CN101178947B - Boron carbide shielding assembly - Google Patents
Boron carbide shielding assembly Download PDFInfo
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- CN101178947B CN101178947B CN2007101950228A CN200710195022A CN101178947B CN 101178947 B CN101178947 B CN 101178947B CN 2007101950228 A CN2007101950228 A CN 2007101950228A CN 200710195022 A CN200710195022 A CN 200710195022A CN 101178947 B CN101178947 B CN 101178947B
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- Prior art keywords
- boron carbide
- rod
- absorber
- shielding
- assembly
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- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 title claims abstract description 38
- 229910052580 B4C Inorganic materials 0.000 title claims abstract description 24
- 239000006096 absorbing agent Substances 0.000 claims abstract description 34
- 229910052708 sodium Inorganic materials 0.000 claims abstract description 25
- 239000011734 sodium Substances 0.000 claims abstract description 25
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims abstract description 23
- 238000007731 hot pressing Methods 0.000 claims abstract description 6
- 238000005273 aeration Methods 0.000 claims description 5
- 239000011651 chromium Substances 0.000 claims description 4
- 238000005254 chromizing Methods 0.000 claims description 4
- 238000000034 method Methods 0.000 claims description 4
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 3
- CXOWYMLTGOFURZ-UHFFFAOYSA-N azanylidynechromium Chemical compound [Cr]#N CXOWYMLTGOFURZ-UHFFFAOYSA-N 0.000 claims description 3
- 229910052804 chromium Inorganic materials 0.000 claims description 3
- 150000004767 nitrides Chemical class 0.000 claims description 3
- 239000012530 fluid Substances 0.000 claims description 2
- 239000008188 pellet Substances 0.000 abstract description 6
- 239000001307 helium Substances 0.000 abstract description 4
- 229910052734 helium Inorganic materials 0.000 abstract description 4
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 abstract description 4
- 238000006243 chemical reaction Methods 0.000 abstract description 3
- 238000005336 cracking Methods 0.000 abstract description 3
- 230000007704 transition Effects 0.000 abstract 5
- 238000001816 cooling Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000005219 brazing Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000009423 ventilation Methods 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000009189 diving Effects 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
- 239000011800 void material Substances 0.000 description 1
Images
Classifications
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- 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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- Ceramic Products (AREA)
Abstract
The invention discloses a neutron reactor core shielding assembly. The assembly consists of a head part, a middle part and a tail part. The head part consists of an operating head and an upper transition joint, and the operating head is matched with the assembly and disassembly equipment and is provided with a sodium discharge hole; the outer side of the upper transition joint is provided with a positioning block to ensure the radial positioning between the components, and the upper transition joint is welded on the upper end surface of the hexagonal sleeve. The middle part is composed of a hexagonal sleeve and a shielding body arranged in the sleeve. The tail part comprises a lower transition joint, a pin and the like, the lower transition joint is welded on the lower end face of the hexagonal sleeve, and the pin is provided with a sodium inlet hole. The high-density hot-pressing boron carbide pellet used in the invention ensures that the boron carbide pellet does not escape out of the rod after cracking, and the absorber rod adopts the ventilated upper end plug to lead helium generated by B-10(n, alpha) reaction out of the rod.
Description
Technical field
The invention belongs to the fast neutron reactor technical field, be specifically related to fast neutron reactor reactor core shield assembly.
Background technology
Boron carbide shielding assembly is one of reactor core assembly of the cold fast neutron reactor of sodium; it is by escape out the neutron of reflection horizon assembly of the 10B element absorption in the natural boron carbide; with the neutron irradiation of protecting in-pile component and heap container to avoid exceeding standard, and avoid the secondary sodium in the intermediate heat exchanger to activate.Boron carbide shielding assembly mainly comprises three parts, respectively by operating head, go up head that crossover sub etc. forms, by the hexagonal sleeve pipe with place the shielding rod of sleeve pipe, the center section that the absorber cluster is formed, by the afterbody that descends crossover sub and pin etc. to form.During work, cooling medium sodium enters assembly by the sodium hole of advancing of assembly pin, and the shielding of flowing through down is excellent, absorber is excellent, go up the shielding rod, and the sodium orifice flow that goes out by operating head goes out at last.
In the prior art, structure about the absorber rod has dual mode, the first adopts the design of diving clock-type, its upper end plug has air hole, and 1 breather plug that is made of porous materials is set in involucrum, and this structure solves ventilation problem on the one hand, stop broken boron carbide to be overflowed on the other hand, but its complex structure, the welding difficulty is difficult to realize.It two is to adopt enclosed construction, as document IAEA-TECDOC-884 (Absorbermaterials, that control rods and designs of shutdown systems for advanced liquid metalfast reactors) introduces is such, make binding medium with helium, in rod, leave very long gas storage chamber, but the central temperature of boron carbide core is up to more than 2000 ℃, and the interior pressure of later stage in life-span rod is also very high, becomes the major limitation of designed life.
Summary of the invention
The objective of the invention is at boron carbide shielding assembly complex structure of the prior art, the problem that is restricted designed life provides a kind of more practical boron carbide shielding assembly.
A kind of boron carbide shielding assembly is made up of head, center section and afterbody three parts.Head is made up of operating head, last crossover sub, and operating head and assembly handling machinery kissing merge the exhaust opening that is provided with sodium; The last crossover sub outside is provided with locating piece to guarantee the radial location between the assembly, and last crossover sub is welded on the upper surface of hexagonal sleeve pipe.Center section is by the hexagonal sleeve pipe and place the shield of sleeve pipe to form.Afterbody is made up of following crossover sub and pin etc., and following crossover sub is welded on the lower surface of hexagonal sleeve pipe, and pin is provided with the hole that enters of sodium.Key is, the locating piece of last crossover sub adopts chromising nitrogen-hardening PROCESS FOR TREATMENT, form based on the nitride of chromium, thickness is 0.07～0.14mm chromium nitride disperse layer.Described shield by the absorber cluster, go up the shielding rod, the shielding rod is formed down.The absorber cluster is made up of the absorber rod.The absorber rod comprises the involucrum pipe, place boron carbide core in the involucrum pipe, end plug is formed up and down, and wherein boron carbide core is that density is 2.0～2.5g/cm
3The hot pressing boron carbide core, upper end plug adopts aeration type.
In addition, in order to guarantee that each building block all has the space of axial expansion, integrality when guaranteeing assembly work, being connected of last shielding rod and last crossover sub, absorber cluster are connected with upper and lower location grid, and down shielding rod and following crossover sub the mode that is connected the employing hinge or leave enough end play.
In the technical scheme provided by the present invention, the locating piece of assembly has adopted chromising nitrogen-hardening PROCESS FOR TREATMENT, and hardness has reached HV
5400 or HV
0.1600, prevented the self-brazing of inter-module, increase the wearing quality of operating head, simultaneously at high temperature anti-sodium corrosion.Particularly use high density hot pressing boron carbide core in the absorber rod, guarantee that it does not overflow outside the rod behind cracking, the absorber rod adopts the upper end plug of aeration type simultaneously, and (n is α) outside the helium eduction rod that reaction produces with B-10; Simultaneously, owing to be to be binding layer between the excellent involucrum of boron carbide core and absorber, reduced the central temperature of boron carbide core, thereby alleviated the stress of involucrum greatly with the Liquid Sodium.Therefore, the boron carbide shielding assembly technical scheme that is provided is not only practical, and has solved the pressure-bearing problem of absorber rod involucrum effectively.
Description of drawings
Fig. 1 boron carbide shielding assembly structural representation;
A-A cut-open view among Fig. 2 Fig. 1;
Fig. 3 absorber bar structure synoptic diagram;
B-B cut-open view among Fig. 4 Fig. 3.
1. operating heads among the figure, 2. go out the sodium hole, 3. go up crossover sub, 4. the sexangle outer tube, 5. on shielding rod, 6.B
4C shielding cluster, 7. time shielding rod, 8. descend crossover sub, 9. pin, 10. enter sodium hole, 11. locating pieces, 12. upper end plug (ventilation), 13. involucrums, 14. boron carbide cores, 15. and locate wrapping wires, 16. times end plugs.
Embodiment
Below in conjunction with accompanying drawing, technical scheme of the present invention is further elaborated.
The described boron carbide shielding assembly of present embodiment is arranged in the periphery of sodium-cooled fast reactor reflection horizon assembly, divides 4 layers of layout, totally 230 boxes, and they are in the fast neutron irradiated of different fluences and the sodium by natural convection cools off.Basic design and operational factor are as shown in table 1.
The basic parameter of table 1 boron carbide shielding assembly
| Parameter name | Numerical value |
| Shielding material | Boron carbide |
| 10B enrichment (%) | (19.8 natural) |
| B in one case assembly 4C weight (kg) | 2.4 |
| The weight of one case assembly (kg) | ～32 |
| The mission life of assembly under the rated power (effectively sky) | |
| (1) ground floor | 1440 |
| (2) second layer | 1680 |
| (3) the 3rd layers | 1920 |
| (4) the 4th layers | 2240 |
| The pot-life of New Parent (year) | 3 |
| With the time (year) of the assembly of crossing in the cooling pond placement | ≤30 |
| The maximum damage dose (dpa) of sexangle |
6 |
| Maximum neutron fluence (10 23/cm 2) | 0.38 |
| B 4The maximum burnup (%) of C | |
| 10B | 19 |
| B | 3.8 |
| Maximum heat release rate (MW/m 3) in boron carbide in stainless steel | 10 5 |
| Cooling condition | The Natural Circulation cooling of sodium |
As shown in Figure 1, the profile of the boron carbide shielding assembly that present embodiment provided is consistent with fuel assembly, to keep the radial location with other assembly.It is made up of head, center section and afterbody three parts.The structure and the function of each several part are as follows:
1. head.Head is made up of operating head 1, last crossover sub 3.Operating head 1 is provided with out sodium hole 2 with the merging of assembly handling machinery kissing; Last crossover sub 3 is provided with locating piece 11 to guarantee the radial location between the assembly, and last crossover sub 3 is welded on the upper surface of sexangle outer tube 4.Wherein locating piece 11 is through chromising nitrogen-hardening PROCESS FOR TREATMENT, form based on the nitride of chromium, thickness is (0.07～0.14mm) chromium nitride (Cr
2N) disperse layer, hardness has reached HV
5400 or HV
0.1600, it has prevented the self-brazing of inter-module, increases the wearing quality of operating head 1, simultaneously at high temperature anti-sodium corrosion.
2. center section.It is by sexangle outer tube 4 and place upward shielding rod 5, absorber cluster 6, the following shielding excellent 7 of sleeve pipe to form.The absorber rod that absorber cluster 6 is 19.2mm by 7 diameters is formed, and presses the triangle lattice cell and arranges, and interrod spacing is 20.25mm.Absorber rod upper end is fixed on the Turbogrid plates with nut, in the hole of Turbogrid plates, makes it that the possibility that vertically moves be arranged when thermal expansion and void swelling downwards under lower end injects.Being wound with diameter on the absorber rod of center is 0.8～1.1mm wrapping wire, and pitch is 80～110mm, makes between it and the adjacent absorber rod to keep certain distance.The diameter that present embodiment adopts is the 0.95mm wrapping wire, and pitch is 100mm.The absorber rod is made up of involucrum pipe 13, aeration type upper end plug 12, following end plug 16, boron carbide core 14 and location wrapping wire 15 (only central rod has wrapping wire).Boron carbide core 14 is placed in the involucrum pipe 13, and it is 2.0～2.5g/cm that pellet uses density
3Hot pressing absorber rod, high density hot pressing boron carbide core guarantees that it does not overflow outside the rod behind cracking.Present embodiment adopts 2.1g/cm
3Pellet.Be aeration type on the upper end plug 12, be provided with cross opening or diameter in its underpart and be 2～3 millimeters air hole, thereby (n is α) outside the helium eduction rod that reaction produces with B-10.Be to be binding layer between pellets 14 and the involucrum in the involucrum 13, reduced the central temperature of pellet 14, thereby alleviated the stress of involucrum 13 greatly with the Liquid Sodium.
Place upper and lower shielding rod 5,7 in the upper and lower part of absorber cluster 6, and absorber cluster 6 and excellent 5,7 of upper and lower shielding leave the space.Upper and lower shielding rod 5,7 is steel shielding rod, and it is as the radiation shield of in-pile component, and the upper end of wherein going up shielding rod 5 is welded on the crossover sub 3, and the lower end of following shielding rod 7 is fixed on down on the crossover sub 8.
3. afterbody.It is by crossover sub 8 and pin 9 etc. are formed down.Following crossover sub 8 is welded on the lower surface of hexagonal sleeve pipe 4.Pin 9 is provided with into sodium hole 10, guarantees the sodium flow by stipulating in the boron carbide shielding assembly, and matching with the conical surface jack of little grid plate header in its spherical outer face, relies on the fluid power self-tightening, guarantees all can not float under any operating mode.Pin 9 is fixed to down on the crossover sub 8 with screw thread earlier, and welding with it then is to guarantee strength of joint.
Boron carbide shielding assembly is when work, and cooling medium sodium enters assembly by the sodium hole 10 of advancing of assembly pin 9, flows through down and shield rod 7, absorber cluster 6, goes up shielding rod 5, and flow out in the last sodium hole 2 that goes out by operating head 1.
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Like this, if of the present invention these are revised and modification belongs within the scope of claim of the present invention and equivalent technologies thereof, then the present invention also is intended to comprise these changes and modification interior.
Claims (4)
1. boron carbide shielding assembly, form by head, center section and afterbody three parts, head is made up of operating head (1), last crossover sub (3), operating head (1) is provided with out sodium hole (2) with the merging of assembly handling machinery kissing, the last crossover sub (3) that the outside is provided with locating piece (11) is welded on the upper surface of sexangle outer tube (4), locating piece (11) adopts chromising nitrogen-hardening PROCESS FOR TREATMENT, form based on the nitride of chromium, thickness is 0.07～0.14mm chromium nitride disperse layer; Center section is by sexangle outer tube (4) and place the shield of sexangle outer tube (4) to form; Afterbody is made up of following crossover sub (8) and pin (9), and following crossover sub (8) is welded on the lower surface of sexangle outer tube (4), and pin (9) is provided with into sodium hole (10);
It is characterized in that: described shield is made up of absorber cluster (6), upward shielding excellent (5), following shielding excellent (7), being connected of last shielding rod (5) and last crossover sub (3), absorber cluster (6) are connected with upper and lower location grid, and the mode that is connected the employing hinge of shielding rod (7) and following crossover sub (8) down;
Described absorber cluster (6) is made up of the absorber rod, is wound with location wrapping wire (15) on the center absorber rod of absorber cluster (6), and location wrapping wire (15) diameter is 0.8～1.1mm, and pitch is 80～110mm;
The absorber rod comprises involucrum pipe (13), places boron carbide core (14) and upper and lower end plug (12,16) in the involucrum pipe (13), and wherein boron carbide core (14) is that density is 2.0～2.5g/cm
3The hot pressing boron carbide core, upper end plug (12) adopts aeration type.
2. according to the described boron carbide shielding assembly of claim 1, it is characterized in that: described upper end plug (12) ventilating mode is that be provided with cross opening or diameter in its underpart be 2～3 millimeters air hole.
3. according to the described boron carbide shielding assembly of claim 1, it is characterized in that: described absorber cluster (6) is that absorber rod upper end is fixed on the Turbogrid plates with nut with the mode of the hinge of upper and lower location grid, and lower end injects in the hole of following Turbogrid plates.
4. according to the described boron carbide shielding assembly of claim 1, it is characterized in that: the sphere of the outer face of described pin (9) for matching with the conical surface jack of little grid plate header relies on the fluid power self-tightening.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2007101950228A CN101178947B (en) | 2007-12-11 | 2007-12-11 | Boron carbide shielding assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2007101950228A CN101178947B (en) | 2007-12-11 | 2007-12-11 | Boron carbide shielding assembly |
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| Publication Number | Publication Date |
|---|---|
| CN101178947A CN101178947A (en) | 2008-05-14 |
| CN101178947B true CN101178947B (en) | 2011-07-20 |
Family
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Family Applications (1)
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|---|---|---|---|
| CN2007101950228A Active CN101178947B (en) | 2007-12-11 | 2007-12-11 | Boron carbide shielding assembly |
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Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101335058B (en) * | 2008-08-06 | 2011-07-20 | 中国原子能科学研究院 | Fuel assembly simulation piece of sodium-cooled fast reactor |
| CN104183290B (en) * | 2013-05-28 | 2016-12-28 | 中国原子能科学研究院 | Experiment Fast Reactor is with containing neptunium transmuting test assembly |
| CN105244067B (en) * | 2015-08-25 | 2017-08-25 | 中国科学院合肥物质科学研究院 | A kind of high density and the reactor shielding layer assembly of big neutron absorption cross-section |
| CN107230503B (en) * | 2016-03-25 | 2020-01-21 | 华北电力大学 | Shielding assembly structure with shielding performance |
| CN107767969A (en) * | 2017-09-04 | 2018-03-06 | 中广核研究院有限公司 | The core structure and core loading method of pressure vessel |
| CN107767968A (en) * | 2017-09-04 | 2018-03-06 | 中广核研究院有限公司 | Reactor and the shielding fuel assembly for reducing nuclear reactor neutron leakage |
| CN112002442B (en) * | 2020-07-31 | 2022-09-23 | 清华大学 | Cross-wing control rod |
| CN112768093B (en) * | 2020-12-31 | 2023-05-23 | 中国原子能科学研究院 | Shielding structure, shielding assembly and sodium-cooled fast reactor |
-
2007
- 2007-12-11 CN CN2007101950228A patent/CN101178947B/en active Active
Non-Patent Citations (6)
| Title |
|---|
| 傅博、李盛荣、王永兰.碳化硼陶瓷材料密度的控制方法与应用.辽宁工学院学报17 2.1997,17(2),44-47. |
| 傅博、李盛荣、王永兰.碳化硼陶瓷材料密度的控制方法与应用.辽宁工学院学报17 2.1997,17(2),44-47. * |
| 叶俭.奥氏体不锈钢的铬氮复合渗.金属热处理32 4.2007,32(4),79-80. |
| 叶俭.奥氏体不锈钢的铬氮复合渗.金属热处理32 4.2007,32(4),79-80. * |
| 谢光善、王晓荣.CEFR碳化硼芯块试制.中国原子能科学研究院年报.2001,5. * |
| 黄晨.CEFR碳化硼屏蔽组件初步设计，黄晨，，第96-97页，1995年.中国原子能科学研究院年报.1995,96-97. * |
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