CN115472316A - Fuel rod, rod bundle assembly and material pouring method - Google Patents
Fuel rod, rod bundle assembly and material pouring method Download PDFInfo
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- CN115472316A CN115472316A CN202211127253.6A CN202211127253A CN115472316A CN 115472316 A CN115472316 A CN 115472316A CN 202211127253 A CN202211127253 A CN 202211127253A CN 115472316 A CN115472316 A CN 115472316A
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- 239000000446 fuel Substances 0.000 title claims abstract description 112
- 238000000034 method Methods 0.000 title claims abstract description 12
- 239000000463 material Substances 0.000 title abstract description 12
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 claims abstract description 160
- 238000004519 manufacturing process Methods 0.000 claims abstract description 54
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 51
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 22
- 238000005253 cladding Methods 0.000 claims abstract description 19
- 238000013461 design Methods 0.000 claims abstract description 9
- 238000007599 discharging Methods 0.000 claims description 2
- 238000012423 maintenance Methods 0.000 abstract description 8
- 230000000694 effects Effects 0.000 abstract description 5
- 238000001816 cooling Methods 0.000 abstract description 4
- 238000006243 chemical reaction Methods 0.000 abstract description 2
- 238000011160 research Methods 0.000 description 7
- 238000009826 distribution Methods 0.000 description 6
- 230000009257 reactivity Effects 0.000 description 6
- 230000000712 assembly Effects 0.000 description 5
- 238000000429 assembly Methods 0.000 description 5
- 230000017525 heat dissipation Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010924 continuous production Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000002059 diagnostic imaging Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000008676 import Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052750 molybdenum Inorganic materials 0.000 description 1
- 239000011733 molybdenum Substances 0.000 description 1
- 239000011824 nuclear material Substances 0.000 description 1
- OFPXSFXSNFPTHF-UHFFFAOYSA-N oxaprozin Chemical compound O1C(CCC(=O)O)=NC(C=2C=CC=CC=2)=C1C1=CC=CC=C1 OFPXSFXSNFPTHF-UHFFFAOYSA-N 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
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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
- G21C3/02—Fuel elements
- G21C3/28—Fuel elements with fissile or breeder material in solid form within a non-active casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/001—Recovery of specific isotopes from irradiated targets
- G21G2001/0036—Molybdenum
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a fuel rod, a rod bundle assembly and a material pouring method, wherein the fuel rod comprises a cladding layer, an enriched fuel layer is sleeved in the cladding layer, and a spent fuel layer is sleeved in the enriched fuel layer; the nested mode that the inner layer is the spent fuel layer and the outer layer is the enriched fuel layer is adopted, because the enriched fuel layer has violent reaction and more released heat, but is close to the cladding layer (relative to the spent fuel layer), the radiating effect is better under the condition of reaching the same yield, and the spent fuel layer of the inner layer produces less heat, so the production is realized 99 The Mo fuel rod can still keep lower central temperature than the standard heavy water reactor fuel rod under the same cooling condition, thereby reducing the influence on the core characteristics and further reducing the weightWater reactor design, safety demonstration, operation maintenance and the like.
Description
Technical Field
The invention relates to the technical field of civil nuclear materials, in particular to a fuel rod, a rod bundle assembly and a material pouring method.
Background
Radionuclides 99 Half-life of Mo is 65.9 hours, its decay products 99m Tc is the most widespread and used isotope in the world for medical imaging, and is internationally recognized as the most efficient and irreplaceable isotope 99 The best mode for producing Mo is to extract Mo from fission products of reactor, and is the most interesting medical isotope ( 99m Parent of Tc).
The research heap now bears the world 99 The main production task of Mo, but the research resources of China are in short supply, and the Mo is currently used in medical treatment of China 99 Mo is completely dependent on foreign import. Dozens of commercial reactors exist in China, the refueling period of a commercial pressurized water reactor is about 12-18 months,the frequency of nuclear fuel discharge limits the sustainability of short half-life isotope extraction and makes it difficult to support stable and reliable 99 Mo production; the commercial heavy water reactor has the characteristic of loading and unloading materials on line without stopping the reactor, and is more suitable for producing short half-life 99 An isotope of Mo.
Affected by factors such as decommissioning of research reactor, uncertainty of operation and the like, the method is carried out in a commercial reactor heavy water reactor 99 The research of Mo production is gradually paid attention to, the theoretical feasibility is preliminarily proved, and the existing production 99 The construction of a commercial heavy water reactor cluster assembly of Mo clusters is shown in FIG. 1, however, the product of these studies 99 The Mo rod bundle basically refers to standard heavy water reactor fuel rods (as shown in figure 2) in a research reactor, and after the Mo rod bundle is put into the reactor, the characteristics of a reactor core are greatly influenced, so that the costs of heavy water reactor design, safety demonstration, operation maintenance and the like are increased.
Disclosure of Invention
The invention aims to provide a fuel rod, a rod bundle assembly and a material pouring method, aiming at solving the problem that the existing standard heavy water reactor improves the fuel enrichment degree to produce 99 The Mo fuel rod can greatly affect the characteristics of a reactor core after being put into the reactor, thereby increasing the cost of heavy water reactor design, safety demonstration, operation maintenance and the like.
In one aspect, the invention provides a method of producing 99 The Mo fuel rod comprises a cladding layer, wherein an enriched fuel layer is sleeved in the cladding layer, and a spent fuel layer is sleeved in the enriched fuel layer.
The invention has the beneficial effects that: production by adopting nesting mode with spent fuel layer as inner layer and enriched fuel layer as outer layer 99 The Mo fuel rod, nuclear reactivity, integral fuel rod power distribution and the like are basically consistent with the standard heavy water reactor fuel rod, and simultaneously, the enriched fuel layer has violent reaction and much released heat, but is close to the cladding layer (relative to the spent fuel layer), so the heat dissipation effect is better under the condition of reaching the same yield, and the spent fuel layer of the inner layer produces less heat, so the heat dissipation effect is better 99 The Mo fuel rod can still keep lower center temperature than the standard heavy water reactor fuel rod under the same cooling condition. Therefore, the influence on the core characteristics can be reduced, and the design and safety of the heavy water reactor are reducedAnd (5) overall demonstration, operation and maintenance and other costs.
In one possible implementation, the fuel-rich bed pair 235 The enrichment degree of U is 3-19.5%.
In another aspect, the present invention provides a heavy water reactor production 99 A cluster of Mo rods comprising a housing in which at least one of the above-mentioned processes is arranged 99 Mo fuel rod and at least one standard heavy water reactor fuel rod, the sum of the number of the Mo fuel rod and the at least one standard heavy water reactor fuel rod is 37, namely, based on the existing standard heavy water reactor fuel assembly, part of the standard heavy water reactor fuel rods are used for producing 99 Mo fuel rod replacement, which can reduce the cost of the improvement. In one possible implementation, the number of standard heavy water reactor fuel rods replaced is 1 to 36.
The invention has the beneficial effects that: by the above production 99 Mo fuel rods and standard heavy water reactor fuel rods are used in combination to meet different requirements 99 Mo yield requirement.
In one possible implementation, the above production 99 The Mo fuel rods and the standard heavy water reactor fuel rods are arranged in at least one ring.
In one possible implementation, when the number of rings is greater than 2, the centers of the plurality of rings coincide.
In a possible implementation manner, when the number of the rings is greater than 2, the centers of the circles of the plurality of rings are standard heavy water reactor fuel rods, so that the temperature of the reactor core is in a reasonable range, and the heat accumulation is avoided.
Finally, the invention also provides a method for producing the same 99 Production of Mo fuel rod 99 The Mo pouring method is to load 1 standard heavy water reactor fuel rod per 8.9 channels on average and discharge 1 production rod per 4.6 days on average 99 A Mo fuel rod.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention and do not limit the invention. In the drawings:
FIG. 1 is a cross-sectional view of a prior art standard commercial heavy water reactor fuel rod;
FIG. 2 is a cross-sectional view of a prior art standard commercial heavy water reactor fuel bundle assembly;
FIG. 3 production in example 99 A cross-sectional view of a Mo fuel rod;
FIG. 4 heavy Water heap production in example 99 A cross-sectional view of a bundle assembly of Mo;
reference numbers and corresponding part names in the drawings:
1-clad layer, 2-standard heavy-water reactor fuel layer, 3-enriched fuel layer, 4-spent fuel layer, 5-standard heavy-water reactor fuel rod, 6-production 99 A Mo fuel rod.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects to be solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
It will be understood that when an element is referred to as being "nested" within or outside of another element, it can have a center point that is coincident with or offset from a center point of the other element. When an element is referred to as being "disposed" or "provided with" another element, it can be directly connected or indirectly connected to the other element.
In the description of the present invention, it is to be understood that the terms "upper", "lower", "front", "rear", "left", "right", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present invention.
In the description of the present invention, it should be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, e.g., as meaning either a fixed connection, a removable connection, or an integral connection; can be mechanically or electrically connected; either directly or indirectly through intervening media, either internally or in any other relationship. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the description of the invention, the end radially closer to the center is inner and the end radially further from the center is outer.
Since the current research heap bears the whole world 99 The main production task of Mo, but the research resources of China are in short supply, and the Mo is currently used in medical treatment of China 99 Mo is completely imported from foreign countries. Dozens of commercial reactors exist in China, the refueling period of a commercial pressurized water reactor is about 12-18 months, so that the mode is known as gap production, the production time period in the gap production is too long, the reactor discharge frequency of nuclear fuel limits the sustainability of extracting isotopes with short half-life periods, and the stable and reliable support is difficult 99 And (4) Mo production.
The inventors of the present invention studied the continuous production using commercial heavy water reactor cluster assemblies 99 In the process of Mo, when the fuel enrichment degree of the standard heavy water reactor fuel rod is improved, great influence is caused on the characteristics of the reactor core, for example, the temperature of the reactor core is increased too much, and then the costs of heavy water reactor design, safety demonstration, operation maintenance and the like are increased.
Fig. 1 is a cross-sectional view of a standard commercial heavy water reactor fuel rod, wherein a standard heavy water reactor fuel rod 5 comprises a cladding layer 1, and a standard heavy water reactor fuel layer 2 is sleeved in the cladding layer 1. To produce for 99 Mo, lifting the fuel layer 2 of a standard heavy water reactor fuel rod 5, has a large impact on the core characteristics.
Fig. 2 is a cross-sectional view of an existing commercial heavy water reactor bundle assembly, which includes an outer casing, 37 standard heavy water reactor fuel rods 5 are disposed in the casing, one of the 37 standard heavy water reactor fuel rods 5 is a center, the remaining 36 fuel rods are distributed in 3 rings, and 3 ring sleeves are disposed, the centers of the rings are coincident with the center, and the number of the standard heavy water reactor fuel rods 5 on each ring from inside to outside is 6, 12 and 18 in sequence.
In order to solve the above problems, the inventors of the present invention have found that dividing the fuel layer 2 into an inner spent fuel layer and an outer enriched fuel layer, adjusting the thickness ratio of the spent fuel layer and the enriched fuel layer, and ensuring the adjusted spent fuel layer and enriched fuel layer to be used in the fuel cell system 99 The nuclear reactivity, the whole fuel rod power distribution and the like of the fuel rods produced by Mo are basically consistent with those of standard heavy water reactor fuel rods, meanwhile, because the enriched fuel layer is close to the clad layer, the heat transfer is fast, and the heat released by the spent fuel layer is less, the lower central temperature can be kept lower than that of the standard heavy water reactor fuel rods under the same cooling condition, so that the influence on the reactor core characteristics can be reduced, and the costs of heavy water reactor design, safety demonstration, operation maintenance and the like are reduced.
FIG. 3 shows the production in this example 99 Cross-sectional view of a Mo fuel rod. As shown in FIG. 3, this example provides a production 99 A Mo fuel rod. The production 99 The Mo fuel rod comprises a cladding layer 1, wherein an enriched fuel layer 3 is sleeved in the cladding layer 1, and a spent fuel layer 4 is sleeved in the enriched fuel layer 3. The material of the cladding layer 1 can be selected according to the requirement, for example: zirconium alloy, but is not limited thereto. The nuclear reactivity of the fuel-rich layer 3 is much greater than that of the fuel-lean layer 4.
Fuel-rich bed 3 pairs in FIG. 3 235 The enrichment of U may be between 3% and 19.5%, suitably between 8% and 19.5%, more suitably between 15% and 19.5%, of the enriched fuel bed 3 without changing other process parameters 235 When the enrichment of U is varied within the above range, the thicknesses of the fuel layer 3 of the rich zone and the spent fuel layer 4 are varied to maintain the nuclear reactivity in agreement. The fuel of the enriched fuel layer 3 may be selected as desired, for example: enriched uranium fuel, but is not so limited.
As shown in FIG. 3, produced in this example 99 The cladding layer 1 of the Mo fuel rod is dimensionally identical to the cladding layer 1 in fig. 1. The sum of the thickness of the fuel-rich layer 3 and the thickness of the spent fuel layer 4 in fig. 3 should be the same as the thickness of the standard heavy-water reactor fuel layer in fig. 1, and as the thickness of the fuel-rich layer 3 increases or decreases, the thickness of the spent fuel layer 4 decreases or increases, both being negativeAnd (6) correlating. When the kind of fuel in the enriched fuel layer 3 is used for a certain time, it is paired 235 The U-enrichment is inversely related to the thickness of the fuel-rich layer 3, i.e., the greater the enrichment, the smaller the value of the thickness of the fuel-rich layer 3.
The nested mode that the inner layer is a spent fuel layer and the outer layer is an enriched fuel layer is adopted, so that the production can be ensured 99 The nuclear reactivity, the overall fuel rod power distribution and the like of the Mo fuel rod are basically consistent with those of a standard heavy water reactor fuel rod, and simultaneously, because the enriched fuel layer reacts violently and releases more heat, but is close to the cladding layer (relative to the spent fuel layer), the heat dissipation effect is better under the condition of achieving the same yield, and the spent fuel layer of the inner layer produces less heat, so that the production efficiency is higher 99 The Mo fuel rod can still keep lower central temperature than the standard heavy water reactor fuel rod under the same cooling condition, so that the influence on the core characteristics can be reduced, and the costs of heavy water reactor design, safety demonstration, operation maintenance and the like are reduced.
FIG. 4 shows heavy water heap production in this example 99 Cross-sectional view of a Mo fuel bundle assembly. As shown in FIG. 4, the cluster tool includes a housing in which at least one of the above-described articles of manufacture is disposed 99 The number of the Mo fuel rods is 8, 15 or 36, but the Mo fuel rods are not limited to the above. To control core performance, the above production can be used 99 The Mo fuel bundle assembly and the standard heavy water reactor fuel bundle assembly are matched for use, and the arrangement mode of the Mo fuel bundle assembly and the standard heavy water reactor fuel bundle assembly can be arranged in any situation.
Due to the fact that 99 Mo output and production 99 The number and the installation position of Mo fuel rods are related, and the Mo fuel rods are also related to a material pouring mode; therefore, under the condition of fixed quantity and material pouring mode, the production can be adjusted 99 Adjusting the mounting position of Mo fuel rod 99 The yield of Mo; when in production 99 Under the condition that the number and the installation position of Mo fuel rods are fixed, the material pouring mode can be adjusted 99 The yield of Mo; e.g. when producing heavy water piles 99 The Mo rod bundle assembly and the existing commercial heavy water reactor rod bundle assembly have the same general parameters (such as power and total number of the rod bundle assemblies), and the material pouring mode of 8 rod bundle assemblies is adopted to levelEach with 1 molybdenum-producing target bundle per 8.9 passes, and each with 1 production discharged per 4.6 days 99 A Mo fuel rod.
As shown in fig. 4, the above production 99 The fuel rods of Mo and the above-mentioned standard heavy water reactor fuel rods are arranged in at least one ring, for example: 3, but not limited thereto. As an achievable way, when the above-mentioned production is carried out 99 When the Mo fuel rods and the standard heavy water reactor fuel rods are arranged into 2 rings, the circle centers of the rings are overlapped; as one achievable way, the above production 99 When the Mo fuel rod and the standard heavy water reactor fuel rod are arranged into 2 rings, the centers of the rings are superposed and the center of the ring is the standard heavy water reactor fuel rod.
In order to save the reconstruction cost and meet the requirement of heavy water reactor production 99 The fuel rod power distribution within the Mo bundle assembly is substantially identical to the fuel rod power distribution within existing commercial heavy water reactor bundle assemblies; in this embodiment, the production shown in FIG. 3 with the same outer diameter of the cladding layer 1 can be used directly in the existing commercial heavy water reactor bundle assembly as shown in FIG. 1 99 Mo fuel rods partially or completely replace standard heavy water reactor fuel rods, the replacement positions can be any positions, and the replacement quantity is determined according to the replacement quantity 99 Mo yield selected, other parameters remaining unchanged, e.g. inner diameter of the cladding layer 1, production 99 The length of the Mo fuel rod, cladding layer 1, geometry and the like are consistent with the standard heavy water reactor fuel rod.
For example, as shown in fig. 4, 36 standard heavy water reactor fuel rods were replaced with the above-described production fuel rods except that the center-positioned standard heavy water reactor fuel rods were not replaced 99 A Mo fuel rod.
In the present example, the clad layer 1 of the fuel rod was produced according to the thickness and production of the existing standard heavy water reactor 99 Enriched fuel layer 3 pairs of Mo fuel rods 235 The enrichment degree of U is 3-19.5 percent and the thickness of the enriched fuel layer 3 can be calculated by the fuel of the common enriched fuel layer 3 and is generally 0.08-0.58 mm, and the volume ratio of the enriched fuel layer 3 to the spent fuel layer 4 can be adjusted to ensure the heavy water reactor production 99 Nuclear-reactive, heavy-water reactor production of bundle assemblies of Mo 99 Bundle of MoThe performance parameters of the assembly, such as power distribution and the like, are basically consistent with those of the conventional commercial heavy water reactor rod bundle assembly, so that the requirement of a melting limit value is met, the influence of the fuel rods after being put into the reactor on the characteristics of the reactor core can be greatly reduced, and the design, demonstration, operation maintenance and other costs of the heavy water reactor are reduced.
For example, a complete 99 The Mo production is implemented as follows: 1. set-up product 99 Of fuel-rod-enriched fuel layer 3 of Mo 235 The U enrichment degree is 3 percent, the thickness of the enriched fuel layer 3 is 0.58 mm, and the inner radius and the outer radius are 0.55 cm and 0.61 cm respectively. 2. Production as shown in FIG. 4 99 Bundle assembly of Mo, 36 standard heavy water reactor fuel rods are replaced by the standard heavy water reactor fuel rods described in step 1 except that the standard heavy water reactor fuel rods in the center position are not replaced 99 And Mo fuel rods. 3. Production described in step 2 99 Mo rod bundle assembly produced under operating conditions of total power of 905kW, steady flow of coolant to maintain constant temperature of coolant at 310 deg.C 99 The Mo bundle assembly maintains a small difference in nuclear reactivity of around 150pcm over a 20 day run time with the root standard heavy water reactor bundle assembly and produces 99 The enriched fuel layer 3 of the Mo bundle assembly has a temperature less than the temperature of the corresponding position of the standard heavy water reactor bundle and less than the UO 2 The melting temperature limit of the pellets. 4. Loading the CANDU 6 core with the production of step 2 99 Bundle assembly of Mo as produced 99 The Mo bundle assembly and the existing CANDU 6 bundle assembly have the same overall parameters, and the average load of 1 production per 8.9 material pouring channels 99 Bundle assembly of Mo, discharging on average 1 production per 4.6 days 99 Bundle assembly of Mo, which can yield about 2.9mg 99 Mo。
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. Production of 99 The Mo fuel rod comprises a cladding layer and is characterized in that an enriched fuel layer is sleeved in the cladding layer, and a spent fuel layer is sleeved in the enriched fuel layer.
2. The fuel rod of claim 1, wherein the pair of enriched fuel layers 235 The enrichment degree of U is 3-19.5%.
3. The fuel rod of claim 1 wherein the fuel region of the fuel rod is configured to be different from the fuel region of a standard heavy water stack assembly fuel rod, and other design parameters are consistent with the standard assembly fuel rod.
4. Heavy water reactor production 99 Bundle assembly of Mo, comprising a housing, characterized in that at least one fuel rod according to any of claims 1-3 and at least one standard heavy water reactor fuel rod, the sum of the numbers of which is 37, are arranged in the housing.
5. The bundle assembly of claim 4, wherein the fuel rod of any one of claims 1-3 and the standard heavy water reactor fuel rod are arranged in at least one ring.
6. The bundle assembly of claim 5, wherein the centers of the plurality of loops coincide when the number of loops is greater than 2.
7. The bundle assembly of claim 6, wherein a plurality of the rings are centered on a standard heavy water reactor fuel rod when the number of rings is greater than 2.
8. Heavy water reactor production 99 Bundle assembly of Mo, characterized in that at least one standard heavy water reactor fuel rod of a standard heavy water reactor fuel assembly is arranged according to any of claims 1-3And replacing the fuel rod.
9. The bundle assembly of claim 8, wherein the number of standard heavy water reactor fuel rods replaced is 1 to 36.
10. A bundle assembly production based on any one of claims 4-7 or 8 or 9 99 The heavy water heap dumping method of Mo is characterized in that 1 production is loaded on average per 8.9 dumping channels 99 Bundle assembly of Mo, discharging on average 1 production per 4.6 days 99 Bundle assembly of Mo.
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| CN202211127253.6A CN115472316A (en) | 2022-09-16 | 2022-09-16 | Fuel rod, rod bundle assembly and material pouring method |
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