CN201242873Y - fuel assembly analog piece for sodium cold rapid stack - Google Patents
fuel assembly analog piece for sodium cold rapid stack Download PDFInfo
- Publication number
- CN201242873Y CN201242873Y CNU2008201328117U CN200820132811U CN201242873Y CN 201242873 Y CN201242873 Y CN 201242873Y CN U2008201328117 U CNU2008201328117 U CN U2008201328117U CN 200820132811 U CN200820132811 U CN 200820132811U CN 201242873 Y CN201242873 Y CN 201242873Y
- Authority
- CN
- China
- Prior art keywords
- sodium
- fuel assembly
- fast reactor
- head
- cooled fast
- 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.)
- Expired - Lifetime
Links
- 239000011734 sodium Substances 0.000 title claims abstract description 24
- 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 title claims abstract description 21
- 229910052708 sodium Inorganic materials 0.000 title claims abstract description 21
- 239000000446 fuel Substances 0.000 title claims abstract description 17
- 238000004088 simulation Methods 0.000 claims abstract 7
- 230000007704 transition Effects 0.000 claims abstract 6
- 235000008331 Pinus X rigitaeda Nutrition 0.000 claims description 4
- 235000011613 Pinus brutia Nutrition 0.000 claims description 4
- 241000018646 Pinus brutia Species 0.000 claims description 4
- 239000002826 coolant Substances 0.000 abstract description 8
- 239000012535 impurity Substances 0.000 abstract description 5
- 238000009434 installation Methods 0.000 abstract description 4
- 238000000746 purification Methods 0.000 abstract 1
- 238000007789 sealing Methods 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 4
- 230000001681 protective effect Effects 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 229910052580 B4C Inorganic materials 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 1
- 238000005254 chromizing Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
Images
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
本实用新型公开了一种钠冷快堆的燃料组件模拟件。该模拟件由头部、中间部分和尾部三部分组成。头部的操作头下端的内圆上安置节流孔板，在上过渡接头中设置上屏蔽棒；中间部分还包括过滤器。本实用新型所提供的技术方案比较好地模拟了钠的流速和压降，从而满足快堆堆芯安装、调试，净化堆芯钠冷却剂中杂质等要求。
The utility model discloses a fuel assembly simulation part of a sodium-cooled fast reactor. The simulation piece consists of three parts: the head, the middle part and the tail. A throttling orifice plate is placed on the inner circle of the lower end of the operating head of the head, and an upper shielding rod is placed in the upper transition joint; the middle part also includes a filter. The technical solution provided by the utility model better simulates the flow rate and pressure drop of sodium, thereby meeting the requirements for fast reactor core installation and debugging, and purification of impurities in the core sodium coolant.
Description
Technical field
The utility model belongs to the fast neutron reactor technical field, is specifically related to the fuel assembly simulating piece of sodium-cooled fast reactor.
Background technology
Need a kind of profile, weight and the hydraulic performance simulating piece consistent with fuel assembly during the Installation and Debugging of sodium-cooled fast reactor fuel assembly, it carries out following function: the assembling function of 1) checking the reactor fuel assembly; 2) ability to work of check fuel assembly refueling agency and transmitting device thereof; 3) reload transportation system and its function of check of debugging reactor core the whole series; 4) hydrodynamic performance of debugging one loop and a loop main circulation pump comprises the upper and lower leakage current amount of assembly pin; 5) remove the impurity that to fall into during the Installation and Debugging in the reactor core sodium cooling agent.Chinese patent 200710195022.8 discloses the boron carbide shielding assembly that a kind of sodium-cooled fast reactor is used, and it is made up of head, center section and afterbody three parts.Head is made up of the last crossover sub of operating head, chromising nitrogen-hardening PROCESS FOR TREATMENT, and operating head and assembly handling machinery kissing merge the exhaust opening that is provided with sodium.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.
Summary of the invention
(1) goal of the invention
The utility model provides a kind of profile, weight and hydraulic performance consistent with fuel assembly in conjunction with prior art, and the simulating piece with certain function.
(2) technical scheme
For achieving the above object, the utility model provides following technical scheme.
A kind of fuel assembly simulating piece of sodium-cooled fast reactor is made up of head, center section and afterbody three parts, and head is made up of operating head, last crossover sub, and operating head and the merging of assembly handling machinery kissing are provided with out the sodium hole; Last crossover sub is welded on the upper surface of hexagonal pipe, and its outside is provided with locating piece to guarantee the radial location between the assembly.Center section comprises the hexagonal pipe and places the shield of sleeve pipe.Afterbody is made up of following crossover sub and pin etc., and following crossover sub is welded on the lower surface of hexagonal pipe, and pin is provided with the hole that enters of sodium.Key is, settles throttling orifice plate on the interior circle of described operating head lower end, guarantees that assembly keeps the pressure drop and the flow of regulation.
Avoid excessive radiation for protective reaction heap upper component, the shielding rod is set in last crossover sub, last shielding rod is connected with operating head with pin by screw thread.
Described center section also comprises filtrator, and shield is for shielding is excellent down.Filtrator mainly is made up of the lining and the silk screen of perforate, and fuses with shielding rod down, and cooling medium Na removes foreign material wherein through filter.
The excellent protective reaction heap of described shielding down lower member is avoided excessive radiation, is again the mass of assembly.
The ball surface portion sitting of following crossover sub by above it is on the base of little screen, and determining simulating piece in the position of reactor core, and Control Component leakage current amount up, the lower end links to each other with pin.
Pin has four kinds of different structures, and there is the ingate of cooling medium Na in the pin stage casing, and the pin epimere has the sealing of pine branch shape, and hypomere has the taenidium sealing, to control upper and lower leakage current amount.This structure had both guaranteed that the assembly of pin separately inserted on the base in flow district to one's name, was beneficial to assembly again and compressed and do not float.
(3) invention effect
The fuel assembly simulating piece of sodium-cooled fast reactor provided by the utility model is provided with filtrator, can remove the impurity that may fall into during the Installation and Debugging in the reactor core sodium cooling agent effectively; The effect that upper and lower shielding rod had both reached shielding is set, again can counterweight; By the acting in conjunction of choke block and upper and lower shielding rod, make simulated assembly simulate the flow velocity and the pressure drop of sodium better simultaneously, the fast reactor reactor core is installed, debugging thereby satisfy, and purifies the requirements such as impurity in the reactor core sodium cooling agent.
Description of drawings
The fuel assembly simulating piece structural representation of Fig. 1 sodium-cooled fast reactor;
A kind of choke block structural representation that Fig. 2 embodiment is provided;
Fig. 3 embodiment provides another kind of choke block structural representation;
Shielding bar structure synoptic diagram on Fig. 4;
Fig. 5 filter structure schematic representation.
1. operating heads among the figure, 2. go out the sodium hole, 3. go up crossover sub, 4. filtrator, 5. the hexagonal pipe, 6. time shielding rod, 7. descend crossover sub, 8. pin, 9. pine branch shape sealing, 10. advance the sodium mouth, 11. taenidiums sealing, 12. is enclosed and is shielded rod, 17a. choke block, 17b. choke block on bucket, 13. compressing tablets, 14. silk screens, 15. linings, 16..
Embodiment
Below in conjunction with accompanying drawing, the technical solution of the utility model is further elaborated.
As shown in Figure 1, a kind of fuel assembly simulating piece of sodium-cooled fast reactor is made up of head, center section and afterbody three parts.
1. head.Head is made up of operating head 1, last crossover sub 3, and the two connects by screw.Operating head 1 and assembly handling machinery kissing merge be provided with sodium go out sodium hole 2, settle throttling orifice plate on the interior circle of operating head lower end 1, guarantee that assembly keeps the pressure drop and the flow of regulation.The center-aisle of choke block can be cylindrical shape 17a as shown in Figure 2, and also 17b as shown in Figure 3 is taper.Last crossover sub 3 is welded on the upper surface of hexagonal pipe 5, and its outside is provided with locating piece to guarantee the radial location between the assembly.For protective reaction heap upper component is avoided excessive radiation, in last crossover sub 3, also be provided with as shown in Figure 4 on shielding rod 16, last shielding excellent 16 is connected with operating head 1 with pin by screw thread.
2. center section.Center section comprises hexagonal pipe 5 and places the filtrator 4 of sleeve pipe, shielding excellent 6 down.Hexagonal pipe 5 is thin-wall special-shaped pipe.Filtrator 4 is made up of the lining 15 and the silk screen 14 of perforate, and its bottom fuses with shielding rod 6 down, and the center pit of the same shielding rod 16 in top communicates.Cooling medium Na flows through through the perforate of the silk screen 14 of filter and lining 15 and goes up shielding rod 16, and wherein foreign material are intercepted outer wall at silk screen 14, and accumulates in down the collecting zone between shielding excellent 6 and the filtrator 4.As shown in Figure 5, the silk screen of filtrator 4 tight 14 tightly is wrapped in the outside of lining 15, and a side of lining 15 is scabbled slightly, and pad 13 passes through fixedly silk screen 14 of this plane.Shielding excellent 6 protective reactions heap lower member down and avoid excessive radiation, is again the mass of assembly, and it is the stainless steel right cylinder, and upper boss links to each other with filtrator 4, and sidewall connects one and encloses bucket 12, forms the impurity collecting zone with filtrator 4.
3. afterbody.Afterbody is by crossover sub 7 and pin 8 etc. are formed down, following crossover sub 7 is welded on the lower surface of hexagonal pipe 5, on the base of little screen, to determine position and Control Component up the leakage current amount of simulating piece at reactor core, the lower end links to each other with pin 8 by the ball surface portion sitting above it.Pin 8 is provided with into sodium hole 10.The pin 8 that multiple different structure is arranged is simulated different fuel assemblies.It had both guaranteed that the assembly of pin 8 separately inserted on the base in flow district to one's name, was beneficial to assembly again and compressed and do not float.Pin 8 epimeres have pine branch shape sealing 9, and hypomere has taenidium sealing 10, to control upper and lower leakage current amount.
During simulating piece work, cooling medium sodium enters assembly by the sodium mouth 10 that advances of assembly pin (8), flows through down and shield rod 6, filtrator 4, goes up shielding rod 16, choke block 17a or 17b, 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 utility model and not break away from spirit and scope of the present utility model.Like this, if of the present utility model these are revised and modification belongs within the scope of the utility model claim and equivalent technologies thereof, then the utility model also is intended to comprise these changes and modification interior.
Claims (5)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2008201328117U CN201242873Y (en) | 2008-08-06 | 2008-08-06 | fuel assembly analog piece for sodium cold rapid stack |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNU2008201328117U CN201242873Y (en) | 2008-08-06 | 2008-08-06 | fuel assembly analog piece for sodium cold rapid stack |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201242873Y true CN201242873Y (en) | 2009-05-20 |
Family
ID=40716163
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNU2008201328117U Expired - Lifetime CN201242873Y (en) | 2008-08-06 | 2008-08-06 | fuel assembly analog piece for sodium cold rapid stack |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN201242873Y (en) |
Cited By (4)
| 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 Simulator for Sodium Cooled Fast Reactor |
| CN104508750A (en) * | 2012-04-26 | 2015-04-08 | 通用电气-日立核能美国有限责任公司 | Fuel bundles for liquid metal cooled nuclear reactors |
| CN105355236A (en) * | 2015-10-13 | 2016-02-24 | 上海核工程研究设计院 | Simplified simulated fuel assembly |
| CN108292532A (en) * | 2015-09-30 | 2018-07-17 | 国家原子能公司原子能署代表俄罗斯联邦 | Fast neutron reactor fuel rod |
-
2008
- 2008-08-06 CN CNU2008201328117U patent/CN201242873Y/en not_active Expired - Lifetime
Cited By (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 Simulator for Sodium Cooled Fast Reactor |
| CN104508750A (en) * | 2012-04-26 | 2015-04-08 | 通用电气-日立核能美国有限责任公司 | Fuel bundles for liquid metal cooled nuclear reactors |
| US9576685B2 (en) | 2012-04-26 | 2017-02-21 | Ge-Hitachi Nuclear Energy Americas Llc | Fuel bundle for a liquid metal cooled nuclear reactor |
| US10706972B2 (en) | 2012-04-26 | 2020-07-07 | Ge-Hitachi Nuclear Energy Americas Llc | Fuel bundle for a liquid metal cooled nuclear reactor |
| CN108292532A (en) * | 2015-09-30 | 2018-07-17 | 国家原子能公司原子能署代表俄罗斯联邦 | Fast neutron reactor fuel rod |
| CN108292532B (en) * | 2015-09-30 | 2022-02-25 | 由俄罗斯原子能集团公司代表的俄罗斯联邦 | Fast neutron reactor fuel rod |
| CN105355236A (en) * | 2015-10-13 | 2016-02-24 | 上海核工程研究设计院 | Simplified simulated fuel assembly |
| CN105355236B (en) * | 2015-10-13 | 2018-02-02 | 上海核工程研究设计院 | A kind of simplified simulated fuel assembly |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20090520 Effective date of abandoning: 20080806 |
|
| AV01 | Patent right actively abandoned |
Granted publication date: 20090520 Effective date of abandoning: 20080806 |