CN107195341A - The on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop - Google Patents

The on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop Download PDF

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Publication number
CN107195341A
CN107195341A CN201710347729.XA CN201710347729A CN107195341A CN 107195341 A CN107195341 A CN 107195341A CN 201710347729 A CN201710347729 A CN 201710347729A CN 107195341 A CN107195341 A CN 107195341A
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China
Prior art keywords
fuel assembly
water tank
power plant
nuclear power
test section
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Pending
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CN201710347729.XA
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Chinese (zh)
Inventor
牛风雷
卓卫乾
郭张鹏
王达
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North China Electric Power University
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North China Electric Power University
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Priority to CN201710347729.XA priority Critical patent/CN107195341A/en
Publication of CN107195341A publication Critical patent/CN107195341A/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses the on-line monitoring device that a kind of nuclear power plant containment shell fragment for belonging to nuclear safety technical field influences on fuel assembly pressure drop.The on-line monitoring device includes test section, full-scale fuel assembly, armoured thermocouple, difference gauge, the electric V-shaped ball valve of pressure gauge and flowmeter, mixes water tank.Containment sump filter screen is passed through into this phenomenon of reactor pressure vessel by simulating fragment after PWR nuclear power plant accident, the measuring instrumentss such as temperature sensor, pressure sensor, differential pressure pick-up, flowmeter are comprehensively utilized, different working conditions and the corresponding fuel assembly pressure drop of amount of debris is monitored on-line.By monitoring the operation of this device during experiment, distribution, attachment and stopping state of the fragment in fuel assembly can be studied, influence of the fragment to fuel assembly pressure drop in containment after quantitative evaluation PWR nuclear power plant LOCA accident, to ensure that the reliable execution of PWR nuclear power plant emergence core stacking cool system security function provides support.

Description

The on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop
Technical field
The invention belongs to nuclear safety technical field, more particularly to a kind of nuclear power plant containment shell fragment is to fuel assembly pressure drop shadow Loud on-line monitoring device.Imaginary loss of-coolant accident (LOCA) (LOCA) containment afterwards occurs for the main simulation pressurized-water reactor nuclear power plant that can operate with The influence produced after fragment incoming fuel component to its pressure drop.
Background technology
Occur imaginary loss of-coolant accident (LOCA) (LOCA) in pressurized-water reactor nuclear power plant and recycle the stage (LTCC) afterwards, because cut is torn Split, the effect such as the injection of HTHP current and the corrosion of material or dissolving, there may be a large amount of fragments in containment.These Fragment, including some impurity, mud, the foreign matters just accumulated originally in containment etc., due to current in containment after accident Migration, will enter containment sump, although fragment can be trapped by melt pit filter screen, but will have partial piece peace capable of bypass Full shell melt pit filter screen enters primary Ioops system, and assembles and deposit in reactor fuel component, causes fuel assembly pressure drop increase. Domestic and international correlative study present situation shows that safe operation of the phenomenon to nuclear power plant LTCC is most important, therefore, after simulation LOCA In the case that the fragment produced in LTCC stages, containment enters pressure vessel, on-line monitoring difference fragment is in different flow It is necessary to descend the size of caused reactor fuel component pressure drop and quantify the relation obtained between them.
The content of the invention
It is an object of the invention to provide the on-line monitoring dress that a kind of nuclear power plant containment shell fragment influences on fuel assembly pressure drop Put, it is characterised in that the device is to load full-scale fuel assembly 2 armouring under the bottom insertion of test section 1 in test section 1 Armoured thermocouple 7, the upper armoured thermocouple 8 of top insertion in thermocouple 6, middle part insertion, two ends difference gauge 5 is with test section about 1 End connection, top difference gauge 4 is connected with the middle end of upper section of test section 1, and bottom difference gauge 3 is connected with the middle lower end of test section 1;Test section 1 top and first pressure meter 10, the 21st electric V-shaped ball valve and flow meter 11, mix water tank 14 and connect;The bottom of test section 1 with Second pressure meter 9, flow down gauge 12, frequency conversion centrifugal pump 13, the 20th electric V-shaped ball valve and mix the lower end of water tank 14 series connection;22nd Electric V-shaped ball valve two ends export and flow down with flow meter 11 respectively gauge 12 outlet be connected;The upper end of 20th electric V-shaped ball valve It is connected lower end connection DN65 stainless steel tubes 25 with the 24th electric V-shaped ball valve, the DN65 stainless steel tubes 25 are from mixing in water tank 14 Portion is accessed, and is turned under in insertion heating coil 15;The public affairs of 23rd electric V-shaped ball valve and second pressure meter 9 and dirty gauge 12 Conode is connected;Flood pattern 17 is connected by water injection valve 19 with mixing the top of water tank 14, and stirring motor 16, which is fixed on, mixes water The top of case 14;Heating coil 15, which is fixed on, mixes the middle and lower part of water tank 14, and is connected with temperature control system 18;
The top for mixing water tank by tank wall nearby 4 positions insertion 14-2 armoured thermocouples, 14-3 armoured thermocouples, 14-4 armoured thermocouples and 14-5 armoured thermocouples;Mix faced the wall and meditated on the outside of water tank on fix vertical bar and mix water tank observation window 14-1。
The heating coil includes 4 coils, and interval, which is fixed on, mixes the middle part of water tank 14;
With each fixed impeller 16-2 in top in the middle part of the motor shaft 16-1 of the stirring motor;Two impellers are respectively at 4 Below the midfeather of coil and minimum coil.
The test section is made up of steel housing body and visual window 1-1;The upper low head of test section is the face of cylinder, is prevented Because the mutation in section forms whirlpool after water inflow;Test section has A, B, C, D four sides:A faces are whole steel sheet, arrange 6 sensors Meet hole 1-3-1~1-3-6;B, C, D face set dismountable visual window 1-1, on the one hand meet visualization requirement, on the other hand convenient Clear up the experiment fragment deposited on full-scale fuel assembly 2.
The aperture that 6 sensors of the arrangement connect hole is φ 10;Two ends difference gauge is connect by the transparent hoses for connecing hole of φ 10 5th, top difference gauge 4 and bottom difference gauge 3;Hole is connect by φ 10 screw thread and meets lower armoured thermocouple 6, the and of middle armoured thermocouple 7 Upper armoured thermocouple 8.
The beneficial effects of the invention are as follows preventing fragment from being precipitated in water tank bottom, prevent experiment from blocking;Using pressure gauge, Differential pressure pickup, temperature sensor, flowmeter, are acquired to pressure, pressure drop, temperature, flow and are converted into standard letter respectively Number, by change its signal is handled after come out by host computer Real time displaying, realize on-line monitoring.
Brief description of the drawings
Fig. 1 is the on-line monitoring device structural representation of nuclear plant safety.
Fig. 2 is test section structural representation, wherein, a is test section stereogram;B is A faces schematic diagram, and c is full-scale fuel Component profile;D is E-E profiles;E is test section F portions enlarged drawing.
Fig. 3 is to mix cisten mechanism schematic diagram, wherein, a is front view, and b is top view.
Fig. 4 is monitoring system principle schematic
Label in figure
1- test sections;1-1- visual windows;1-2- fuel assembly support columns;1-3-1~1-3-6- sensors connect hole;1-4- determines Position block;1-5- hollow support plates;The full-scale fuel assemblies of 2-;3- difference gauges;4- difference gauges;5- difference gauges;6- armoured thermocouples; 7- armoured thermocouples;8- armoured thermocouples;9- pressure gauges;10- pressure gauges;11- flowmeters;12- flowmeters;13- frequency conversions are centrifuged Pump;14- mixes water tank;14-1- mixes water tank observation window;14-2- armoured thermocouples;14-3- armoured thermocouples;14-4- armourings Thermocouple;14-5- armoured thermocouples;15- heating coils;16- stirring motors;16-1- motor shafts;16-2- impellers;17- water fillings System;18- temperature control systems;19- water injection valves;The electric V-shaped ball valves of 20-;The electric V-shaped ball valves of 21-;The electric V-shaped ball valves of 22-;23- electricity Dynamic V-type ball valve;The electric V-shaped ball valves of 24-;25-DN65 stainless steel tubes
Embodiment
The present invention provides the on-line monitoring device that a kind of nuclear power plant containment shell fragment influences on fuel assembly pressure drop, ties below Accompanying drawing is closed to be explained.
Fig. 1 show the on-line monitoring device structural representation of nuclear plant safety.On-line monitoring device shown in figure be Load full-scale fuel assembly 2 in test section 1;The armouring in armoured thermocouple 6, middle part insertion under the bottom insertion of test section 1 Thermocouple 7, the upper armoured thermocouple 8 of top insertion, two ends difference gauge 5 are connected with the upper and lower side of test section 1, top difference gauge 4 and examination The connection of the middle end of upper section of section 1 is tested, bottom difference gauge 3 is connected with the middle lower end of test section 1;The top of test section 1 and first pressure meter 10, the 21 electric V-shaped ball valves and flow meter 11, mix water tank 14 and connect;The bottom of test section 1 and second pressure meter 9, the gauge 12 that flows down, Frequency conversion centrifugal pump 13, the 20th electric V-shaped ball valve and mix the lower end of water tank 14 series connection;22nd electric V-shaped ball valve two ends respectively with it is upper Flowmeter 11 export and flow down the entrance of gauge 12 connection;The upper end of 20th electric V-shaped ball valve is connected down with the 24th electric V-shaped ball valve End connection DN65 stainless steel tubes 25, the DN65 stainless steel tubes 25 are accessed from the middle and upper part of water tank 14 is mixed, and are turned under insertion heating In coil 15;23rd electric V-shaped ball valve is connected with the common node of second pressure meter 9 and dirty gauge 12;Flood pattern 17 is led to Cross water injection valve 19 and be connected with mixing the top of water tank 14, stirring motor 16, which is fixed on, mixes the top of water tank 14;Heating coil 15 is fixed The middle and lower part of water tank 14 is being mixed, and is being connected with temperature control system 18;
Fig. 2 show test section structural representation.The test section is made up of steel housing body and visual window 1-1;Examination The upper low head for testing section is the face of cylinder, prevents water after flowing into because the mutation in section forms whirlpool;Test section has A, B, C, D tetra- Face:A faces are that (it is test section stereogram that Fig. 2 includes a to whole steel sheet;B is A faces schematic diagram, and c is full-scale fuel assembly profile;d For E-E profiles;E is test section F portions enlarged drawing), wherein, a is test section stereogram;B is A faces schematic diagram, and 6 are arranged thereon Sensor meets hole 1-3-1~1-3-6;B, C, D face set dismountable visual window 1-1, on the one hand meet visualization requirement, the opposing party The experiment fragment that face easy cleaning is deposited on full-scale fuel assembly 2.C is full-scale fuel assembly profile, full-scale fuel The critical piece of component 2 has:Upper base 2-1, fuel assembly skeleton 2-2, fuel bundle group 2-3, grid spacer 2-4, bottom nozzle 2-5.Fuel assembly skeleton 2-2 runs through fuel bundle group 2-3 and grid spacer 2-4, the upper base 2-1 of its upper end connection, and lower end connects Meet bottom nozzle 2-5.Positioned, determined at upper base 2-1 by four pieces of locating piece 1-4 by four support column 1-2 at bottom nozzle 2-5 Position.The aperture that 6 sensors of the arrangement connect hole is φ 10;Two ends difference gauge 5, top are connect by the transparent hoses for connecing hole of φ 10 Difference gauge 4 and bottom difference gauge 3;Hole is connect by φ 10 screw thread and connects lower armoured thermocouple 6, middle armoured thermocouple 7 and upper armouring Thermocouple 8;Connect hole numbering and respective sensor or sensor interface is as shown in the table:
Fig. 3, which is shown, mixes cisten mechanism schematic diagram, wherein, a is front view, and b is top view.The top for mixing water tank By tank wall, nearby 14-2 armoured thermocouples, 14-3 armoured thermocouples, 14-4 armoured thermocouples and 14-5 armourings are inserted in 4 positions in portion Thermocouple;Mix faced the wall and meditated on the outside of water tank on fix vertical bar and mix water tank observation window 14-1.Heating coil includes 4 coils, Interval, which is fixed on, mixes the middle part of water tank 14;With each fixed impeller 16-2 in top in the middle part of the motor shaft 16-1 of stirring motor;Two leaves Wheel is respectively at below the midfeather of 4 coils and minimum coil.
Fig. 4 show monitoring system principle schematic;Explained with reference to above three figure, illustrate to monitor principle.Pressure difference Count (two ends difference gauge 5, top difference gauge 4 and bottom difference gauge 3), pressure gauge (first pressure meter 10 and second pressure meter 19), Flowmeter (flow meter 11 and dirty gauge 12), thermocouple (lower armoured thermocouple 6, middle part insertion in armoured thermocouple 7, on The upper armoured thermocouple 8 of portion's insertion, 14-2 armoured thermocouples, 14-3 armoured thermocouples, 14-4 armoured thermocouples and 14-5 armourings heat Galvanic couple), electrically operated valve (the electric V-shaped ball valves of 19-, the electric V-shaped ball valves of 20-, the electric V-shaped ball valves of 21-, the electric V-shaped ball valves of 22-, The electric V-shaped balls of 23- and the electric V-shaped ball valves of 24-), sensor or the equipment outputting standard electric signal such as variable frequency pump and water tank electrical heating To online monitoring system (controller, host computer), controller (controller 1, controller 2) is led to host computer by 485 connections News, host computer completes the function of monitoring and control.Host computer monitoring refers to that, by receiving the signal of controller 1, host computer is to letter Number it is read out, while being converted into readable thermal parameter, is shown in the monitoring interface such as Fig. 1, while carries out backstage storage; Then by receiving the signal of controller 2, host computer by intuitively equipment state after signal transacting to including the monitoring in such as Fig. 1 In interface, the modification and operation of parameter are carried out by mouse and keyboard, so as to realize the logic control to system, what is controlled is dynamic Make to include the switch control of electrically operated valve, rotating speed (flow) control of variable frequency pump and water tank electric heating control.
Test loop operation principle:Load full-scale fuel assembly 2 in test section 1, pass through note in water tank 14 is mixed Water system 17 (need to coordinate opening water injection valve 19) injection testing institute water requirement, may make up a test loop.During test run, the 20 electric V-shaped ball valves and the 21st electric V-shaped ball valve are opened, and the 22nd electric V-shaped ball valve, the 23rd electric V-shaped ball and the 24th are electric V-shaped Ball valve is closed.Water is from the outflow of the lower end of water tank 14 is mixed, and it is electric V-shaped to sequentially pass through the 20th under the driving effect of frequency conversion centrifugal pump 13 Enter test section 1 after ball valve, frequency conversion centrifugal pump 13, flow down gauge 12 and second pressure meter 9, pass through first pressure meter after outflow again 10, the 21st electric V-shaped ball valve and flow meter 11, is then back to mixed water tank 14.
When test loop because debugging needs, when only carrying out draining to test section 1, the 23rd electric V-shaped ball valve and the 21st electronic V Type ball valve is opened, and other valves are closed.When mixed water tank 14 needs draining, the 24th electric V-shaped ball valve is opened, and other valves are closed Close.If being blocked during testing, the 22nd electric V-shaped ball valve is opened.
Mix needs to add experiment fragment during injecting a certain amount of water, experiment in water tank 14.Stirring motor 16 is opened, passes through electricity Arbor 16-1 impellers rotate 16-2, are that fragment provides in water and mixes power, and allowing mix can form uniformly in water tank 14 Fragment suspension.The precipitation of fragment can coning be prevented by mixing the bottom design of water tank 14.DN65 stainless steel tubes 25 are from top Stretch into and mix after water tank 14 in inverted L shape, fluid full packages is can guarantee that when being and being run to ensure to mix under the low water level state of water tank 14. Mix and four groups of heating coils 15 are disposed in water tank 14, access control system can reach required temperature with guarantee test reclaimed water.In Fig. 3 B top views in mix the bottom of water tank 14 and assign 14-2 armoured thermocouples, 14-3 armoured thermocouples, 14-4 armours in the direction of the clock Thermocouple and 14-5 armoured thermocouples are filled, for providing temperature feedback for heating coil 15.
Injection testing institute water requirement, may make up a test loop.During test run, the 20th electric V-shaped ball valve and the 21st Electric V-shaped ball valve is opened, and the 22nd electric V-shaped ball valve, the 23rd electric V-shaped ball valve and the 24th electric V-shaped ball valve are closed.Water is from mixing The lower end of water tank 14 is flowed out, and the 20th electric V-shaped ball valve, frequency conversion centrifugal pump are sequentially passed through under the driving effect of frequency conversion centrifugal pump 13 13, enter test section 1 after flow down gauge 12 and second pressure meter 9, pass through first pressure meter 10 after outflow again, the 21st is electric V-shaped Ball valve and flow meter 11, are then back to and mix water tank.

Claims (6)

1. a kind of on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop, it is characterised in that the device To load full-scale fuel assembly (2) armoured thermocouple (6), middle part under the bottom insertion of test section (1) in test section (1) Armoured thermocouple (7), the upper armoured thermocouple (8) of top insertion in insertion, two ends difference gauge (5) connect with test section (1) upper and lower side Connect, top difference gauge (4) is connected with test section (1) middle end of upper section, and bottom difference gauge (3) is connected with the middle lower end of test section (1);Examination Test section (1) top and first pressure meter (10), the 21st electric V-shaped ball valve and flow meter (11, mix water tank (14) series connection;Examination Section (1) bottom and second pressure meter (9) are tested, flows down and gauge (12), frequency conversion centrifugal pump (13), the 20th electric V-shaped ball valve and mixes Connect water tank (14) lower end;22nd electric V-shaped ball valve two ends are exported with flow meter (11) outlet and dirty gauge (12) respectively Connection;The upper end of 20th electric V-shaped ball valve is connected lower end connection DN65 stainless steel tubes (25, the DN65 with the 24th electric V-shaped ball valve Stainless steel tube (25) is accessed from water tank (14) middle and upper part is mixed, and is turned under in insertion heating coil (15);23rd electric V-shaped ball Valve is connected with the common node of second pressure meter (9) and dirty gauge (12);Flood pattern (17) is by water injection valve (19) with stirring Mixed water tank (14) top is connected, and stirring motor (16), which is fixed on, to be mixed at the top of water tank (14);Heating coil (15), which is fixed on, to be mixed Water tank (14) middle and lower part, and be connected with temperature control system (18).
2. the on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop according to claim 1, it is special Levy and be, the top for mixing water tank by tank wall nearby 4 positions insertion 14-2 armoured thermocouples, 14-3 armoured thermocouples, 14-4 armoured thermocouples and 14-5 armoured thermocouples;Mix faced the wall and meditated on the outside of water tank on fix vertical bar and mix water tank observation window (14-1)。
3. the on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop according to claim 1, it is special Levy and be, the heating coil includes 4 coils, interval, which is fixed on, mixes water tank (14 middle parts.
4. the on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop according to claim 1, it is special Levy and be, with each fixed impeller (16-2) in top in the middle part of the motor shaft (16-1) of the stirring motor;Two impellers are respectively at 4 Below the midfeather of individual coil and minimum coil.
5. the on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop according to claim 1, it is special Levy and be, the test section is made up of steel housing body and visual window (1-1);The upper low head of test section is the face of cylinder, is prevented Because the mutation in section forms whirlpool after sealing inflow;Test section has A, B, C, D four sides:A faces are whole steel sheet, arrange 6 sensings Device connects hole (1-3-1~1-3-6);B, C, D face set dismountable visual window (1-1), on the one hand meet visualization requirement, the opposing party The experiment fragment that face easy cleaning is deposited on full-scale fuel assembly (2).
6. the on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop according to claim 5, it is special Levy and be, the aperture that 6 sensors of the arrangement connect hole is φ 10;Two ends difference gauge is connect by the transparent hoses for connecing hole of φ 10 (5), top difference gauge (4) and bottom difference gauge (3);Hole is connect by φ 10 screw thread and connects lower armoured thermocouple (6), middle armouring heat Galvanic couple (7) and upper armoured thermocouple (8).
CN201710347729.XA 2017-05-17 2017-05-17 The on-line monitoring device that nuclear power plant containment shell fragment influences on fuel assembly pressure drop Pending CN107195341A (en)

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Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107221362A (en) * 2017-04-27 2017-09-29 中国核电工程有限公司 A kind of sump filter henchnmrk test system
CN108538407A (en) * 2018-06-01 2018-09-14 华北电力大学 The device and cold section of cut analogy method that simulation fragment influences fuel assembly pressure drop
CN109243638A (en) * 2018-09-05 2019-01-18 西安交通大学 Nuclear reactor safety shell fragment migration characteristic pilot system and its test method
CN111028961A (en) * 2019-12-12 2020-04-17 华北电力大学 Simulation system and method for fragment flow in fuel assembly after pressurized water reactor accident
CN112836269A (en) * 2020-11-16 2021-05-25 西南交通大学 Method for splicing nuclear reactor fuel assembly anti-seismic analysis modeling substructure types

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN201387731Y (en) * 2009-04-22 2010-01-20 中广核工程有限公司 Containment sump device
CN104318962A (en) * 2014-10-16 2015-01-28 中科华核电技术研究院有限公司 Location grid rack provided with streamline low pressure drop runner, and fuel assembly
CN104392753A (en) * 2014-10-13 2015-03-04 中国工程物理研究院材料研究所 Experimental system used for simulating severe accident conditions of containment of nuclear power plant, and implementation method thereof
CN106104700A (en) * 2014-04-03 2016-11-09 西屋电气有限责任公司 Low pressure drop nuclear fuel assembly bottom nozzle

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN201387731Y (en) * 2009-04-22 2010-01-20 中广核工程有限公司 Containment sump device
CN106104700A (en) * 2014-04-03 2016-11-09 西屋电气有限责任公司 Low pressure drop nuclear fuel assembly bottom nozzle
CN104392753A (en) * 2014-10-13 2015-03-04 中国工程物理研究院材料研究所 Experimental system used for simulating severe accident conditions of containment of nuclear power plant, and implementation method thereof
CN104318962A (en) * 2014-10-16 2015-01-28 中科华核电技术研究院有限公司 Location grid rack provided with streamline low pressure drop runner, and fuel assembly

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
卓卫乾: "事故后安全壳碎片对燃料组件流动压降影响的研究", 《中国优秀硕士学位论文全文数据库 工程科技II辑》 *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107221362A (en) * 2017-04-27 2017-09-29 中国核电工程有限公司 A kind of sump filter henchnmrk test system
CN108538407A (en) * 2018-06-01 2018-09-14 华北电力大学 The device and cold section of cut analogy method that simulation fragment influences fuel assembly pressure drop
CN109243638A (en) * 2018-09-05 2019-01-18 西安交通大学 Nuclear reactor safety shell fragment migration characteristic pilot system and its test method
CN109243638B (en) * 2018-09-05 2019-07-02 西安交通大学 Nuclear reactor safety shell fragment migration characteristic pilot system and its test method
CN111028961A (en) * 2019-12-12 2020-04-17 华北电力大学 Simulation system and method for fragment flow in fuel assembly after pressurized water reactor accident
CN112836269A (en) * 2020-11-16 2021-05-25 西南交通大学 Method for splicing nuclear reactor fuel assembly anti-seismic analysis modeling substructure types

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