CN115394460A - Control rod absorber core block and control rod - Google Patents
Control rod absorber core block and control rod Download PDFInfo
- Publication number
- CN115394460A CN115394460A CN202210911082.XA CN202210911082A CN115394460A CN 115394460 A CN115394460 A CN 115394460A CN 202210911082 A CN202210911082 A CN 202210911082A CN 115394460 A CN115394460 A CN 115394460A
- Authority
- CN
- China
- Prior art keywords
- zirconium hydride
- control rod
- cylinder
- boron carbide
- zirconium
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000006096 absorbing agent Substances 0.000 title claims abstract description 58
- 229910000568 zirconium hydride Inorganic materials 0.000 claims abstract description 124
- QSGNKXDSTRDWKA-UHFFFAOYSA-N zirconium dihydride Chemical compound [ZrH2] QSGNKXDSTRDWKA-UHFFFAOYSA-N 0.000 claims abstract description 120
- 229910052580 B4C Inorganic materials 0.000 claims abstract description 47
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims abstract description 47
- 239000008188 pellet Substances 0.000 claims description 24
- 238000005253 cladding Methods 0.000 claims description 15
- 239000002994 raw material Substances 0.000 claims description 5
- 239000000463 material Substances 0.000 abstract description 13
- 230000009257 reactivity Effects 0.000 abstract description 8
- 230000002035 prolonged effect Effects 0.000 abstract description 4
- 230000008961 swelling Effects 0.000 abstract description 3
- 230000000903 blocking effect Effects 0.000 abstract description 2
- 238000000034 method Methods 0.000 description 4
- 230000008569 process Effects 0.000 description 4
- 238000010521 absorption reaction Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 229910052692 Dysprosium Inorganic materials 0.000 description 2
- 229910052693 Europium Inorganic materials 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- OGPBJKLSAFTDLK-UHFFFAOYSA-N europium atom Chemical compound [Eu] OGPBJKLSAFTDLK-UHFFFAOYSA-N 0.000 description 2
- 239000012634 fragment Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- 238000005245 sintering Methods 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 229910052715 tantalum Inorganic materials 0.000 description 2
- GUVRBAGPIYLISA-UHFFFAOYSA-N tantalum atom Chemical compound [Ta] GUVRBAGPIYLISA-UHFFFAOYSA-N 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000007731 hot pressing Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
- G21C7/103—Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/24—Selection of substances for use as neutron-absorbing material
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a control rod absorber core block and a control rod, wherein the control rod absorber core block comprises a zirconium hydride cylinder body and at least two boron carbide sub-blocks, wherein the zirconium hydride cylinder body is internally provided with at least two sub-cavities; the boron carbide blocks are respectively filled in the sub-cavities of the zirconium hydride cylinders; within the zirconium hydride column, the height of the boron carbide block extends along the height direction of the zirconium hydride column. The control rod absorber core block is mainly formed by the zirconium hydride cylinder and the boron carbide filled in the zirconium hydride cylinder in a blocking manner, has the advantages of high reactivity value, low irradiation swelling rate and the like, and can replace pure B 4 The absorber core block made of the existing absorber materials such as C and the like is applied to the fast reactor, and meanwhile, the absorber core block also has application potential in the hot reactor, so that the service life of the control rod is prolonged, and the mechanical life of the control rod assembly is prolonged.
Description
Technical Field
The invention relates to the technical field of control rod absorber materials, in particular to a control rod absorber core block and a control rod.
Background
The control rod assembly is an important component for controlling the power level of the reactor, and the power control is realized in the whole operation process mainly by adjusting the position of the control rod assembly in the reactor. The control rod assembly is an important safety assembly of the reactor, and under the accident condition, the control rod assembly quickly falls down by utilizing the gravity of the control rod assembly to realize the emergency shutdown of the whole reactor core and ensure the overall safety.
The control rod assembly is typically comprised of a control rod cluster. The control rod is manufactured by stacking controlled absorber pellets, loading the absorber pellets into a stainless steel cladding, and sealing the stainless steel cladding by using an end plug. The design is particularly important because all of the reactivity control material is contained within the control rod absorber core block.
The neutron energy spectrums of a fast reactor (namely a fast neutron reactor) and a pressurized water reactor are different, and the control material selection is slightly different. At present, fast reactors in the world are basically in the research stage, no mature control rod absorber pellet design form exists, and the used absorber materials are various, wherein boron carbide, tantalum, chromium boride, europium and the like are mainly used; the model is mostly a short cylinder. According to the experimental description, the pellets have a plurality of defects, such as low thermal conductivity of boron, low melting point of tantalum, high radioactive residual of europium and the like, and cannot meet the requirement of fast reactor, and the targeted design on materials and structures is needed to improve the performance of the absorber pellets and ensure the safety of the reactor.
In conclusion, the development of a novel high-performance and high-cost-performance fast reactor control rod absorber core block is of great significance.
Disclosure of Invention
The invention aims to provide an improved control rod absorber core block and a control rod.
The technical scheme adopted by the invention for solving the technical problems is as follows: providing a control rod absorber core block, which comprises a zirconium hydride cylinder with at least two sub-cavities inside, at least two boron carbide sub-blocks; the boron carbide blocks are respectively filled in the sub-cavities of the zirconium hydride cylinders;
within the zirconium hydride column, the height of the boron carbide blocks extends along the height direction of the zirconium hydride column.
Preferably, the zirconium hydride column comprises a zirconium hydride cylinder, a zirconium hydride central column and at least two zirconium hydride connecting walls;
the zirconium hydride central column is arranged in the zirconium hydride cylinder, the zirconium hydride connecting wall is connected between the outer surface of the zirconium hydride central column and the inner surface of the zirconium hydride cylinder, and an annular cavity between the zirconium hydride central column and the zirconium hydride cylinder is divided into at least two sub-cavities;
each boron carbide block is filled in one of the sub-cavities.
Preferably, the height of the zirconium hydride cylinder, the zirconium hydride central column and the zirconium hydride connecting wall is consistent.
Preferably, the ratio of the diameter of the zirconium hydride central column to the outer diameter of the zirconium hydride column is 1:3-1:5.
Preferably, the wall thickness of the zirconium hydride connecting wall is more than or equal to that of the zirconium hydride cylinder.
Preferably, said zirconium hydride cylinder comprises four of said zirconium hydride connecting walls;
the four zirconium hydride connecting walls divide an annular cavity between the zirconium hydride central column and the zirconium hydride cylinder into four sub-cavities.
Preferably, the corners of the boron carbide blocks and the corners in the sub-cavities are chamfered.
Preferably, the boron carbide agglomerated raw material B 4 In the step (C), the step (A), 1 the enrichment degree of 0B is more than or equal to 80 percent.
Preferably, in the raw materials of the zirconium hydride column, the stoichiometric ratio of Zr to H is 1.
The invention also provides a control rod, which comprises a cladding and a plurality of control rod absorber pellets of any one of the above items;
a number of the control rod absorber pellets are stacked within the cladding in an axial direction of the cladding.
The control rod absorber core block is mainly formed by the zirconium hydride cylinder and the boron carbide filled in the zirconium hydride cylinder in a blocking manner, has the advantages of high reactivity value, low irradiation swelling rate and the like, and can replace pure B 4 The absorber core block made of the existing absorber materials such as C and the like is applied to the fast reactor, and meanwhile, the absorber core block also has application potential in the hot reactor, so that the service life of the control rod is prolonged, and the mechanical life of the control rod assembly is prolonged.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is an axial cross-sectional structural view of a control rod absorber core block of an embodiment of the present invention;
FIG. 2 is a schematic radial cross-sectional view of a control rod absorber core block of an embodiment of the present invention;
FIG. 3 shows boron carbide and other absorber materials (Dy) in the present invention 2 TiO 5 、Hf、Ag-In-Cd、Dy 2 O 3 ·HfO 2 ) Versus a graph of relative reactive value of (c).
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
As shown in fig. 1 and 2, the control rod absorber core block according to an embodiment of the present invention includes a zirconium hydride cylinder and at least two boron carbide blocks (i.e., B 4 C blocks) 4.
The zirconium hydride cylinder is a cylinder structure which is hollow inside and provided with at least two cavities, and the boron carbide blocks 4 are respectively filled in the cavities of the zirconium hydride cylinder, namely, each cavity is filled with one boron carbide block 4, so that the zirconium hydride cylinder and the boron carbide blocks 4 form a solid columnar absorber core block.
In the zirconium hydride cylinder, the height of the boron carbide block 4 extends in the height direction of the zirconium hydride cylinder 4, and the heights of the boron carbide block 4 and the zirconium hydride cylinder may be made uniform so that the end face of the zirconium hydride cylinder is flush with the end face of the boron carbide block 4.
The zirconium hydride column further may comprise a zirconium hydride cylinder 1, a zirconium hydride center column 2, and at least two zirconium hydride connecting walls 3.
The zirconium hydride central column 2 is arranged in the zirconium hydride cylinder 1 and extends along the height direction of the zirconium hydride cylinder 1, namely the height direction of the zirconium hydride cylinder 1 is consistent and the height of the zirconium hydride cylinder is also consistent. The zirconium hydride connecting wall 3 is connected between the outer surface of the zirconium hydride central column 2 and the inner surface of the zirconium hydride cylinder 1, and divides an annular cavity between the zirconium hydride central column 2 and the zirconium hydride cylinder 1 into at least two sub-cavities; each boron carbide segment 4 is filled in a chamber.
The zirconium hydride connecting wall 3 is also provided extending in the height direction of the zirconium hydride cylinder 1, and the height thereof coincides with the height of the zirconium hydride cylinder 1. The zirconium hydride connecting wall 3 is divided into sub-cavities which are formed in the cavity of the annular cavity and penetrate through the two opposite ends of the zirconium hydride cylinder, and the sub-cavities are filled with boron carbide blocks 4 arranged in the sub-cavities.
Alternatively, the ratio of the diameter of the zirconium hydride central column 2 to the outer diameter of the zirconium hydride column is 1:3 to 1:5. The wall thickness of the zirconium hydride connecting wall 3 is more than or equal to that of the zirconium hydride cylinder body 1.
The corners of the boron carbide blocks 4 and the corners in the sub-cavities are chamfered, so that the influence on the integrity of the control rod absorber core blocks due to the fact that the excessive stress at the corners concentrates to generate fragments when the control rod absorber core blocks are installed and stacked is prevented.
In the embodiment shown in fig. 1, the zirconium hydride cylinder comprises four zirconium hydride connecting walls 3. The four zirconium hydride connecting walls 3 divide the annular cavity between the zirconium hydride central column 2 and the zirconium hydride cylinder 3 into four sub-cavities. Correspondingly, the control rod absorber core block comprises four boron carbide blocks 4, and the four boron carbide blocks 4 are respectively filled in the four sub-cavities.
It is understood that in other embodiments, the four boron carbide segments 4 and the cavities may be increased or decreased according to specific needs, so as to increase the amount of the boron carbide, for example, three boron carbide segments 4, five boron carbide segments 4, and so on.
In the control rod absorber core block, the zirconium hydride cylinder is mainly made of zirconium hydride; in the raw material of the zirconium hydride column, the stoichiometric ratio of Zr to H is 1.7 to 1, and preferably 1:2, 1.8. Boron carbide blocks 4 consisting essentially of B 4 C, preparing; feedstock B in boron carbide agglomerates 4 4 In the step (C), the reaction solution is mixed, 1 the enrichment degree of 0B is more than or equal to 80 percent.
When the control rod absorber core block is prepared, boron carbide-enriched powder is firstly sintered in advance according to the shape of the boron carbide blocks 4, the boron carbide blocks 4 are placed in a zirconium hydride cylinder die, zirconium hydride is added, a zirconium hydride cylinder is formed by hot pressing, and the zirconium hydride cylinder and the boron carbide blocks 4 form the integral control rod absorber core block.
The control rod absorber core block of the present invention is used in a control rod. For a control rod, the control rod comprises a cladding and a plurality of control rod absorber core blocks, wherein the control rod absorber core blocks are stacked in the cladding along the axial direction of the cladding.
In summary, the control rod absorber core block of the present invention is mainly formed by a zirconium hydride column and boron carbide blocks 4 filled therein, wherein the zirconium hydride column mainly forms a structure of an inner support (such as a zirconium hydride central column 2) and an outer cladding (such as a zirconium hydride cylinder 1), and the boron carbide blocks 4 are filled in the zirconium hydride column in a spaced distribution manner. Wherein:
with boron carbide agglomerates 4 as absorber matrix, B 4 The price of C is cheaper than other absorber materials, the C is the material with the highest economical efficiency, the powder sintering is also very easy to process and manufacture, the size and the efficiency of the absorber are convenient to adjust, the manufacturing and sintering process is mature, the porosity is adjustable, and the adjustment of the deformation of the core block is convenient.
Relative reactivity value of boron carbide with other absorber materials (Dy) 2 TiO 5 、Hf、Ag-In-Cd、Dy 2 O 3 ·HfO 2 ) Relative reactivity value ofAs shown in fig. 3. From the relative reactivity values of the materials in FIG. 3 as a function of the available run time, B 4 The relative reactivity value of C is the highest in the initial stage, and the use requirement of a fast reactor (namely, a fast neutron reactor) is met. For B in 4 C, increasing therein 10 And B is higher in reactivity value.
Due to B 4 The thermal neutron absorption cross section of C is larger than the fast neutron absorption cross section, so that boron carbide blocks 4 are coated by the zirconium hydride cylinder, the zirconium hydride slowing structure is added to slow fast neutrons, and B is improved 4 C absorption efficiency, thereby improving overall control rod value.
Through the setting of zirconium hydride center post 2 and zirconium hydride connecting wall 3, form the heat conduction route, can derive the pellet surface in the boron carbide piecemeal 4 with the heat, increase pellet radiating efficiency to reduce the temperature, reduce the control rod pellet irradiation swelling, reduce gas generation, reach increase of service life, improve the effect of control rod security.
For the raw material zirconium hydride of the zirconium hydride cylinder, the stoichiometric number of H in the zirconium hydride cylinder is adjusted, so that the outermost structure of the pellet (namely the zirconium hydride cylinder 1) has the performance similar to zirconium metal, the interaction force of the pellet and the cladding can be greatly reduced, and the pellet is prevented from being cracked under the action of excessive contact force. Once the control rod absorber core blocks are pulverized due to irradiation, the zirconium hydride barrel 3 can also achieve the purposes of wrapping the fragments and continuously maintaining the integrity of the control rod absorber core blocks.
In the control rod, the absorber pellet of the control rod is in contact with the cladding through the zirconium hydride cylinder 3, and the zirconium hydride and the cladding material have stable chemical properties and good compatibility and can stably coexist for a long time.
The above description is only an embodiment of the present invention, and not intended to limit the scope of the present invention, and all modifications of equivalent structures and equivalent processes performed by the present specification and drawings, or directly or indirectly applied to other related technical fields, are included in the scope of the present invention.
Claims (10)
1. A control rod absorber core block, which is characterized by comprising a zirconium hydride cylinder with at least two cavities inside, at least two boron carbide blocks; the boron carbide blocks are respectively filled in the sub-cavities of the zirconium hydride cylinders;
within the zirconium hydride column, the height of the boron carbide block extends along the height direction of the zirconium hydride column.
2. The control rod absorber pellet of claim 1, wherein the zirconium hydride cylinder comprises a zirconium hydride cylinder, a zirconium hydride center column, and at least two zirconium hydride connecting walls;
the zirconium hydride central column is arranged in the zirconium hydride cylinder, the zirconium hydride connecting wall is connected between the outer surface of the zirconium hydride central column and the inner surface of the zirconium hydride cylinder, and an annular cavity between the zirconium hydride central column and the zirconium hydride cylinder is divided into at least two sub-cavities;
each boron carbide block is filled in one of the sub-cavities.
3. The control rod absorber pellet of claim 2, wherein the zirconium hydride cylinder, the zirconium hydride center column, and the zirconium hydride connecting wall are uniform in height.
4. The control rod absorber pellet as set forth in claim 2, wherein a ratio of a diameter of the zirconium hydride central column to an outer diameter of the zirconium hydride column is 1:3-1:5.
5. The control rod absorber pellet as set forth in claim 2, wherein the wall thickness of the zirconium hydride connecting wall is greater than or equal to the wall thickness of the zirconium hydride barrel.
6. The control rod absorber pellet of claim 2, wherein the zirconium hydride cylinder comprises four of the zirconium hydride connecting walls;
the four zirconium hydride connecting walls divide an annular cavity between the zirconium hydride central column and the zirconium hydride cylinder into four sub-cavities.
7. The control rod absorber pellet as set forth in any of claims 1-6, wherein corners of the boron carbide segment and corners within the sub-cavity are chamfered.
8. The control rod absorber pellet as set forth in any one of claims 1 to 6, wherein the boron carbide segmented feedstock B 4 In the step (C), the step (A), 10 the enrichment degree of B is more than or equal to 80 percent.
9. The control rod absorber pellet as set forth in any one of claims 1 to 6, wherein the stoichiometric ratio of Zr to H in the raw material of the zirconium hydride cylinder is 1.7 to 1.
10. A control rod comprising a cladding and a plurality of control rod absorber pellets according to any one of claims 1 to 9;
a number of the control rod absorber pellets are stacked within the cladding in an axial direction of the cladding.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202210911082.XA CN115394460A (en) | 2022-07-29 | 2022-07-29 | Control rod absorber core block and control rod |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202210911082.XA CN115394460A (en) | 2022-07-29 | 2022-07-29 | Control rod absorber core block and control rod |
Publications (1)
Publication Number | Publication Date |
---|---|
CN115394460A true CN115394460A (en) | 2022-11-25 |
Family
ID=84117817
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202210911082.XA Pending CN115394460A (en) | 2022-07-29 | 2022-07-29 | Control rod absorber core block and control rod |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN115394460A (en) |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB1056950A (en) * | 1964-12-22 | 1967-02-01 | Hitachi Ltd | Control elements for fast nuclear reactors |
FR2012731A1 (en) * | 1968-07-11 | 1970-03-20 | Atomenergi Ab | Control rod for fast atomic reactors |
US4652424A (en) * | 1985-05-09 | 1987-03-24 | Combustion Engineering, Inc. | Extended life nuclear control rod |
JPS62200290A (en) * | 1986-02-27 | 1987-09-03 | 株式会社日立製作所 | Control rod for nuclear reactor |
US6226340B1 (en) * | 1996-05-22 | 2001-05-01 | General Electric Company | Hermaphroditic absorber loading for higher worth control rods |
CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
-
2022
- 2022-07-29 CN CN202210911082.XA patent/CN115394460A/en active Pending
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB1056950A (en) * | 1964-12-22 | 1967-02-01 | Hitachi Ltd | Control elements for fast nuclear reactors |
FR2012731A1 (en) * | 1968-07-11 | 1970-03-20 | Atomenergi Ab | Control rod for fast atomic reactors |
US4652424A (en) * | 1985-05-09 | 1987-03-24 | Combustion Engineering, Inc. | Extended life nuclear control rod |
JPS62200290A (en) * | 1986-02-27 | 1987-09-03 | 株式会社日立製作所 | Control rod for nuclear reactor |
US6226340B1 (en) * | 1996-05-22 | 2001-05-01 | General Electric Company | Hermaphroditic absorber loading for higher worth control rods |
CN110853774A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
RU2546971C2 (en) | Fuel rod and method of making pellets for said fuel rod | |
US8085894B2 (en) | Swelling-resistant nuclear fuel | |
EP2647012B1 (en) | Fully ceramic nuclear fuel and related methods | |
TWI746754B (en) | A sintered nuclear fuel pellet, a fuel rod, a fuel assembly, and a method of manufacturing a sintered nuclear fuel pellet | |
KR20200089680A (en) | High temperature nuclear fuel system for thermal neutron reactor | |
CN114068043A (en) | Particulate dense fuel element | |
CN109461509B (en) | Inert matrix dispersion fuel pellet and preparation method thereof | |
KR101652729B1 (en) | Preparation method of nuclear fuel pellet with thermal conductive metal network, and the nuclear fuel pellet thereby | |
US11501885B2 (en) | Nuclear fuel pellet having enhanced thermal conductivity and method of manufacturing the same | |
CN106448749A (en) | Fuel pellet and preparation method thereof | |
CN115394460A (en) | Control rod absorber core block and control rod | |
CN109801717B (en) | Liquid lead bismuth cooling small-sized reactor fuel rod capable of reducing PCI effect | |
CN114044672B (en) | Control rod absorber material and preparation method thereof | |
US9685244B2 (en) | Active zone of lead-cooled fast reactor | |
CN114300163B (en) | Absorber material for pebble-bed high-temperature gas cooled reactor control rod and preparation method thereof | |
Radford et al. | Fabrication development and application of an annular Al2O3-B4C burnable absorber | |
CN113674875B (en) | Quick spectrum reactor core design method and core structure | |
JP4522924B2 (en) | Fuel compact | |
RU2119199C1 (en) | Absorbing core of nuclear reactor control element | |
RU2467410C1 (en) | Composite nuclear fuel pellet (versions) | |
CN117711647A (en) | Method for manufacturing neutron absorber of fast neutron reactor and neutron absorber of fast neutron reactor | |
JPS5819594A (en) | Control rod element for reactor | |
CN117253630A (en) | Reactor core based on metal additive manufacturing and manufacturing process thereof | |
RU115550U1 (en) | NUCLEAR FUEL TABLET (OPTIONS) AND NUCLEAR REACTOR FUEL ELEMENT | |
CN115938614A (en) | Rod-shaped fuel element and application thereof |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination |