CN204496935U - Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor - Google Patents
Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor Download PDFInfo
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- CN204496935U CN204496935U CN201420744490.1U CN201420744490U CN204496935U CN 204496935 U CN204496935 U CN 204496935U CN 201420744490 U CN201420744490 U CN 201420744490U CN 204496935 U CN204496935 U CN 204496935U
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- reactor core
- pressurized water
- pressure reduction
- simulation test
- layout structure
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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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Abstract
The utility model discloses the pressure reduction point layout structure in the overall hydraulic simulation test of a kind of pressurized water reactor, the groove in order to pre-buried pressure guiding pipe is offered respectively in the upper and lower surface of reactor core upper plate and reactor core support lower plate, pressure guiding pipe comprises linkage section and embedded section, and the sidewall of embedded section is in axial direction arranged at intervals with through hole; The sidewall of described groove is provided with the water inlet clearance groove corresponding with the lead to the hole site of embedded section.By adopting pressure reduction point layout structure of the present utility model, in the overall hydraulic simulation test of pressurized water reactor, liquid enters in pressure guiding pipe by through hole on the embedded section sidewall that is embedded in the pressure guiding pipe of correspondence position, then test model is drawn along pressure guiding pipe endoporus, the surveying instrument connected by outside record reactor core upper plate, reactor core support lower plate upper and lower surface respectively with the pressure reduction of reference position, obtain the pressure drop data of reactor critical section, the rationality of in-pile component structural design and the correctness of flow field analysis can be verified preferably.
Description
Technical field
The utility model relates to PWR nuclear power plant nuclear reactor designs field, relates in particular to the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor.
Background technology
In-pile component is one of visual plant in reactor main body system, it is arranged in reactor pressure vessel, hold and support reactor core, combining realization response heap function with equipment such as reactor pressure vessel, control rod drive mechanisms (CRD), fuel assembly and associated components.According to the requirement of respective standard regulation and safety criterion, for prototype reactor, be checking in-pile component design and analysis, the overall hydraulic simulation experimental study of reactor must be carried out.It can verify the rationality of the degree of uniformity of core inlet assignment of traffic and structural design, analytical calculation; The result of calculation of the resistance to flow (pressure drop) of each critical section under the interior flow action of checking heap; Rate of flow of fluid distribution in confirmatory reaction heap chamber.
In the overall hydraulic simulation test of pressurized water reactor, test model is usually reduced according to a certain percentage according to prototype and is obtained by certain Amending design.In the overall hydraulic simulation test of pressurized water reactor, the drop measurement of reactor core upper plate and reactor core support lower plate upper and lower surface is significant, it to be related in reactor reactor core section and other critical sections under flow action and to obtain resistance to flow, designs and flow field analysis provides significant data for reactor core internals.
In order to measure the resistance to flow (pressure drop) of each critical section under flow action in heap, need to arrange pressure reduction measuring point at test model ad-hoc location.According to test needs, all need to arrange corresponding pressure reduction measuring point on the surface of reactor core upper plate and reactor core support lower plate.
The pressure reduction point layout mode of traditional reactor core upper plate and reactor core support lower plate is by guide assembly and the auxiliary layout of secondary support column assembly, gets the identical position of its axial height and installs pressure guiding pipe.The measurement result relative ideal of this method for arranging, but due to the relation of guide cylinder and secondary support column physical location, there is limitation in its point position, is easily subject to the impact of other structures simultaneously, brings measuring error.Lean on the surface of reactor fuel assembly simultaneously at reactor core upper plate and reactor core support lower plate respectively, corresponding measuring point cannot be arranged.
Utility model content
For the problems referred to above, the utility model provides the pressure reduction point layout structure in the overall hydraulic simulation test of a kind of pressurized water reactor, to solve pressure reduction point layout structure of the prior art easily by the impact of other structures, brings the problem of measuring error.
To achieve these goals, the technical solution of the utility model is as follows:
Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor, it is characterized in that, the groove in order to pre-buried pressure guiding pipe is offered respectively in the upper and lower surface of reactor core upper plate and reactor core support lower plate, described pressure guiding pipe comprises linkage section in order to be connected with external measurement devices and in order to be embedded in the embedded section in described groove, the sidewall of described embedded section is in axial direction arranged at intervals with through hole, the perforate direction of through hole be parallel to reactor core upper plate and reactor core support lower plate upper and lower surface and perpendicular to the axis of pressure guiding pipe self; The sidewall of described groove is provided with the water inlet clearance groove corresponding with the lead to the hole site of embedded section.
In a preferred embodiment of the present utility model, detected fluid is drawn out-pile along reactor axial direction and is measured by linkage section.
In a preferred embodiment of the present utility model, the width of described groove is not less than the width of embedded section.
In a preferred embodiment of the present utility model, described depth of groove is 0.2:1 ~ 3:1 with the ratio of the equivalent diameter of pressure guiding pipe.
In a preferred embodiment of the present utility model, described embedded section is pipe, the arc surface that the bottom surface of groove is.
In a preferred embodiment of the present utility model, described embedded section is the body of square tube or other shapes.
In a preferred embodiment of the present utility model, described through hole is laid on the sidewall of embedded section.
In a preferred embodiment of the present utility model, itself and reactor core upper plate or reactor core support lower plate are connected and fixed by silica gel, epoxy resin, bonding, mechanical interlocking or welding manner by described embedded section.
By adopting pressure reduction point layout structure of the present utility model, in the overall hydraulic simulation test of pressurized water reactor, the liquid of reactor core upper plate and reactor core support lower plate upper and lower surface enters in pressure guiding pipe by through hole on the embedded section sidewall that is embedded in the pressure guiding pipe of correspondence position, then test model is drawn along pressure guiding pipe endoporus, the surveying instrument connected by outside records reactor core upper plate, reactor core support lower plate upper and lower surface respectively with the pressure reduction of reference position, obtain the pressure drop data of reactor critical section, the rationality of in-pile component structural design and the correctness of flow field analysis can be verified preferably.
By through hole on the embedded section sidewall of pressure guiding pipe, can the hydraulic pressure value on average corresponding surface, obtain the average pressure drop of reactor core upper plate and reactor core support lower plate upper and lower surface position.
The utility model is well positioned to meet the requirement of the overall hydraulic simulation test of pressurized water reactor.
The detailed description and obtaining that feature of the present utility model can consult the graphic and following better embodiment of this case is well understood to.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of the overall hydraulic simulation testpieces of pressurized water reactor.
Fig. 2 is that pressure guiding pipe is embedded in the schematic diagram of specifying point position.
Fig. 3 is the schematic diagram of pressure guiding pipe.
Fig. 4 is the schematic diagram of groove.
Wherein, 1, upper-part in-reactor component; 2, bottom in-pile component; 3, reactor core upper plate; 4, reactor core support lower plate; 5, groove; 51, water inlet clearance groove; 61, linkage section; 62, embedded section; 63, through hole.
Embodiment
The technological means realized to make the utility model, creation characteristic, reaching object and effect is easy to understand, setting forth the utility model further below in conjunction with specific embodiment.
See Fig. 1, in the overall hydraulic simulation testpieces of pressurized water reactor, generally include upper-part in-reactor component 1 and bottom in-pile component 2, reactor core upper plate 3 belongs to upper-part in-reactor component, reactor core support lower plate 4 belongs to bottom in-pile component, and these are routine techniques, are not described in detail in this.
See Fig. 2 and 4, offer the groove 5 in order to pre-buried pressure guiding pipe respectively in the upper and lower surface of reactor core upper plate and reactor core support lower plate.
See Fig. 3, pressure guiding pipe comprises linkage section 61 in order to be connected with external measurement devices and in order to be embedded in the embedded section 62 in described groove, the linkage section 61 of pressure guiding pipe is vertical with embedded section 62 (will note guaranteeing that pressure guiding pipe keeps unimpeded at bending part), and detected fluid is drawn out-pile along reactor axial direction and measured by linkage section.In the present embodiment, embedded section is pipe.Certainly, embedded section also can be the body of square tube or other shapes.Recess width is not less than the width of embedded section, the external diameter of embedded section is 4mm, internal diameter is 2mm, the corresponding respectively recess width of reactor core upper plate and reactor core support lower plate upper and lower surface is 6mm, the arc surface of to be Radius be the bottom surface of fluting 3mm, arc surface extreme lower position, apart from corresponding surperficial 5mm, facilitates the pre-buried of pressure guiding pipe and keeps its stability.
It is 2mm through hole (being symmetrical arranged) 63 that the two side of embedded section 62 is in axial direction arranged at intervals with diameter, the perforate direction of through hole 63 be parallel to reactor core upper plate and reactor core support lower plate upper and lower surface and perpendicular to the axis of pressure guiding pipe self.Depth of groove is 0.2:1 ~ 3:1 with the ratio of the equivalent diameter of pressure guiding pipe, and in one of them preferred implementation of the present utility model, the sidewall of groove 5 is provided with the water inlet clearance groove 51 corresponding with the lead to the hole site of embedded section, as shown in Figure 4, the length and width of water inlet clearance groove 51 are respectively 12mm, 3mm and 4.5mm deeply, make fluid enter in pressure guiding pipe smoothly by water inlet clearance groove 51.
Last for the embedded section being embedded in reactor core upper plate and reactor core support lower plate upper and lower surface, by silica gel, epoxy resin, bonding, mechanical interlocking or welding manner, itself and reactor core upper plate or reactor core support lower plate are connected and fixed, but the through hole on embedded section sidewall must not be blocked.
Specific process is as follows:
First complete the processing of pressure guiding pipe as requested, then the groove of reactor core upper plate and reactor core support lower plate upper and lower surface is processed, by having joined the processing of corresponding clearance groove of intaking on plate with pressure guiding pipe, again pressure guiding pipe is respectively installed in the groove of reactor core upper plate and reactor core support lower plate upper and lower surface, finally fix pressure guiding pipe with silica gel or epoxy resin, note not blocking perforate on pressure guiding pipe sidewall.
In the overall hydraulic simulation test of pressurized water reactor, the liquid of reactor core upper plate and reactor core support lower plate upper and lower surface enters in pressure guiding pipe by perforate on the sidewall that is embedded in the pressure guiding pipe of correspondence position, then test model is drawn along pressure guiding pipe endoporus, the surveying instrument connected by outside record reactor core upper plate, reactor core support lower plate upper and lower surface respectively with the pressure reduction of reference position, obtain the pressure drop data of reactor critical section, the rationality of in-pile component structural design and the correctness of flow field analysis can be verified preferably.The utility model can obtain the average pressure drop of reactor core upper plate and reactor core support lower plate upper and lower surface position.Be well positioned to meet the requirement of the overall hydraulic simulation test of pressurized water reactor.
More than show and describe ultimate principle of the present utility model, principal character and advantage of the present utility model.The technician of the industry should understand; the utility model is not restricted to the described embodiments; the just principle of the present utility model described in above-described embodiment and instructions; under the prerequisite not departing from the utility model spirit and scope, the utility model also has various changes and modifications, and these changes and improvements all fall in claimed scope of the present utility model.The protection domain that the utility model requires is defined by appending claims and equivalent thereof.
Claims (8)
1. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor, it is characterized in that, the groove in order to pre-buried pressure guiding pipe is offered respectively in the upper and lower surface of reactor core upper plate and reactor core support lower plate, described pressure guiding pipe comprises linkage section in order to be connected with external measurement devices and in order to be embedded in the embedded section in described groove, the sidewall of described embedded section is in axial direction arranged at intervals with through hole, the perforate direction of through hole be parallel to reactor core upper plate and reactor core support lower plate upper and lower surface and perpendicular to the axis of pressure guiding pipe self; The sidewall of described groove is provided with the water inlet clearance groove corresponding with the lead to the hole site of embedded section.
2. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, detected fluid is drawn out-pile along reactor axial direction and is measured by linkage section.
3. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, the width of described groove is not less than the width of embedded section.
4. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, described depth of groove is 0.2:1 ~ 3:1 with the ratio of the equivalent diameter of pressure guiding pipe.
5. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, described embedded section is pipe, the arc surface that the bottom surface of groove is.
6. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, described embedded section is the body of square tube or other shapes.
7. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, described through hole is laid on the sidewall of embedded section.
8. the pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor according to claim 1, it is characterized in that, itself and reactor core upper plate or reactor core support lower plate are connected and fixed by silica gel, epoxy resin, bonding, mechanical interlocking or welding manner by described embedded section.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420744490.1U CN204496935U (en) | 2014-12-01 | 2014-12-01 | Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420744490.1U CN204496935U (en) | 2014-12-01 | 2014-12-01 | Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor |
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| Publication Number | Publication Date |
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| CN204496935U true CN204496935U (en) | 2015-07-22 |
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| CN201420744490.1U Active CN204496935U (en) | 2014-12-01 | 2014-12-01 | Pressure reduction point layout structure in the overall hydraulic simulation test of pressurized water reactor |
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| Date | Code | Title | Description |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder |
Address after: 200233 Shanghai city Xuhui District Hong Cao Road No. 29 Patentee after: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. Address before: 200233 Shanghai city Xuhui District Hong Cao Road No. 29 Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
|
| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
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| CP01 | Change in the name or title of a patent holder |