CN203260332U - Neptunium-containing transmutation test assembly for an experimental fast reactor - Google Patents
Neptunium-containing transmutation test assembly for an experimental fast reactor Download PDFInfo
- Publication number
- CN203260332U CN203260332U CN2013202977229U CN201320297722U CN203260332U CN 203260332 U CN203260332 U CN 203260332U CN 2013202977229 U CN2013202977229 U CN 2013202977229U CN 201320297722 U CN201320297722 U CN 201320297722U CN 203260332 U CN203260332 U CN 203260332U
- Authority
- CN
- China
- Prior art keywords
- neptunium
- test assembly
- transmuting
- fast reactor
- assembly
- 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
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model relates to a neptunium-containing transmutation test assembly for a Chinese experimental fast reactor (CEFR). The test assembly comprises an operating head (1), an upper transition joint (2), an outer sleeve (4), a lower transition joint (7), a pin (8) and a pin point (9) which are sequentially fixedly connected with each other, a grid frame (6) is arranged at the lower end in the outer sleeve (4), and the grid frame (6) is fixedly connected with the outer sleeve (4); and a target element assembly (3) is arranged in the outer sleeve (4), and the upper end of the target element assembly (3) is fixedly connected with the upper transition joint (2). The test assembly can be put in the first row of stainless steel reflection layer assemblies in the CEFR core for irradiation test, so the main technologic parameters of the test assembly are obtained; and the test assembly can be matched with other assemblies of the core, the material changing system of the core assembly and the lower grid structure of the core.
Description
Technical field
The utility model belongs to the nuclear power technology field, is specifically related to a kind of Experiment Fast Reactor with containing neptunium transmuting test assembly.
Background technology
After China Experiment Fast Reactor (CEFR) is built up, to become the test platform of fast reactor technical research, wherein very important a part of content is exactly the irradiation test that carries out New-type fuel and structured material, and the important step of the circulation strategy that acts as a fuel, research and the transmuting rule of grasp long-life nucleic in fast reactor also become the task of top priority.Contain neptunium transmuting assembly and be exactly for this purpose and development and design.
Summary of the invention
The transmuting rule in Experiment Fast Reactor for research and grasp neptunium pellet, the purpose of this utility model provides a kind of Experiment Fast Reactor with containing neptunium transmuting test assembly, test by adopting this test assembly, can obtain the important technological parameters of this assembly, and the design of this structure has guaranteed to contain the coupling of neptunium transmuting test assembly and other assembly of reactor core.
For reaching above purpose, the technical solution adopted in the utility model is: provide a kind of Experiment Fast Reactor with containing neptunium transmuting test assembly, comprise affixed successively operating head, upper crossover sub, outer tube, lower crossover sub, pin and pin joint, the lower end is provided with the screen screen work in the described outer tube, and described screen screen work and described outer tube are affixed; Be provided with the target element subassembly in the described outer tube, the upper end of described target element subassembly and upper crossover sub are affixed.
Further, described target element subassembly comprises top grating and is fixed in the little six angle pipes of top grating lower surface, is provided with mutually affixed upper sleeve pipe and running casing in the described little six angle pipes, and the upper end of described upper sleeve pipe and described top grating are affixed; Described upper sleeve pipe and inside, described cased junction are provided with upper spacer, and the lower end in the described running casing is provided with lower clapboard; Be provided with the neptunium rod between described upper spacer and the lower clapboard, upper spacer is inserted in the upper end of described neptunium rod, and the lower end is inserted lower clapboard and is fixedly connected with it.
Further, be provided with temperature monitoring between described upper spacer and the described top grating, top grating is inserted in described temperature monitoring upper end, upper spacer is inserted in the lower end.
Further, described running casing outer wall is provided with elongated slot vertically, is provided with flux monitor in the described elongated slot.
Further, be provided with stainless steel parts between described outer tube and the described little six angle pipes, described stainless steel parts lower end is fixed on the screen screen work; Described stainless steel parts comprises the end plug at cladding tubes and welding cladding tubes two ends, and cladding tubes inside is divided into air cavity and entity two parts, is air cavity corresponding to the position of reactor core active region, and all the other are stainless steel solid.
Further, described neptunium rod is cladding tubes, and weld with end plug at described cladding tubes two ends; Be provided with in the described cladding tubes and contain the neptunium pellet, the described neptunium pellet that contains is by end plug and holddown spring location.
Further, be provided with coolant entrance above the described pin, the pin upper and lower part is provided with seal groove.
Further, be equipped with the coolant flow through hole on described top grating, upper spacer and the lower clapboard, described operating head is provided with coolant outlet.
The beneficial effects of the utility model are:
(1) adopts containing neptunium transmuting test assembly and can putting into the position of Experiment Fast Reactor reactor core first row Stainless Steel Reflector of Core assembly and carry out irradiation test of the utility model institute processing and manufacturing;
(2) obtain the important technological parameters of this test assembly by this experiment, for the use of neptunium element provides reliable data;
(3) this test assembly has guaranteed the coupling with other assembly of reactor core, reactor core assembly refuelling system and reactor core lower grid plate structure.
Description of drawings
Fig. 1 is the utility model Experiment Fast Reactor structural representation that contains neptunium transmuting test assembly;
Fig. 2 be among Fig. 1 A-A to cut-open view;
Fig. 3 is the hit structural representation of component assembly of Fig. 1.
Embodiment
Below in conjunction with accompanying drawing embodiment of the present utility model is described in further detail.
As shown in Figure 1, 2, Experiment Fast Reactor provided by the utility model comprises affixed successively operating head 1, upper crossover sub 2, outer tube 4, lower crossover sub 7, pin 8 and pin joint 9 with containing neptunium transmuting test assembly.Outer tube 4 interior lower ends are installed with screen screen work 6; Be provided with target element subassembly 3 in the outer tube 4, the upper end of described target element subassembly 3 and upper crossover sub 2 are affixed; Be provided with two circle stainless steel parts 5 between outer tube 4 and the target element subassembly 3, stainless steel parts 5 is fixed on the screen screen work 6.
Wherein, the interface of CEFR refueling machine grabbing assembly when operating head 1 is charge and discharge operations, the above arranges coolant outlet.
The xsect of upper crossover sub 2 is hexagon, is used for the transition and conversion of the profile between operating head 1 and the outer tube 4, and the position at six angles arranges projection, play and peripheral components between the effect of radial location.Be connected with pin by screw thread between upper end and the operating head 1, lower end and target element subassembly 3 and outer tube 4 welds.
Outer tube 4 is that xsect is hexagonal supporting sleeve, is used for containing the core of assembly.
Stainless steel parts 5 comprises cladding tubes and is welded on the end plug at cladding tubes two ends, in fill the normal pressure helium.Be divided into air cavity and entity two parts in each cladding tubes, the position of corresponding reactor core active region is the long air cavity of 450mm, and all the other are stainless steel solid.
Screen screen work 6 is welded on the outer tube 4, adopts the screen screen work of head of garlic tee section, the lower end edge fluting of stainless steel parts 5 is pushed the screen screen work can realize axial location, does not need welding.
Lower crossover sub 7 and outer tube 4 welding are used for the profile transition and conversion, and and the jack of the little grid plate header of fixation kit of reactor core between form the sealing of ball cone.
Pin 8 is threaded connection and welds with lower crossover sub 7, and the above arranges coolant entrance; The pin upper and lower part is provided with pine branch shape seal groove, can control cooling medium by the leakage current amount of assembly outside.
Be threaded connection and weld between pin joint 9 and the pin 8, at the pin joint some circular flow regulator pieces are set, symmetry offers the horizontal direction rectangular channel on the flow regulator pieces, offers the vertical direction rectangular channel in the adjacent segments flow.
As shown in Figure 3, target element subassembly 3 comprises top grating 31 and is fixed in the little six angle pipes 32 of top grating 31 lower surfaces that be provided with mutually affixed upper sleeve pipe 33 and running casing 34 in the little six angle pipes 32, the upper end of upper sleeve pipe 33 and top grating 31 are affixed; Upper sleeve pipe 33 is provided with upper spacer 35 with the inside, junction of running casing 34, and the lower end in the running casing is provided with lower clapboard 36; Be provided with neptunium rod 37 between upper spacer and the lower clapboard, upper spacer 35 is inserted in the upper end of neptunium rod 37, and the lower end is inserted lower clapboard 36 and is fixedly connected with it.Be laid with three temperature monitorings 38 between upper spacer and the top grating, top grating 31 is inserted in temperature monitoring 38 upper ends, and upper spacer 35 is inserted in the lower end.The running casing outer wall is laid with three elongated slots vertically corresponding to the position of active region, is provided with three flux monitors 39 in described three elongated slots, and the flux monitor two ends add clip and are welded and fixed.
Wherein, neptunium rod 37 adopts external diameter 6.0mm, the cladding tubes of wall thickness 0.4mm, and two ends and end plug welding, inside is filled with 0.11~0.13MPa helium, and the outside is tied with wrapping wire.The inside of neptunium rod is provided with and contains the neptunium pellet, contains the long 96mm of neptunium pellet, relies on two ends end plug and holddown spring location.The mass percentage content of neptunia is 5% in the pellet, and all the other are depleted uranium.
Three temperature monitorings are welded by φ 6.0 * 0.4mm cladding tubes and end plug, in fill the 0.1MPa helium, the eutectic alloy of built-in heterogeneity, but the monitor temperature scope is 500~640 ℃.
Three flux monitors, its structure is similar to temperature monitoring, the built-in quartz ampoule that complete neutron activation foil detector is housed.
In order to guarantee the Experiment Fast Reactor cooling problem that contains neptunium transmuting test assembly, on pin, be provided with the inflow entrance of cooling medium, the coolant flow through hole all is set on top grating, upper spacer and the lower clapboard, operating head is provided with the flow export of cooling medium.Wherein, CEFR adopts sodium as cooling medium.Contain neptunium transmuting test assembly when work, cooling medium sodium flows into from pin, behind restriction device and screen screen work, is divided into two branch roads.Article one, branch road flows into the target element subassembly of central authorities, through containing neptunium fuel rod and temperature monitoring, and another branch road stainless steel parts of flowing through.Two-way cooling medium sodium stream all flows out from top grating, and the upper crossover sub inner chamber of flowing through again flows out from operating head at last.
Experiment Fast Reactor all adopts domestic 20% cold worked 316 (Ti) stainless steel with the stainless steel parts, operating head, upper crossover sub, outer tube, lower crossover sub and the pin that contain in the neptunium transmuting test assembly.
The below is the important technological parameters that contains neptunium transmuting test assembly:
Important technological parameters
Parameter name | Numerical value |
The assembly total length, mm | 2592 |
The assembly gross weight, kg | 28 |
Neptunium rod total length, mm | 1325 |
Contain neptunium column of pellets length, mm | 96 |
Stainless steel parts quantity, root | 42 |
The stainless steel parts total length, mm | 1350 |
Neptunium rod maximum linear heat generation rate, W/cm | 22 |
Neptunium rod maximum fuel burnup, MWd/kg | 2.3 |
Contain neptunium pellet maximum temperature, ℃ | 568 |
The cladding tubes maximum temperature, ℃ | 500 |
Coolant inlet temperature, ℃ | 360 |
Coolant outlet temperature, ℃ | 500 |
Coolant flow is through the maximum pressure drop of assembly, MPa | 0.27 |
Experiment Fast Reactor described in the utility model is not limited to the embodiment described in the embodiment with containing neptunium transmuting test assembly, those skilled in the art draw other embodiment according to the technical solution of the utility model, belong to equally technological innovation scope of the present utility model.
Claims (8)
1. an Experiment Fast Reactor is with containing neptunium transmuting test assembly, comprise affixed successively operating head (1), upper crossover sub (2), outer tube (4), lower crossover sub (7), pin (8) and pin joint (9), the interior lower end of described outer tube (4) is provided with screen screen work (6), and described screen screen work (6) is affixed with described outer tube (4); It is characterized in that, be provided with target element subassembly (3) in the described outer tube (4), the upper end of described target element subassembly (3) and upper crossover sub (2) are affixed.
2. Experiment Fast Reactor according to claim 1 is with containing neptunium transmuting test assembly, it is characterized in that, described target element subassembly (3) comprises top grating (31) and is fixed in the little six angle pipes (32) of top grating (31) lower surface, be provided with mutually affixed upper sleeve pipe (33) and running casing (34) in the described little six angle pipes (32), the upper end of described upper sleeve pipe (33) and described top grating (31) are affixed; Described upper sleeve pipe (33) is provided with upper spacer (35) with the inside, junction of described running casing (34), and the lower end in the described running casing is provided with lower clapboard (36); Be provided with neptunium rod (37) between described upper spacer and the described lower clapboard, upper spacer (35) is inserted in the upper end of described neptunium rod (37), and the lower end is inserted lower clapboard (36) and is fixedly connected with it.
3. Experiment Fast Reactor according to claim 2 is with containing neptunium transmuting test assembly, it is characterized in that, be provided with temperature monitoring (38) between described upper spacer (35) and the described top grating (31), top grating (31) is inserted in described temperature monitoring (38) upper end, upper spacer (35) is inserted in the lower end.
4. Experiment Fast Reactor according to claim 3 is characterized in that with containing neptunium transmuting test assembly, and described running casing (34) outer wall is provided with elongated slot vertically, is provided with flux monitor (39) in the described elongated slot.
5. Experiment Fast Reactor according to claim 4 is with containing neptunium transmuting test assembly, it is characterized in that, be laid with stainless steel parts (5) between described outer tube (4) and the described little six angle pipes (32), described stainless steel parts (5) lower end is fixed on the screen screen work (6); Described stainless steel parts comprises cladding tubes and is welded on the end plug at described cladding tubes two ends, and described cladding tubes inside is divided into air cavity and entity two parts, is air cavity corresponding to the position of reactor core active region, and all the other are stainless steel solid.
6. each described Experiment Fast Reactor is characterized in that with containing neptunium transmuting test assembly according to claim 2-5, and described neptunium rod is cladding tubes, and weld with end plug at described cladding tubes two ends; Be provided with in the described cladding tubes and contain the neptunium pellet, the described neptunium pellet that contains is by the described end plug in two ends and holddown spring location.
7. Experiment Fast Reactor according to claim 6 is characterized in that with containing neptunium transmuting test assembly, and described pin is provided with coolant entrance above (8), and pin (8) upper and lower part is provided with seal groove.
8. Experiment Fast Reactor according to claim 7 is characterized in that with containing neptunium transmuting test assembly, is equipped with the coolant flow through hole on described top grating, upper spacer and the lower clapboard; Described operating head is provided with coolant outlet.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN2013202977229U CN203260332U (en) | 2013-05-28 | 2013-05-28 | Neptunium-containing transmutation test assembly for an experimental fast reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN2013202977229U CN203260332U (en) | 2013-05-28 | 2013-05-28 | Neptunium-containing transmutation test assembly for an experimental fast reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
CN203260332U true CN203260332U (en) | 2013-10-30 |
Family
ID=49472878
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN2013202977229U Expired - Lifetime CN203260332U (en) | 2013-05-28 | 2013-05-28 | Neptunium-containing transmutation test assembly for an experimental fast reactor |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN203260332U (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104180967A (en) * | 2013-05-28 | 2014-12-03 | 中国原子能科学研究院 | Outside-reactor experimental section for component |
CN104183290A (en) * | 2013-05-28 | 2014-12-03 | 中国原子能科学研究院 | Neptunium-containing transmutation test assembly for experimental fast reactor |
-
2013
- 2013-05-28 CN CN2013202977229U patent/CN203260332U/en not_active Expired - Lifetime
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104180967A (en) * | 2013-05-28 | 2014-12-03 | 中国原子能科学研究院 | Outside-reactor experimental section for component |
CN104183290A (en) * | 2013-05-28 | 2014-12-03 | 中国原子能科学研究院 | Neptunium-containing transmutation test assembly for experimental 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 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JP5918228B2 (en) | Triuranium disilicide nuclear fuel composition for light water reactors | |
CN110600150A (en) | Irradiation test device for metal type fast reactor fuel element | |
CN109545412B (en) | Online removing device for fission gas of pressurized water reactor fuel assembly | |
CN105244069A (en) | High-specific-activity radioactive source core target, radioactive rod and novel thimble plug assembly | |
CN104183290A (en) | Neptunium-containing transmutation test assembly for experimental fast reactor | |
CN203260332U (en) | Neptunium-containing transmutation test assembly for an experimental fast reactor | |
CN109935349A (en) | A kind of cooling annular fuel assembly of the fixed square double-sided in fuel rod lower end | |
CN103310855A (en) | Liquid heavy metal cooling reactor fuel assembly | |
Domínguez et al. | Evolution of the Canadian SCWR fuel-assembly concept and assessment of the 64 element assembly for thermalhydraulic performance | |
KR20100085465A (en) | A simulation method for the temperature and heat flux of dual-cooled, annular, nuclear fuel rod | |
US8293151B2 (en) | Triuranium disilicide nuclear fuel composition for use in light water reactors | |
CN207731671U (en) | A kind of two-sided cooling annular fuel rod with wrapping wire | |
CN208767029U (en) | A kind of fuel assembly and its bottom nozzle and bottom device | |
Nava-Dominguez et al. | Canadian SCWR bundle optimization for the new fuel channel design | |
Duan et al. | Conceptual design of oil field energy supply system based on natural circulation lead–bismuth fast reactor | |
CN104662613A (en) | Lower end plug with temperature reduction device and nuclear reactor fuel rod including same | |
CN107230503A (en) | A kind of shield assembly structure with high-efficiency shielding performance | |
RU2524681C2 (en) | Fuel element for nuclear reactor | |
CN104676919B (en) | The solar energy tower type heat extractor of a kind of biserial tubular construction and method for designing thereof | |
Chen et al. | Preliminary thermal-hydraulic design and analysis of china lead alloy cooled research reactor (CLEAR-I) | |
CN203021290U (en) | Composite hydrogen storage system | |
Deokule et al. | Reactor physics and thermal hydraulic Analysis of annular fuel rod cluster for Advanced Heavy Water Reactor | |
CN106448750B (en) | A kind of Embedded Double flow supercritical water reactor fuel assembly | |
CN109036591A (en) | Nuclear reactor | |
Conboy et al. | Thermal-hydraulic performance of cross-shaped spiral fuel in high-power-density BWRs |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C14 | Grant of patent or utility model | ||
GR01 | Patent grant |