CN103400613B - The transverse direction stream test unit of nuclear power plant's drive wire cold test and test method - Google Patents
The transverse direction stream test unit of nuclear power plant's drive wire cold test and test method Download PDFInfo
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- CN103400613B CN103400613B CN201310327179.7A CN201310327179A CN103400613B CN 103400613 B CN103400613 B CN 103400613B CN 201310327179 A CN201310327179 A CN 201310327179A CN 103400613 B CN103400613 B CN 103400613B
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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
Abstract
The invention discloses transverse direction stream test unit and the test method of a kind of nuclear power plant drive wire cold test, wherein, the transverse direction that comprises test unit flows restrictor, the adapter of horizontal inflow entrance and discharge connection, laterally stream restrictor is removably disposed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, and horizontal inflow entrance adapter is stretched into through pressure vessel top cylindrical shell and laterally flowed in restrictor.The present invention, by arranging the detachable transverse direction stream restrictor changed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, makes laterally stream flowing more tally with the actual situation; Again by changing the transverse direction stream restrictor of different structure, can need to measure the laterally impact of stream on C&P systems rod drop time according to difference, making to optimize drive wire design by test findings becomes possibility.
Description
Technical field
The present invention relates to nuclear power plant's reactor control rod drive wire cold test, more particularly, the present invention relates to a kind of transverse direction stream test unit and test method of drive wire cold test.
Background technology
In nuclear power plant, the reactive change of reactor core is controlled by reactor control rod drive wire, specifically utilize the control rod drive mechanisms (CRD) being arranged in reactor pressure vessel top to drive C&P systems to move up and down at heap in-core by driving stem, control the reactive Rapid Variable Design of reactor core.Reactor control rod drive wire regulates reactor capability when normal operation, and under accident conditions, then introduce negative reactivity fast, be reactor emergency shut-down, guarantees the important guarantee that nuclear power plant's reactor safety is run.Therefore, need when reactor designs to verify by drive wire cold test the reliability that drive wire designs.
Control rod drive line cold test mainly measures the rod drop time of C&P systems under different operating mode, to determine the improvement project of each parts on drive wire according to this, cold test content comprises: hydrostatic, dynamic water Rod drop test; Coolant flow change test; Wrong alignment test; Laterally stream test etc.Wherein, laterally stream test is one of important tests content of reactor control rod drive wire cold test, and it can the flow characteristics of analogue enlargement rod guide cylinder bottom coohng agent, and then the checking laterally impact of stream on C&P systems rod drop time in upper chamber.Refer to the line cold test device shown in Fig. 1, the test of existing laterally stream arranges a horizontal inflow entrance adapter 12 and a discharge connection 14 on top cylindrical shell 10 wall of pressure vessel.Wherein, horizontal inflow entrance adapter 12 is positioned at the exit of fuel assembly fluid, and its position is higher than reactor core upper plate 16, and the insertion depth of the mouth of pipe makes it not contact with guide assembly 18.But, use above-mentioned laterally stream test unit to have following defect: 1) most of horizontal stream can not in ramp metering rod guide assembly 18, therefore can not simulate for lateral stream on the impact of rod drop time; 2) laterally streamed single, the cooling medium can not simulating diverse location place of upper chamber laterally flows flow characteristics.
In view of this, necessaryly provide a kind of and can simulate the flowing of multiple laterally stream to the transverse direction stream test unit of C&P systems rod drop time impact and test method.
Summary of the invention
The object of the invention is to: provide a kind of and can simulate the flowing of multiple laterally stream to the transverse direction stream test unit of C&P systems rod drop time impact and test method, so that optimize drive wire design by test findings.
In order to realize foregoing invention object, the invention provides the transverse direction stream test unit of a kind of nuclear power plant drive wire cold test, it comprises transverse direction and flows restrictor, the adapter of horizontal inflow entrance and discharge connection, laterally stream restrictor is removably disposed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, and horizontal inflow entrance adapter is stretched into through pressure vessel top cylindrical shell and laterally flowed in restrictor.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, and described laterally stream restrictor is hollow cylindrical, and on sidewall, offer the mounting hole of two positional symmetry.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, described laterally stream restrictor is hollow cylindrical, and be divided into two arch sections because of the vertical through hole offering two positional symmetry on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, and described laterally stream restrictor is hollow cylindrical, and on sidewall, do not establish fluid perforate.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, the hollow tubular structure of described laterally stream restrictor to be xsect be regular polygon, and on sidewall, do not establish fluid perforate.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, and described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure, and be divided into small one and large one two arch sections because offering a vertical through hole on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, and be removably fastened on reactor core upper plate by bolt bottom described laterally stream restrictor, overhead height is higher than the position of control rod guide tubes and bundles upper window.
One as the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test is improved, and described horizontal inflow entrance adapter is positioned at the exit of fuel assembly fluid, and the outside wall surface of its front end and control rod guide tubes and bundles remains with certain interval.
In order to realize foregoing invention object, present invention also offers the transverse direction stream test method of a kind of nuclear power plant drive wire cold test, the transverse direction that comprises the transverse direction stream test unit that it adopts flows restrictor, the adapter of horizontal inflow entrance and discharge connection, laterally stream restrictor is removably disposed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, and horizontal inflow entrance adapter is stretched into through pressure vessel top cylindrical shell and laterally flowed in restrictor; Described test method is that the mode by changing laterally stream restrictor simulates the cooling medium horizontal stream flow characteristics at diverse location place of upper chamber to the impact of C&P systems rod drop time.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and it utilizes the impact on rod drop time when laterally flowing restrictor simulation upper chamber segment fluid flow ramp metering rod guide cylinder; Described laterally stream restrictor is hollow cylindrical, and on sidewall, offer the mounting hole of two positional symmetry.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and its utilization horizontal stream restrictor simulation upper chamber flows into transverse direction stream flowing during maximum flow in control rod guide tubes and bundles; Described laterally stream restrictor is hollow cylindrical, and is divided into two arch sections because of the vertical through hole offering two positional symmetry on sidewall, and laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, when it utilizes the horizontal control rod guide tubes and bundles flowed in restrictor simulation upper chamber to be surrounded by other guide cylinder that surrounding is adjacent, the flowing of laterally flowing when being maximized restriction; Described laterally stream restrictor is hollow cylindrical, and on sidewall, do not establish fluid perforate.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, when it utilizes the horizontal control rod guide tubes and bundles flowed in restrictor simulation upper chamber to be surrounded by other guide cylinder that surrounding is adjacent, the flowing of laterally flowing when being maximized restriction; The hollow tubular structure of described laterally stream restrictor to be xsect be regular polygon, and on sidewall, do not establish fluid perforate.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and it utilizes the transverse direction stream flowing being arranged on the control rod guide tubes and bundles surrounding fluid near reactor pressure vessel discharge connection in laterally stream restrictor simulation upper chamber; Described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and the transverse direction stream in its guide cylinder utilizing the fluid in laterally stream restrictor simulation upper chamber in control rod guide tubes and bundles to flow into the flowing of the one side of guide cylinder window and the fluid section that flows out in guide cylinder around other to be completely adjacent flows; Described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure, and be divided into small one and large one two arch sections because offering a vertical through hole on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and be removably fastened on reactor core upper plate by bolt bottom described laterally stream restrictor, overhead height is higher than the position of control rod guide tubes and bundles upper window.
One as the transverse direction stream test method of nuclear power plant of the present invention drive wire cold test is improved, and described horizontal inflow entrance adapter is positioned at the exit of fuel assembly fluid, and the outside wall surface of its front end and control rod guide tubes and bundles remains with certain interval.
Compared with prior art, the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test, by arranging the detachable transverse direction stream restrictor changed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, makes laterally stream flowing more tally with the actual situation; Again by changing the transverse direction stream restrictor of different structure, can need to measure the laterally impact of stream on C&P systems rod drop time according to difference, making to optimize drive wire design by test findings becomes possibility.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test, test method and beneficial effect thereof are described in detail, wherein:
Fig. 1 is the structural representation of existing nuclear power plant drive wire line cold test device.
Fig. 2 is the structural representation of the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test.
Fig. 3 is the structural representation that the present invention laterally flows restrictor first embodiment.
Fig. 4 is the structural representation that the present invention laterally flows restrictor second embodiment.
Fig. 5 is the structural representation that the present invention laterally flows restrictor the 3rd embodiment.
Fig. 6 is the structural representation that the present invention laterally flows restrictor the 4th embodiment.
Fig. 7 is the structural representation that the present invention laterally flows restrictor the 5th embodiment.
Fig. 8 is the structural representation that the present invention laterally flows restrictor the 6th embodiment.
Embodiment
In order to make goal of the invention of the present invention, technical scheme and Advantageous Effects thereof more clear, below in conjunction with the drawings and specific embodiments, the present invention is further elaborated.Should be understood that, the embodiment described in this instructions is only used to explain the present invention, is not intended to limit the present invention.
Refer to Fig. 2, the transverse direction stream test unit of nuclear power plant of the present invention drive wire cold test comprises laterally stream restrictor 20, horizontal inflow entrance adapter 22 and discharge connection (not shown).
Laterally stream restrictor 20 is arranged between pressure vessel top cylindrical shell 30 and control rod guide tubes and bundles (not shown), removably be fastened on reactor core upper plate 36 by bolt 34 bottom it, overhead height is higher than the position of control rod guide tubes and bundles upper window.
Horizontal inflow entrance adapter 22 is positioned at the exit of fuel assembly fluid, it stretches into through pressure vessel top cylindrical shell 30 and laterally flows in restrictor 20, the outside wall surface of front end and control rod guide tubes and bundles remains with certain interval, and gap width draws by carrying out fluid mechanics numerical simulation calculation to drive wire body.
The position of discharge connection is identical with actual response core pressure vessel discharge connection position, repeats no more herein.
In order to the limiting condition of cooling medium cross flow in mock-up reactor upper chamber, by carrying out Three-Dimensional Flow Field Analysis to the flow field characteristic of cooling medium in upper chamber, obtain the flow characteristics that cooling medium laterally flows in upper chamber, the present invention devises the transverse direction stream restrictor of following various structures, carries out selecting and changing for during test.
Refer to Fig. 3, for the present invention laterally flows the structural representation of restrictor first embodiment.This transverse direction stream restrictor 20a is hollow cylindrical, and on sidewall, offer the mounting hole 26a of two positional symmetry, the impact on rod drop time when it is for simulating upper chamber's segment fluid flow ramp metering rod guide cylinder.
Refer to Fig. 4, for the present invention laterally flows the structural representation of restrictor second embodiment.This transverse direction stream restrictor 20b is hollow cylindrical, and is divided into two arch sections because of the vertical through hole 26b offering two positional symmetry on sidewall, and laterally the sidewall of stream restrictor 20b outwards bends at vertical through hole 26b place and forms flanging 28b.Laterally stream restrictor 20b is for simulating transverse direction stream flowing when upper chamber flows into maximum flow in control rod guide tubes and bundles.
Refer to Fig. 5, for the present invention laterally flows the structural representation of restrictor the 3rd embodiment.This transverse direction stream restrictor 20c is hollow cylindrical, and on sidewall, do not establish fluid perforate.
Refer to Fig. 6, for the present invention laterally flows the structural representation of restrictor the 4th embodiment.The tubular structure of this transverse direction stream restrictor 20d to be xsect be octagon, and on sidewall, do not establish fluid perforate.In other embodiments, laterally the xsect of stream restrictor also can be other regular polygons.
When transverse direction stream restrictor 20c, 20d of third and fourth embodiment are surrounded by other guide cylinder that surrounding is adjacent for the control rod guide tubes and bundles of simulating in upper chamber, laterally flow the flowing of flowing when being maximized restriction.According to differential responses heap heap-type choose the fuel assembly of different structure and C&P systems carry out drive wire test time, need to choose transverse direction stream restrictor 20c, the 20d with varying cross-section and carry out horizontal flow field simulation.
Refer to Fig. 7, for the present invention laterally flows the structural representation of restrictor the 5th embodiment.This transverse direction stream restrictor 20e is xsect is semicircular semi-circular cylindrical structure, and it is for simulating in upper chamber the transverse direction stream flowing of the control rod guide tubes and bundles surrounding fluid be arranged near reactor pressure vessel discharge connection.
Refer to Fig. 8, for the present invention laterally flows the structural representation of restrictor the 6th embodiment.This transverse direction stream restrictor 20f is xsect is semicircular semi-circular cylindrical structure, and be divided into small one and large one two arch sections because offering a vertical through hole 26f on sidewall, laterally the sidewall of stream restrictor 20f outwards bends at vertical through hole 26f place and forms flanging 28f.Laterally stream restrictor 20f flows for the transverse direction stream of simulating fluid in upper chamber in control rod guide tubes and bundles and flowing into the flowing of the one side of guide cylinder window and the fluid section that flows out in guide cylinder around other completely in the guide cylinder that is adjacent.
Known by describing above, the present invention, by arranging the detachable transverse direction stream restrictor 20 changed between pressure vessel top cylindrical shell 30 and control rod guide tubes and bundles, makes laterally stream flowing more tally with the actual situation; Again by changing the transverse direction stream restrictor 20a-20f of different structure, can need to measure the laterally impact of stream on C&P systems rod drop time according to difference, making to optimize drive wire design by test findings becomes possibility.In addition, the structure that the present invention laterally flows test unit is simple, has the advantage that use operation is reliable, be easy to popularization.
The announcement of book and instruction according to the above description, those skilled in the art in the invention can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, the present invention is not limited to embodiment disclosed and described above, also should fall in the protection domain of claim of the present invention modifications and changes more of the present invention.In addition, although employ some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the present invention.
Claims (18)
1. the transverse direction stream test unit of nuclear power plant's drive wire cold test, it is characterized in that: comprise and laterally flow restrictor, the adapter of horizontal inflow entrance and discharge connection, laterally stream restrictor is removably disposed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, and horizontal inflow entrance adapter is stretched into through pressure vessel top cylindrical shell and laterally flowed in restrictor.
2. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, is characterized in that: described laterally stream restrictor is hollow cylindrical, and on sidewall, offer the mounting hole of two positional symmetry.
3. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, it is characterized in that: described laterally stream restrictor is hollow cylindrical, and be divided into two arch sections because of the vertical through hole offering two positional symmetry on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
4. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, is characterized in that: described laterally stream restrictor is hollow cylindrical, and on sidewall, do not establish fluid perforate.
5. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, is characterized in that: the hollow tubular structure of described laterally stream restrictor to be xsect be regular polygon, and on sidewall, do not establish fluid perforate.
6. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, is characterized in that: described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure.
7. the transverse direction stream test unit of nuclear power plant according to claim 1 drive wire cold test, it is characterized in that: described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure, and be divided into small one and large one two arch sections because offering a vertical through hole on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
8. the transverse direction stream test unit of nuclear power plant according to any one of claim 1 to 7 drive wire cold test, it is characterized in that: be removably fastened on reactor core upper plate by bolt bottom described laterally stream restrictor, overhead height is higher than the position of control rod guide tubes and bundles upper window.
9. the transverse direction stream test unit of nuclear power plant according to any one of claim 1 to 7 drive wire cold test, it is characterized in that: described horizontal inflow entrance adapter is positioned at the exit of fuel assembly fluid, and the outside wall surface of its front end and control rod guide tubes and bundles remains with certain interval.
10. the transverse direction stream test method of nuclear power plant's drive wire cold test, it is characterized in that: the transverse direction stream test unit that test adopts comprises transverse direction and flows restrictor, the adapter of horizontal inflow entrance and discharge connection, laterally stream restrictor is removably disposed between pressure vessel top cylindrical shell and control rod guide tubes and bundles, and horizontal inflow entrance adapter is stretched into through pressure vessel top cylindrical shell and laterally flowed in restrictor; Described test method is that the mode by changing laterally stream restrictor simulates the cooling medium horizontal stream flow characteristics at diverse location place of upper chamber to the impact of C&P systems rod drop time.
The transverse direction stream test method of 11. nuclear power plant according to claim 10 drive wire cold tests, is characterized in that: utilize the impact on rod drop time when laterally flowing restrictor simulation upper chamber segment fluid flow ramp metering rod guide cylinder; Described laterally stream restrictor is hollow cylindrical, and on sidewall, offer the mounting hole of two positional symmetry.
The transverse direction stream test method of 12. nuclear power plant according to claim 10 drive wire cold tests, is characterized in that: utilization horizontal stream restrictor simulation upper chamber flows into transverse direction stream flowing during maximum flow in control rod guide tubes and bundles; Described laterally stream restrictor is hollow cylindrical, and is divided into two arch sections because of the vertical through hole offering two positional symmetry on sidewall, and laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
The transverse direction stream test method of 13. nuclear power plant according to claim 10 drive wire cold tests, it is characterized in that: when utilizing the horizontal control rod guide tubes and bundles flowed in restrictor simulation upper chamber to be surrounded by other guide cylinder that surrounding is adjacent, the flowing of laterally flowing when being maximized restriction; Described laterally stream restrictor is hollow cylindrical, and on sidewall, do not establish fluid perforate.
The transverse direction stream test method of 14. nuclear power plant according to claim 10 drive wire cold tests, it is characterized in that: when utilizing the horizontal control rod guide tubes and bundles flowed in restrictor simulation upper chamber to be surrounded by other guide cylinder that surrounding is adjacent, the flowing of laterally flowing when being maximized restriction; The hollow tubular structure of described laterally stream restrictor to be xsect be regular polygon, and on sidewall, do not establish fluid perforate.
The transverse direction stream test method of 15. nuclear power plant according to claim 10 drive wire cold tests, is characterized in that: utilize the transverse direction stream flowing being arranged on the control rod guide tubes and bundles surrounding fluid near reactor pressure vessel discharge connection in laterally stream restrictor simulation upper chamber; Described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure.
The transverse direction stream test method of 16. nuclear power plant according to claim 10 drive wire cold tests, is characterized in that: the transverse direction stream in the guide cylinder utilizing the fluid in laterally stream restrictor simulation upper chamber in control rod guide tubes and bundles to flow into the flowing of the one side of guide cylinder window and the fluid section that flows out in guide cylinder around other to be completely adjacent flows; Described laterally stream restrictor is xsect is semicircular semi-circular cylindrical structure, and be divided into small one and large one two arch sections because offering a vertical through hole on sidewall, laterally the sidewall of stream restrictor outwards bends at vertical through hole place and forms flanging.
17. according to claim 10 to the transverse direction stream test method of the nuclear power plant's drive wire cold test according to any one of 16, it is characterized in that: be removably fastened on reactor core upper plate by bolt bottom described laterally stream restrictor, overhead height is higher than the position of control rod guide tubes and bundles upper window.
18. according to claim 10 to the transverse direction stream test method of the nuclear power plant's drive wire cold test according to any one of 16, it is characterized in that: described horizontal inflow entrance adapter is positioned at the exit of fuel assembly fluid, and the outside wall surface of its front end and control rod guide tubes and bundles remains with certain interval.
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Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN103714736B (en) * | 2013-12-31 | 2016-01-20 | 中国核动力研究设计院 | Presurized water reactor drive wire line cold test device |
| CN105632573A (en) * | 2016-01-08 | 2016-06-01 | 上海核工程研究设计院 | Acquiring and processing system for reactor control rod drive wire test data |
| CN105702304A (en) * | 2016-01-08 | 2016-06-22 | 上海核工程研究设计院 | Reactor control rod drive line comprehensive performance testing and verifying device |
| CN106653116A (en) * | 2017-01-11 | 2017-05-10 | 中国核动力研究设计院 | Pressure bearing vessel suitable for out-of-pile test of reversely inserted drive wire |
| CN110600143B (en) * | 2019-09-19 | 2021-07-20 | 中国核动力研究设计院 | Inlet flow channel assembly for stably fixing rod bundles |
| CN111028640B (en) * | 2019-11-11 | 2021-10-29 | 中广核研究院有限公司 | Thermal state test device for control rod drive wire and centering method thereof |
| CN112530612A (en) * | 2020-11-27 | 2021-03-19 | 中广核研究院有限公司 | Hydraulic simulator of control rod guide cylinder assembly |
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| JPH0815480A (en) * | 1994-07-01 | 1996-01-19 | Shikoku Sogo Kenkyusho:Kk | Computing method of time of drop of control rod of reactor |
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