CN115223733A - Full ceramic cladding fuel element and small direct circulation reactor core - Google Patents
Full ceramic cladding fuel element and small direct circulation reactor core Download PDFInfo
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- CN115223733A CN115223733A CN202210847027.9A CN202210847027A CN115223733A CN 115223733 A CN115223733 A CN 115223733A CN 202210847027 A CN202210847027 A CN 202210847027A CN 115223733 A CN115223733 A CN 115223733A
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- 239000000446 fuel Substances 0.000 title claims abstract description 121
- 238000005253 cladding Methods 0.000 title claims abstract description 12
- 239000000919 ceramic Substances 0.000 title claims description 13
- 239000008188 pellet Substances 0.000 claims abstract description 21
- 239000002826 coolant Substances 0.000 claims abstract description 13
- 239000012071 phase Substances 0.000 claims description 12
- 239000000463 material Substances 0.000 claims description 11
- 239000011159 matrix material Substances 0.000 claims description 5
- 239000002574 poison Substances 0.000 claims description 4
- 231100000614 poison Toxicity 0.000 claims description 4
- 230000004323 axial length Effects 0.000 claims description 3
- 239000011248 coating agent Substances 0.000 claims description 3
- 238000000576 coating method Methods 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 239000007791 liquid phase Substances 0.000 claims description 2
- 230000007704 transition Effects 0.000 claims description 2
- 239000012808 vapor phase Substances 0.000 claims description 2
- 239000011162 core material Substances 0.000 abstract description 58
- 238000013461 design Methods 0.000 abstract description 8
- 230000008859 change Effects 0.000 abstract description 5
- 230000002285 radioactive effect Effects 0.000 abstract description 4
- 230000011218 segmentation Effects 0.000 abstract description 2
- 238000005524 ceramic coating Methods 0.000 abstract 1
- 239000000470 constituent Substances 0.000 description 14
- 230000008901 benefit Effects 0.000 description 3
- 230000014509 gene expression Effects 0.000 description 3
- 239000002245 particle Substances 0.000 description 3
- 241000013033 Triso Species 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000006870 function Effects 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000002296 pyrolytic carbon Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 231100000331 toxic Toxicity 0.000 description 2
- 230000002588 toxic effect Effects 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
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
- G21C3/02—Fuel elements
-
- 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
- G21C3/58—Solid reactor fuel Pellets made of fissile material
-
- 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 full ceramic coating fuel element and a small direct circulation reactor core, wherein the fuel element is of a single rod structure and comprises FCM fuel pellets and cladding; the fuel core in the FCM fuel pellet is made of high-density fuel. The fuel element is also arranged in an axial segmentation mode according to the phase change of the coolant, the related structural design of a fuel assembly is cancelled, the fuel core material adopts high-density fuel, and the fuel element is axially segmented according to the phase change of the coolant, so that the neutron economy of the reactor core is effectively improved, the safety of the reactor core is ensured, and the release of radioactive products is reduced.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor design, and particularly relates to a full-ceramic coated fuel element and a small direct circulation reactor core.
Background
Existing "UO 2 The traditional fuel system of the pellet-Zr cladding gradually exposes some defects along with the development of the core design of a reactor and the accumulation of the running experience of the running time of a global reactor, and an accident-resistant fuel (ATF) concept is developed in response, which aims to improve the reliability and the safety characteristic of the fuel, reduce the failure probability and the hydrogen production of the fuel under the accident working condition and simultaneously keep the good running characteristic under the normal running working condition. Among the currently available forms of ATF fuel, one form of fuel that accounts for high temperature gas cooled reactors: fully ceramic coated Fuels (FCMs) have entered the public's field of view with their excellent radioactive product containment and safety. The fuel cell is formed by dispersing TRISO particles in a SiC matrix, wherein the TRISO particles are formed by a fuel core, a buffer layer, an inner pyrolytic carbon layer, a SiC layer and an outer pyrolytic carbon layer. The FCM fuel has good safety and extremely infusibility, can effectively prevent radioactive products from being released, has little performance degradation in the irradiation process, can be effectively adapted to a direct circulating water-cooled reactor, and lays a foundation for the ultra-safety of the direct circulating reactor.
Meanwhile, in order to meet the increasingly diversified power requirements of the current power demand market, a novel reactor concept, namely a Small Modular Reactor (SMR), is proposed in the nuclear industry, and has the greatest characteristics of integration, modularization, high safety performance and multiple purposes. The reactor has low power and small volume, can be processed and manufactured into functional modules in a production factory in advance, can be quickly installed on site, and can adjust the number of the power generation modules according to requirements to adapt to target power output, so that the reactor has high flexibility and adaptability.
Therefore, under the urgent need of safety and flexibility in nuclear power applications, there is a need to develop an FCM device suitable for a small direct cycle reactor.
Disclosure of Invention
The invention provides an all-ceramic cladding fuel element suitable for a high-safety small direct circulation reactor core. The fuel element makes the small direct circulation reactor have long operation life, high safety and high flexibility, and the direct circulation simplifies the loop and system equipment and improves the economy of the reactor.
The invention is realized by the following technical scheme:
an all-ceramic clad fuel element, said fuel element being a single rod structure comprising FCM fuel pellets and cladding;
the fuel core in the FCM fuel pellet uses a high density fuel. The fuel element of the invention adopts a single rod as a fuel element unit, cancels the related structural design of the fuel assembly, simplifies the fuel element and the reactor core structure and reduces the cost. The fuel element pellets of the present invention employ FCM fuel to ensure core over-safety. The fuel core in the FCM fuel adopts high-density fuel, and other elements can be doped to improve the performance of the fuel.
As a preferred embodiment, the fuel elements of the present invention are axially segmented in accordance with a small direct cycle reactor core coolant axial phase transition with different fuel enrichment, particulate phase matrix, poison material and poison content at different axial heights.
As a preferred embodiment, the cladding material of the invention uses a FeCrAl, siC or Zr matrix Cr coating.
As a preferred embodiment, the high density fuel of the present invention is UN or UC.
As a preferred embodiment, the fuel core in the FCM fuel pellets of the present invention may also incorporate Pu or Th.
In a preferred embodiment, the fuel element of the present invention is phase-changed into a liquid phase, a two-phase and a vapor phase along the axial direction of the core coolant.
In another aspect, the present invention provides a small direct cycle reactor core carrying the all-ceramic-clad fuel element of the present invention.
In the core, the part of the fuel elements in the core adopts part of long fuel elements;
the partially long fuel element is a fuel element that replaces fuel pellets within the axial length of the fully ceramic coated fuel element steam section with pellets of additional moderator material.
As a preferred embodiment, the core of the invention is arranged in a hexagon, no fuel elements are arranged at six corners, and the axial height of the core in the active area is fully covered by the slowing layer.
As a preferred embodiment, the reactor core adopts direct circulation, and the coolant and the moderator are both light water, so that the reactor core can be operated at full power for a long time without refueling.
The invention has the following advantages and beneficial effects:
the FCM fuel element provided by the invention cancels the related structural design of a fuel assembly, adopts a high-density fuel core material, and carries out axial segmentation according to the phase change of a coolant, thereby effectively improving the neutron economy of a reactor core, ensuring the safety of the reactor core and reducing the release of radioactive products.
The small direct circulation reactor provided by the invention combines the FCM fuel element with the small direct circulation reactor, ensures that the reactor core has super-safety characteristics, can discharge passive heat depending on the design characteristics of the reactor core and the fuel element under the condition of a super-reference accident, and ensures that the reactor core is not melted.
The small direct circulation reactor provided by the invention adopts a hexagonal arrangement, the periphery of the active region is wrapped with the extra slowing layer, and part of fuel elements adopt a 'part of long fuel elements' arrangement form, so that loops are reduced, the economy of the reactor core is effectively improved while the ultra-safety of the reactor core is ensured, the reactor core is smaller, and the flexibility of the reactor core is ensured.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is an axial schematic view of an FCM fuel element according to an embodiment of the present invention.
Fig. 2 is a radial schematic view of an FCM fuel element according to an embodiment of the present invention.
FIG. 3 is an axial sectioned diagrammatic view of an FCM fuel element according to an embodiment of the present invention.
FIG. 4 is a schematic view of the axial distribution of a portion of the elongated fuel elements of an embodiment of the present invention.
FIG. 5 is a schematic view of a radial arrangement of a small direct cycle reactor core according to an embodiment of the present invention.
FIG. 6 is a schematic axial layout of a compact direct cycle reactor core according to an embodiment of the present invention.
Reference numbers and corresponding part names in the drawings:
1-pellets, 2-cladding, 3-liquid, 4-two-phase, 5-vapor, 6-extra moderating material pellets, 7-moderating layer, 8-coolant or moderator, 9-FCM fuel element, 10-partial long fuel element.
Detailed Description
Hereinafter, the term "including" or "may include" used in various embodiments of the present invention indicates the presence of the inventive function, operation, or element, and does not limit the addition of one or more functions, operations, or elements. Furthermore, the terms "comprises," "comprising," "has," "having," "includes," "including," "has," "having," "including," "contains," "containing," "involving," or any combination thereof, as used in various embodiments of the present invention, are intended to cover only particular features, integers, steps, operations, elements, components, or combinations of the foregoing, and should not be construed as first excluding the presence of or adding to one or more other features, integers, steps, operations, elements, components, or combinations of the foregoing.
In various embodiments of the invention, the expression "or" at least one of a or/and B "includes any or all combinations of the words listed simultaneously. For example, the expression "a or B" or "at least one of a or/and B" may include a, may include B, or may include both a and B.
Expressions (such as "first", "second", and the like) used in various embodiments of the present invention may modify various constituent elements in various embodiments, but may not limit the respective constituent elements. For example, the above description does not limit the order and/or importance of the elements described. The foregoing description is for the purpose of distinguishing one element from another. For example, the first user device and the second user device indicate different user devices, although both are user devices. For example, a first element could be termed a second element, and, similarly, a second element could be termed a first element, without departing from the scope of various embodiments of the present invention.
It should be noted that: if it is described that one constituent element is "connected" to another constituent element, the first constituent element may be directly connected to the second constituent element, and a third constituent element may be "connected" between the first constituent element and the second constituent element. In contrast, when one constituent element is "directly connected" to another constituent element, it is understood that there is no third constituent element between the first constituent element and the second constituent element.
The terminology used in the various embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the various embodiments of the invention. As used herein, the singular forms are intended to include the plural forms as well, unless the context clearly indicates otherwise. Unless otherwise defined, all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art to which various embodiments of the present invention belong. The terms (such as those defined in commonly used dictionaries) should be interpreted as having a meaning that is consistent with their contextual meaning in the relevant art and will not be interpreted in an idealized or overly formal sense unless expressly so defined herein in various embodiments of the present invention.
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
The present embodiments provide an all ceramic coated fuel element (hereinafter referred to as FCM fuel element) suitable for use in a small direct cycle reactor, which can improve the safety and economy of the core. A fuel element of an embodiment of the present invention is shown in fig. 1-2, which in particular embodiments is axially segmented based on coolant phase change.
The fuel element of this embodiment includes pellets and cladding. The pellets adopt FCM fuel to ensure the ultra-safety of a reactor core and reduce the radiation source item of a direct circulation primary loop; the cladding adopts but not limited FeCrAl, siC or Zr matrix Cr coating to ensure high safety of the fuel element and is suitable for a small direct circulation reactor.
The fuel pellet core material of this example uses high density fuels such as UN, UC, etc. to increase the uranium loading and thus neutron economy. Meanwhile, special elements such as Pu and Th can be doped, the reactivity is controlled at the initial stage, the effect of fuel proliferation is achieved at the later stage, and the performance of the reactor core is further optimized.
The fuel elements of the embodiment are arranged in segments according to the axial phase change of the direct circulation reactor core coolant, and have different fuel enrichment degrees, particle phase matrixes, toxic materials, toxic content and the like at different axial heights, so that better power distribution and reactivity control effects are obtained. Specifically, as shown in fig. 3, the fuel element of the present embodiment can be divided into a liquid section, a two-phase section and a vapor section, and specific fuel element parameters are shown in table 1.
TABLE 1 Fuel element parameters
Example 2
This example presents a small direct cycle reactor core carrying the FCM fuel elements presented in example 1 above. The core of this embodiment uses the FCM fuel elements proposed in embodiment 1, and in the core of this embodiment, part of the fuel elements uses "part of long fuel elements", so called "part of long fuel elements", that is, fuel pellets within the axial length of the steam section of the FCM fuel elements are replaced by extra moderating material pellets (for example, beO moderating material pellets), so as to increase extra moderation of the steam section and improve neutron economy.
As shown in fig. 5-6, 2971 fuel elements are arranged in the core of the present embodiment, the core is arranged in a hexagonal shape, and the fuel elements are not arranged at six corners, so as to increase the aspect ratio and facilitate the radiation heat exchange. The core active area is axially and highly wrapped by the BeO layer in full length so as to reduce neutron leakage and increase neutron economy. The reactor core of the embodiment adopts direct circulation, and the coolant and the moderator are light water, so that the reactor core can run at full power for a long time without changing materials. The key parameters relevant to the physical design of the core in this embodiment are shown in table 2.
TABLE 2 physically designed key parameters of small direct cycle core
The core life of the small direct circulation reactor provided by the embodiment reaches 4000EFPD, and the core has the average enrichment degree of fuel of no more than 9 percent 235 The U utilization rate reaches 53.84%, the average unloading burnup of the reactor core reaches 44800MWd/tU, related parameters of neutron economy are superior to those of most pure rod-controlled power reactors, and loops caused by direct circulation are reduced, so that the economy of the scheme is better. Finally, the ultra-safety verification shows that under the condition of an over-reference accident, the hottest fuel temperature of the reactor core is lower than 1400 ℃, and the thermal decomposition temperature of SiC is lower than 2500 ℃, so that the reactor core can be prevented from melting, and the FCM fuel multiple barriers can contain radioactivity and prevent leakage. Meanwhile, the small direct circulation reactor has super-safety capacity, active equipment investment and operator intervention are not needed under the condition of an over-reference accident, and the reactor core can be guaranteed not to be molten by means of the design characteristics of the reactor core and fuel elements and a passive heat removal system.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. An all-ceramic clad fuel element, wherein the fuel element is a single rod structure comprising FCM fuel pellets and cladding;
the fuel core in the FCM fuel pellet is made of high-density fuel.
2. The all-ceramic-clad fuel element of claim 1, wherein said fuel element is axially segmented according to a mini direct cycle reactor core coolant axial phase transition with different fuel enrichment, particulate phase matrix, poison material and poison content at different axial heights.
3. An all ceramic clad fuel element according to claim 1 wherein said cladding material is a FeCrAl, siC or Zr based Cr coating.
4. An all ceramic coated fuel element according to claim 1 wherein the high density fuel is UN or UC.
5. An all-ceramic coated fuel element according to claim 4, wherein the fuel core of the FCM fuel pellet further incorporates Pu or Th.
6. The all-ceramic-clad fuel element according to any one of claims 1 to 5, wherein the fuel element is phase-changed into a liquid phase section, a two-phase section and a vapor phase section along the axial direction of the core coolant.
7. A small direct cycle reactor core carrying the all-ceramic-clad fuel element of any one of claims 1-5.
8. The core as claimed in claim 7, wherein the partial fuel elements in the core are partial long fuel elements;
the partially long fuel element is a fuel element in which fuel pellets within the axial length of the full ceramic coated fuel element steam segment are replaced with pellets of additional moderator material.
9. A compact direct cycle reactor core according to claim 7 wherein the core is in a hexagonal arrangement with six locations of corners free of fuel elements and an axial height fully enclosing the moderating layer in the active zone.
10. The core as claimed in claim 7, wherein the core is in direct circulation and the coolant and moderator are light water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210847027.9A CN115223733A (en) | 2022-07-07 | 2022-07-07 | Full ceramic cladding fuel element and small direct circulation reactor core |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202210847027.9A CN115223733A (en) | 2022-07-07 | 2022-07-07 | Full ceramic cladding fuel element and small direct circulation reactor core |
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| CN115223733A true CN115223733A (en) | 2022-10-21 |
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| CN202210847027.9A Pending CN115223733A (en) | 2022-07-07 | 2022-07-07 | Full ceramic cladding fuel element and small direct circulation reactor core |
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Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109473183A (en) * | 2018-11-14 | 2019-03-15 | 中国核动力研究设计院 | A kind of ultra-large type pressurized-water reactor nuclear power plant reactor core display |
| CN110867261A (en) * | 2019-11-21 | 2020-03-06 | 中国核动力研究设计院 | Multi-type pellet mixed loading metal cooling reactor and management method |
| CN113674876A (en) * | 2021-07-20 | 2021-11-19 | 中国核动力研究设计院 | Reactor core arrangement and component arrangement of metal-cooled reactor containing solid moderator |
| CN114038583A (en) * | 2021-11-17 | 2022-02-11 | 中国核动力研究设计院 | Full ceramic fuel rod |
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- 2022-07-07 CN CN202210847027.9A patent/CN115223733A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109473183A (en) * | 2018-11-14 | 2019-03-15 | 中国核动力研究设计院 | A kind of ultra-large type pressurized-water reactor nuclear power plant reactor core display |
| CN110867261A (en) * | 2019-11-21 | 2020-03-06 | 中国核动力研究设计院 | Multi-type pellet mixed loading metal cooling reactor and management method |
| CN113674876A (en) * | 2021-07-20 | 2021-11-19 | 中国核动力研究设计院 | Reactor core arrangement and component arrangement of metal-cooled reactor containing solid moderator |
| CN114038583A (en) * | 2021-11-17 | 2022-02-11 | 中国核动力研究设计院 | Full ceramic fuel rod |
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