation state, so that the requirements of container transportation, simple and convenient assembly and rapid deployment under special application situations are difficult to meet.
In view of the above, the present invention is particularly proposed.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a modular pressure tube type gas-cooled micro-reactor core which can meet the requirements of quick transportation and simple and convenient assembly.
The technical scheme of the invention is as follows:
a modular pressure tube type gas-cooled micro-reactor core comprises a fuel assembly, a reflecting layer and control rods; the fuel assemblies are placed within a pressure tube such that the pressure tube serves as a pressure containment boundary for a core, the reflector layer and control rods being mounted outside the pressure tube.
Further, the modular pressure tube type gas-cooled micro-reactor core comprises a fuel assembly and a fuel assembly, wherein the fuel assembly comprises graphite blocks, fuel rods, burnable poison rods and coolant flow channels; the fuel rods are arranged in the fuel rod channels of the graphite blocks, and the burnable poison rods are arranged in the burnable poison channels of the graphite blocks; the coolant flow channel is one or more of an independent coolant orifice channel provided on the graphite block, a coolant flow channel formed by a gap between the fuel rod and the graphite block, and a coolant flow channel centrally formed when the fuel rod is annular in cross section.
Further, the modular pressure tube gas-cooled micro-stack core comprises a plurality of fuel pellets stacked along the axial direction; the fuel pellet is formed by dispersing fuel particles in a matrix.
Further, in the above modular pressure tube type gas-cooled micro-reactor core, the fuel particles include a fuel core and a cladding structure cladding the fuel core.
Further, the modular pressure tube type air-cooled micro-reactor core also comprises an inner tube arranged in the pressure tube; the fuel assembly is disposed in the inner tube; the coolant flows in from the coolant flow channel between the pressure tube and the inner tube, joins outside the top or bottom reflector layer, and then flows out from the coolant flow channel in the fuel assembly.
Further, in the modular pressure tube type air-cooled micro-reactor core, a moderator material jacket layer is arranged outside the pressure tube, and the fuel assembly, the pressure tube and the moderator material jacket layer form a fuel assembly unit together; the control rod is arranged in a control rod passage of the control rod assembly; the control rod assembly is disposed adjacent to the fuel assembly unit.
Further, in the modular pressure tube type air-cooled micro-reactor core, a moderating material jacket layer is arranged outside the pressure tube; the control rods are disposed in the control rod passageways of the moderator material jacket such that the control rods and the fuel assembly are formed as a single unit.
The invention has the beneficial effects that:
1. the fuel assembly is placed into the pressure pipe, and the pressure pipe bears pressure to form modularization, so that the fuel assembly is convenient to install, and the problems of multiple high-temperature gas cooled reactor transportation elements, complex assembly and slow response and deployment are solved.
2. The pressure tube type assembly design avoids long-time field assembly, and improves the convenience of transportation, assembly and deployment of each part; the reactor core has excellent inherent safety, design flexibility, environmental adaptability and transportation and assembly convenience, and has great market potential in the fields of remote mountain power supply, aerospace, island power supply, deep sea power supply and the like.
3. The pressure pipe is cooled by the inlet coolant, the temperature of the core outside the pipe is lower, and the requirement of the control rod component on high temperature resistance is lowered. The jacket layer and the reflecting layer outside the pressure pipe can be considered to use slowing-down materials with lower working temperature and better slowing-down performance to replace traditional graphite materials, such as beryllium oxide, zirconium hydride, yttrium hydride and the like, so that the size of the core is further reduced.
Drawings
FIG. 1 is a schematic structural view of a modular pressure tube gas cooled micro-reactor core according to one embodiment of the present invention.
Fig. 2 is a schematic structural view of a modular pressure tube gas-cooled micro-reactor core according to another embodiment of the present invention.
Fig. 3 is an enlarged schematic view of a part of the structure in fig. 2.
Fig. 4 is a schematic axial cross-sectional view of fig. 2.
FIG. 5 is a control rod grouping schematic of the core of FIG. 2.
FIG. 6 is a schematic structural view of a control rod.
FIG. 7 is a graph of gas cooled micro-reactor burnup characteristics.
FIG. 8 is a normalized assembly power distribution plot for a gas cooled micro-reactor zero burn-up core at control rod withdrawal.
Fig. 9 to 11 are graphs showing the temperature reactivity coefficient change of the gas-cooled micro-reactor at different burnup points and different temperatures, wherein the temperature reactivity coefficients include a fuel temperature coefficient, a core graphite temperature coefficient and a reflector graphite temperature coefficient.
In the above drawings: 1. a fuel assembly; 2. a control rod assembly; 3. a side reflective layer; 4. a control rod bore; 5. a fuel pellet; 6. a coolant flow passage; 7. a poison rod; 8. a pressure pipe; 9. an inner tube; 10. a control rod; 11. a control rod cladding.
Detailed Description
Embodiments of the invention are described below with reference to the accompanying drawings:
as shown in fig. 1 and 2, the present invention provides a modular pressure tube gas-cooled micro-reactor core including a fuel assembly 1, a reflective layer, and control rod assemblies 2. The reflecting layer covers the fuel assembly 1 and the control rod assembly 2 completely, and specifically comprises an upper reflecting layer, a lower reflecting layer and a side reflecting layer 3.
As shown in fig. 3, the fuel assemblies 1 are placed in the pressure tubes 8 such that the pressure tubes 8 serve as the pressure-containing boundary of the core, and the reflector layer and control rod assemblies 2 are installed outside the pressure tubes 8. The fuel assembly 1 comprises graphite blocks and fuel rods; the fuel rods are arranged in fuel rod channels of graphite blocks and form coolant flow channels 6 between the fuel rods and the graphite blocks; the fuel rod is annular in cross section such that a coolant flow passage is formed in the center of the fuel rod. The coolant flows in from the coolant flow channel 6 between the pressure pipe 8 and the inner pipe 9, joins outside the top reflecting layer, and flows out from the coolant flow channels inside and outside the fuel pellet 5 of the fuel cell.
The fuel rod comprises a plurality of fuel pellets 5 stacked in the axial direction; the fuel pellets 5 are formed by dispersing fuel particles in a silicon carbide matrix. The fuel particles comprise a fuel core and a four-layer cladding structure cladding the fuel core; the fuel core is uranium dioxide, and the cladding structure is high-temperature ceramic.
The fuel adopted by the invention is ceramic fuel particles, which can effectively prevent fission products from releasing and avoid the fuel from being corroded; the coolant used is single-phase inert gas helium; the graphite is a neutron moderator, a reactor core structure material and a reflecting layer material, and has the advantages of large heat capacity, high temperature resistance, high thermal conductivity, high moderation ratio, small thermal neutron absorption cross section and the like. Meanwhile, the safety or the economy of the reactor is further improved by using the annular fuel element.
Each pressure tube 8 has a fuel assembly 1 disposed therein and a jacket of graphite (i.e., a jacket of moderator material) disposed outside the pressure tube 8.
The pressure tube type assembly design in the invention ensures that the pressure-bearing boundary of the reactor core is the pressure tube 8 of the fuel assembly 1, and the reflecting layer and the control rod component are not in the pressure boundary, thereby improving the convenience of dismounting and transporting the reflecting layer and the control rod component. Meanwhile, the temperature of the core outside the pressure pipe 8 is lower, and the requirement of the control rod component on high temperature resistance is lowered. It is also contemplated that the pressure tube 8 outer core graphite and reflector graphite could be replaced with a moderator material that has better moderating properties but lower operating temperatures, such as beryllium oxide, zirconium hydride, etc., to further reduce the core size.
When the modular pressure tube type gas-cooled micro-reactor core adopts small pressure tube type fuel assemblies, as shown in figure 1, the fuel assemblies 1, the pressure tubes 8 and the moderator jacket layer together form a fuel assembly unit; the control rods are disposed in control rod passages of the control rod assembly 2; the control rod assemblies 2 are arranged adjacent to the fuel assembly unit. In FIG. 1, each pressure tube fuel assembly unit is adjacent to at least one control rod assembly 2.
When the modular pressure tube gas cooled micro-reactor core of the invention employs large pressure tube fuel assemblies, as shown in fig. 2-4, the control rods are disposed in the control rod channels of the moderator material jacket such that the control rods and fuel assemblies are formed as a single unit. In this embodiment, the pressure tubes are in groups of 7, with 6 peripheral pressure tubes arranged around 1 central pressure tube; and a control rod hole passage 4 is arranged on the graphite sleeve layer of the pressure pipe 8. The cross section of the graphite jacket layer is in a regular hexagon shape, each graphite jacket layer is provided with 3 control rod pore passages 4, and the control rod pore passages 4 are distributed near three vertexes of the hexagonal cross section of the graphite jacket layer at intervals.
The fuel assemblies 1 in the pressure pipes 8 are arranged in a core in a radial 2-divided area (a central area and a peripheral area) and an axial 6-divided area (namely, 6 layers of fuel assemblies 1 are stacked in each pressure pipe 8), the whole stack has 42 fuel blocks, and the size, the structure and the like of the fuel blocks are basically the same. Wherein the fuel assembly 1, located in the central region of the core, has 6 burnable poison rods arranged in the edge positions thereof. The axial height of the whole core is 2.7m, and the radial diameter is 2.6 m.
The control rods are arranged in 1 group in the central fuel assembly 1 and 3 groups in the peripheral fuel assemblies 1, as shown in fig. 5. The control rod group located in the center of the core has 3 rod control rods, and the other 3 groups of control rods located in the 6 fuel assembly zones on the periphery have 6 rod control rods.
As shown in fig. 5, the control rods in the control rod bore 4 of each group of pressure tubes 8 are grouped by distance from the central axis of the central pressure tube into a zeroth control rod group (CR0), a first control rod group (CR1), a second control rod group (CR2) and a third control rod group (CR 3). The zeroth control rod group is 1 group of control rods positioned in the center of the reactor core, and 3 rod-shaped control rods are arranged; the first control rod group to the third control rod group are positioned around the pressure pipe at the periphery of the reactor core, and each group is provided with 6 rod-shaped control rods which are distributed in concentric circles and distributed from near to far according to the distance from the center of the reactor core.
The zeroth control rod group and the first control rod group are used as shutdown rod groups and are used for emergency shutdown and cold shutdown of the reactor core; the second control rod group and the third control rod group are used as a starting rod and an adjusting rod and are used for compensating reactivity change, thermal shutdown and the like caused by temperature change, xenon-samarium toxicity, fuel consumption and the like.
As shown in FIG. 6, the control rods 10 of the control rod assembly are externally wrapped with a control rod cladding 11.
In order to analyze the physical characteristics of the reactor core of the modularized pressure tube type gas-cooled micro-reactor, the invention utilizes a general Monte Carlo program to perform modeling calculation analysis on the gas-cooled micro-reactor with the assumed reactor core temperature of 1200K.
The result of the calculation of the burnup characteristics of the gas-cooled micro-reactor is shown in fig. 7, and the core life is about 650EFPD at 5MW thermal power, which satisfies the design target of 1.5 years life. The arrangement of the burnable poison not only effectively reduces the residual reactivity of the reactor core, but also does not cause reactivity penalty and does not influence the life of the reactor core.
The core power distribution of the air-cooled micro-reactor is shown in fig. 8, which is a module power distribution normalized based on the average power when the zero-burn, control rod is completely withdrawn from the core. In the radial direction, the power distribution is relatively uniform, and the radial power peak factor is about 1.21; in the axial direction, the power distribution is distributed in a cosine function mode, and the axial power peak factor is 1.21; the full stack assembly power factor is at most 1.46 and at least 0.71. Of course, if the fuel enrichment is partitioned according to the position of the fuel assembly, the core power distribution can be further optimized.
The results of calculating the temperature reactivity coefficient of the gas-cooled micro-reactor are shown in fig. 9 to 11. Wherein, FIG. 9 shows the temperature coefficients of the fuel at the beginning of life (0EFPD) and at the end of life (400EFPD) at different temperatures, which are between-2.2 pcm/K and-4.5 pcm/K; FIG. 10 is a graph of core graphite temperature coefficients at the beginning of life (0EFPD) and at the end of life (400EFPD) at different temperatures, with values between-2.8 pcm/K and-3.7 pcm/K; FIG. 11 shows the graphite temperature coefficients of the reflective layer at the beginning of life (0EFPD) and at the end of life (400EFPD), which are small positive values between 0.4 and 1.3 pcm/K. Because the reactor core has better cooling performance and heat conduction performance, the temperature difference between the fuel and the reactor core graphite is very small, the temperature change is almost synchronous, and the total temperature reactivity coefficient of the reactor core can be approximately regarded as the sum of the fuel temperature coefficient, the reactor core graphite temperature coefficient and the temperature coefficient of the reflection layer graphite, and the value of the total temperature reactivity coefficient of the reactor core is between-4.3 pcm/K and-6.6 pcm/K.
The inherent safety of gas cooled micro-reactors is physically manifested primarily in core operation and shutdown. (1) The emergency reactor core shutdown and the cold reactor core shutdown depend on the reactor core shutdown rods, and the reactor core shutdown rods can at least provide a reactor shutdown depth of-4636 pcm and completely meet the reactor shutdown depth requirement of-1000 pcm when the reactor core temperature is 300K during the cold reactor shutdown and the stick value uncertainty is 10% (namely, the multiplier factor is 0.9) and the positive response uncertainty caused by temperature reduction is 10% (namely, the multiplier factor is 1.1) under the consideration of the stick clamping principle and the stick value uncertainty. (2) The hot shutdown of the reactor core depends on the reactor core starting rod and the regulating rod, and the reactor core temperature is 700K when the reactor core is in the hot shutdown, and the reactor core starting rod and the regulating rod can at least provide the shutdown depth of-3765 pcm and completely meet the shutdown depth requirement of the hot shutdown of-1000 pcm when the stick clamping principle, the stick value uncertainty of 10 percent (namely, the multiplier factor of 0.9) and the positive response uncertainty caused by temperature reduction of 10 percent (namely, the multiplier factor of 1.1) are considered. (3) The maximum inherent safety of the air-cooled micro-reactor is realized under the accident condition without any emergency measures, and the reactor core is only stopped by means of temperature negative feedback. Assuming that all control rods are completely ejected, the maximum k of the reactor core is within the service lifeeffThe remaining reactivity was +2326pcm, 1.023528. The total temperature reactivity coefficient of the reactor core is between 4.3pcm/K and 6.6 pcm/K. Assuming an overall temperature coefficient of-4.3 pcm/K, the reactor shutdown due to the negative reactivity introduced by the temperature rise occurred when the temperature rose to 1740K, while the core temperature limit of 1600 ℃ (1873K) still has a large temperature rise margin. Therefore, the modularized pressure tube type gas-cooled micro-reactor can realize automatic shutdown by only depending on temperature negative feedback without any emergency measures even under accident conditions, and physically excludes the possibility of core melting and radioactive substance release.
The design life of the modular pressure tube type gas-cooled micro-reactor core provided by the embodiment is 1.5 years, and the design power is 5 MW; in the service life, when the control rod is pulled out, the radial power peak factor is about 1.21, the axial power distribution is in a cosine function form, and the axial power peak factor is about 1.21; the reactor core control rods can realize cold shutdown and hot shutdown respectively and are provided with two independent shutdown rod groups; the reactor core has strong temperature negative feedback, the temperature negative reactivity coefficient at least reaches more than minus 4pcm/K, and the large temperature rise margin ensures that the reactor core can be automatically shut down only by the temperature negative feedback under the accident condition without any emergency measures even if the control rod is completely popped up. The modular pressure tube gas-cooled micro-reactor core design has good physical properties of the core and excellent intrinsic safety.
The design of different power and different service lives of the reactor can be realized by reasonably designing the fuel of the reactor core, adjusting the size of the reactor core, the fuel enrichment degree and other parameters; the core power distribution can be optimized through the partition arrangement of the enrichment degrees of the fuel assemblies at different positions; the reactivity can be effectively controlled by adjusting the arrangement of the burnable poison and the control rod; the core size can be further reduced by reasonable selection of moderator materials outside the pressure pipe. The modular pressure tube type gas-cooled micro-reactor core design scheme has excellent design flexibility and environmental applicability.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (7)
1. A modularized pressure pipe type gas-cooled micro-reactor core is characterized by comprising a fuel assembly, a reflecting layer and control rods; the fuel assemblies are placed within a pressure tube such that the pressure tube serves as a pressure containment boundary for a core, the reflector layer and control rods being mounted outside the pressure tube.
2. The modular pressure tube gas-cooled micro-stack core of claim 1, wherein the fuel assemblies comprise graphite blocks, fuel rods, burnable poison rods, and coolant flow channels; the fuel rods are arranged in the fuel rod channels of the graphite blocks, and the burnable poison rods are arranged in the burnable poison channels of the graphite blocks; the coolant flow channel is one or more of an independent coolant orifice channel provided on the graphite block, a coolant flow channel formed by a gap between the fuel rod and the graphite block, and a coolant flow channel centrally formed when the fuel rod is annular in cross section.
3. The modular pressure tube gas-cooled micro-stack core of claim 2, wherein the fuel rod comprises a plurality of fuel pellets stacked in an axial direction; the fuel pellet is formed by dispersing fuel particles in a matrix.
4. The modular pressure tube gas-cooled micro-stack core of claim 3, wherein the fuel particles comprise a fuel core and a cladding structure that wraps around the fuel core.
5. The modular pressure tube gas-cooled micro-stack core as claimed in any one of claims 1 to 4, further comprising an inner tube disposed within the pressure tube; the fuel assembly is disposed in the inner tube; the coolant flows in from the coolant flow channel between the pressure tube and the inner tube, joins outside the top or bottom reflector layer, and then flows out from the coolant flow channel in the fuel assembly.
6. The modular pressure tube gas cooled micro-stack core of claim 5, wherein a moderator material jacket is disposed outside the pressure tube, the fuel assemblies, the pressure tubes and the moderator material jacket together forming a fuel assembly unit; the control rods are disposed in control rod passages of a separate control rod assembly; the control rod assembly is disposed adjacent to the fuel assembly unit.
7. The modular pressure tube gas cooled micro-reactor core as claimed in claim 5, wherein a moderator material jacket is disposed outside the pressure tube; the control rods are disposed in the control rod passageways of the moderator material jacket such that the control rods and the fuel assembly are formed as a single unit.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110332498.1A CN113270205B (en) | 2021-03-29 | 2021-03-29 | Modularized pressure pipe type gas-cooled micro-reactor core |
| PCT/CN2021/142915 WO2022206072A1 (en) | 2021-03-29 | 2021-12-30 | Gas-cooled micro-reactor core and gas-cooled micro-reactor |
| CA3212783A CA3212783A1 (en) | 2021-03-29 | 2021-12-30 | Gas-cooled micro-reactor core and gas-cooled micro-reactor |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115101221A (en) * | 2022-08-05 | 2022-09-23 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
| WO2022206072A1 (en) * | 2021-03-29 | 2022-10-06 | 中国核电工程有限公司 | Gas-cooled micro-reactor core and gas-cooled micro-reactor |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1236331A (en) * | 1968-02-09 | 1971-06-23 | Hitachi Ltd | Pressure tube type fuel assembly for nuclear reactor |
| CN103137221A (en) * | 2013-01-15 | 2013-06-05 | 西安交通大学 | Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product |
| CN103778972A (en) * | 2014-02-24 | 2014-05-07 | 中国科学院合肥物质科学研究院 | Control rod assembly comprising axial partition control rod and heavy metal absorber rod |
| CN109801723A (en) * | 2019-01-29 | 2019-05-24 | 哈尔滨工程大学 | A kind of liquid fuel heat pipe reactor |
| CN110634580A (en) * | 2019-09-26 | 2019-12-31 | 哈尔滨工程大学 | Heat pipe type deep sea application nuclear reactor system |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3016402A1 (en) * | 1980-04-29 | 1981-11-05 | GHT Gesellschaft für Hochtemperaturreaktor-Technik mbH, 5060 Bergisch Gladbach | HIGH-TEMPERATURE REACTOR IN MODULAR DESIGN |
| DE3335452A1 (en) * | 1983-09-30 | 1985-04-18 | Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund | Control and shutdown device for a high temperature reactor |
| CN105405475B (en) * | 2015-10-30 | 2017-04-19 | 西安交通大学 | Long-service-life supercritical carbon dioxide cooled reactor |
| CN106229015B (en) * | 2016-08-24 | 2018-09-11 | 中国核动力研究设计院 | A kind of high-temperature molten salt pressure pipe and pipe tube type graphite high-temperature molten salt reactor |
| CN106683720B (en) * | 2017-01-13 | 2018-01-30 | 中国核动力研究设计院 | A kind of shell-and-tube lead-containing alloy cooled reactor |
| CN110232979B (en) * | 2019-06-13 | 2020-09-01 | 西安交通大学 | Open grid type gas-cooled space nuclear reactor core |
| CN113270205B (en) * | 2021-03-29 | 2023-12-22 | 中国核电工程有限公司 | Modularized pressure pipe type gas-cooled micro-reactor core |
-
2021
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- 2021-12-30 WO PCT/CN2021/142915 patent/WO2022206072A1/en active Application Filing
- 2021-12-30 CA CA3212783A patent/CA3212783A1/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1236331A (en) * | 1968-02-09 | 1971-06-23 | Hitachi Ltd | Pressure tube type fuel assembly for nuclear reactor |
| CN103137221A (en) * | 2013-01-15 | 2013-06-05 | 西安交通大学 | Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product |
| CN103778972A (en) * | 2014-02-24 | 2014-05-07 | 中国科学院合肥物质科学研究院 | Control rod assembly comprising axial partition control rod and heavy metal absorber rod |
| CN109801723A (en) * | 2019-01-29 | 2019-05-24 | 哈尔滨工程大学 | A kind of liquid fuel heat pipe reactor |
| CN110634580A (en) * | 2019-09-26 | 2019-12-31 | 哈尔滨工程大学 | Heat pipe type deep sea application nuclear reactor system |
Non-Patent Citations (1)
| Title |
|---|
| 董建华等: "气冷微堆堆芯CFD模型基准研究", 《核工程研究与设计》, pages 29 - 38 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2022206072A1 (en) * | 2021-03-29 | 2022-10-06 | 中国核电工程有限公司 | Gas-cooled micro-reactor core and gas-cooled micro-reactor |
| CN115101221A (en) * | 2022-08-05 | 2022-09-23 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
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| CN113270205B (en) | 2023-12-22 |
| CA3212783A1 (en) | 2022-10-06 |
| WO2022206072A1 (en) | 2022-10-06 |
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