CN104200853A - Sliced natural circulation device for heavy liquid metal - Google Patents
Sliced natural circulation device for heavy liquid metal Download PDFInfo
- Publication number
- CN104200853A CN104200853A CN201410472751.3A CN201410472751A CN104200853A CN 104200853 A CN104200853 A CN 104200853A CN 201410472751 A CN201410472751 A CN 201410472751A CN 104200853 A CN104200853 A CN 104200853A
- Authority
- CN
- China
- Prior art keywords
- heavy metal
- rectangular
- main body
- liquid
- shaped loops
- 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.)
- Granted
Links
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 invention discloses a sliced natural circulation device for heavy liquid metal. A device body adopts the rectangular sliced structural design and mainly comprises a rectangular loop main body, a heat exchanger, a heating assembly, a flowmeter and an inserting thermocouple. At the international level, the research on a natural circulation experiment of the heavy liquid metal is mainly performed in an experiment platform formed by round tubes; the device disclosed by the invention adopts the rectangular sliced square box design and a reactor core body structure of a reactor is simplified, so that complex flow filed information which are more abundant than a round tube type natural circulation loop and similar to operating conditions of a real reactor is acquired while the development cost of an experimental verification platform is reduced; qualitative simulation and confirmatory research for a heavy liquid metal flow field inside the reactor can be realized; the device can be applied to the field of technology research and development and basic scientific research of the nuke industry as well as verification of analysis software and simulation software of a thermal hydraulic system, and has important research and engineering values.
Description
Technical field
The invention belongs to liquid-metal reactor thermohydraulics research field, relating to liquid heavy metal flows and Research on Heat Transfer Characteristics field, be specifically related to the liquid heavy metal natural circulating device of a kind of slice type, can be the 4th generation lead base cooled reactor structure design verification provide experimental data, accumulation engineering experience.
Background technology
In recent years, liquid heavy metal alloy (Pb, PbBi) because of its have unique neutronics performance, heat-transfer capability and distinctive security become in the world the 4th generation nuclear power reactor candidate select one of cooling medium, therefore a lot of countries are all being devoted to the hot-working hydraulic characteristic research of liquid heavy metal cooling medium, and in succession set up each fluid-like state heavy metal thermal-hydraulic Basic circuit device for this reason, carry out relevant the flowing and heat transfer research of liquid heavy metal, for design and the checking of the 4th generation of technology such as nuclear energy system provides thermal-hydraulic data and technical support.
According to literature survey and analysis, most of liquid heavy metal loop all adopts circular pipeline as the agent structure of platform in the world.As Korea S HELIOS loop, Italian NACIE loop and Sweden TALL loop etc. are circular pipe formula structural design.On these devices, can only obtain temperature and the data on flows information in pipeline direction, and pipe size diameter is relatively little, can not to the true thermal-hydraulic phenomenon occurring of reactor core, carries out overall experimental simulation and checking on the whole.
In order to be convenient to carry out liquid heavy metal reactor hot-working hydraulic characteristic confirmatory experiment, further investigate the flow characteristics of liquid heavy metal cooling medium in heap, device described herein is by adopting the design of rectangle slice type square box that reactor core body construction is simplified and simulated, when reducing development cost, guarantee to obtain than circular pipe type natural convection loop horn of plenty more, press close to the complex flowfield information of actual response stack operation operating mode, can simulate qualitatively and confirmatory study reactor interior liquid heavy metal flow field, this device can be applied to nuclear industry technical research and basic scientific research field, especially the checking of thermohydraulics systematic analysis software and simulation softward, there is important construction value.
Summary of the invention
Technical purpose of the present invention: the liquid heavy metal natural circulating device of a kind of slice type provided by the invention, its agent structure adopts rectangle slice type framework, and the key of the mock-up reactors such as heat interchanger, heating component is built and is included in an Integral box type system.Possess Natural Circulation, gaslift enhancing circular flow function, operating condition that can liquid towards heavy metal reactor carries out simplation verification, reactor passive natural circulation ability is studied, and the liquid heavy metal coolant temperature field in acquisition thermal source and low-temperature receiver Experimental Study of Heat Transfer Characteristics data and between the two upper chamber and lower chambers and velocity field distribute.
Technical scheme of the present invention: the liquid heavy metal natural circulating device of a kind of slice type, is characterized in that described device comprises: storage box 1, liquid level gauge 2, gas circuit pipe 3, row fills pipe 4, and row fills valve 5, rectangular-shaped loops main body 6, insertion-type thermocouple 7, heat interchanger 8, trunk for expansion 9, liquid level gauge 10, gas circuit pipe 11, eduction column 12, upper baffle 13, Venturi meter 14, heating component 15, lower baffle 16; Storage box 1 is positioned at the liquid heavy metal of device below storage, is equipped with liquid level gauge 2 and gas circuit pipe 3; Row fills valve 5 and fills on pipe 4 the row between storage box 1 and rectangular-shaped loops main body 6; Insertion-type thermocouple 7 is distributed on rectangular-shaped loops main body 6 surfaces, surveys liquid heavy metal temperature field; Heat interchanger 8 lays respectively at top and the bottom in rectangular-shaped loops main body 6 with heating component 15; Trunk for expansion 9, is equipped with liquid level gauge 10 and gas circuit pipe 11 at device topmost; Eduction column 12 is fixed on the flange of trunk for expansion 9; Baffle 13 and baffle 16 are arranged in the upper and lower of rectangular-shaped loops main body 6; Venturi meter 14 is positioned at the upper end of heating component 15, for flow measurement.
The liquid heavy metal natural circulating device of described a kind of slice type, it is characterized in that: described rectangular-shaped loops main body 6 is rectangle slice type square box, by insertion-type thermocouple 7, measure liquid heavy metal Temperature Distribution parameter of overall importance in rectangular-shaped loops main body 6, qualitative examination reactor core flow characteristics.
The liquid heavy metal natural circulating device of described a kind of slice type, it is characterized in that: in described rectangular-shaped loops main body 6, be designed with dismountable baffle 13 and baffle 14, the auxiliary mobilization that strengthens is played in liquid towards heavy metal flow field, and the temperature field of modeling effort reactor upper chamber and lower chambers and velocity field distribute.
The liquid heavy metal natural circulating device of described a kind of slice type, it is characterized in that: described Venturi meter 14 is positioned at heating component 15 upper ends, under the prerequisite of the liquid heavy metal flow of assurance measurement, do not destroy the import and export flow field environment of heating component 15, guarantee that data are accurate.
The invention has the advantages that:
Operating condition than the comprehensive liquid towards heavy metal reactor of liquid heavy metal loop energy of conventional circular pipe type structure carries out experimental simulation checking research, obtain flow field and temperature field information more comprehensively and more, by simplifying experimental provision, disclose coolant flow characteristics under liquid heavy metal reactor operation operating mode.Meanwhile, the checking that can be system program simulation softward provides abundant experimental data.
Accompanying drawing explanation
Fig. 1 is the liquid heavy metal natural circulating device of a kind of slice type skeleton view;
Fig. 2 is the liquid heavy metal natural circulating device of a kind of slice type outside drawing;
Fig. 3 is the liquid heavy metal natural circulating device of a kind of slice type cut-open view;
In figure: storage box 1, liquid level gauge 2, gas circuit pipe 3, row fills pipe 4, and row fills valve 5, rectangular-shaped loops main body 6, insertion-type thermocouple 7, heat interchanger 8, trunk for expansion 9, liquid level gauge 10, gas circuit pipe 11, eduction column 12, upper baffle 13, Venturi meter 14, heating component 15, lower baffle 16.
Embodiment
Below in conjunction with accompanying drawing and specific embodiment, further illustrate the present invention.
As shown in Figure 1, the liquid heavy metal natural circulating device of a kind of slice type of the present invention, this device comprises: storage box 1, liquid level gauge 2, gas circuit pipe 3, row fills pipe 4, row fills valve 5, rectangular-shaped loops main body 6, insertion-type thermocouple 7, heat interchanger 8, trunk for expansion 9, liquid level gauge 10, gas circuit pipe 11, eduction column 12, upper baffle 13, Venturi meter 14, heating component 15, lower baffle 16; Storage box 1 is positioned at the liquid heavy metal of device below storage, is equipped with liquid level gauge 2 and gas circuit pipe 3; Row fills valve 5 and fills on pipe 4 the row between storage box 1 and rectangular-shaped loops main body 6; Insertion-type thermocouple 7 is distributed on rectangular-shaped loops main body 6 surfaces, surveys liquid heavy metal temperature field; Heat interchanger 8 lays respectively at top and the bottom in rectangular-shaped loops main body 6 with heating component 15; Trunk for expansion 9, is equipped with liquid level gauge 10 and gas circuit pipe 11 at device topmost; Eduction column 12 is fixed on the flange of trunk for expansion 9; Baffle 13 and baffle 16 are arranged in the upper and lower of rectangular-shaped loops main body 6; Venturi meter 14 is positioned at the upper end of heating component 15, for flow measurement.
Described rectangular-shaped loops main body 6 is rectangle slice type square box, by insertion-type thermocouple 7, measure liquid heavy metal Temperature Distribution parameter of overall importance in rectangular-shaped loops main body 6, qualitative examination reactor core flow characteristics, the number of thermopair can increase according to the actual requirements and reduce.
In described rectangular-shaped loops main body 6, be designed with dismountable baffle 13 and baffle 14, the auxiliary mobilization that strengthens is played in liquid towards heavy metal flow field, the temperature field of modeling effort reactor upper chamber and lower chambers and velocity field distribute, and can change according to the actual requirements shape and the size of baffle and distribute.
Described Venturi meter 14 is positioned at heating component 15 upper ends, does not destroy the import and export flow field environment of heating component 15 under the prerequisite of the liquid heavy metal flow of assurance measurement, guarantees that data are accurate.
The course of work of the present invention is as follows:
1) whole device, in heating and thermal insulation and argon shield state, is mounted with liquid heavy metal in storage box 1;
2) open gas circuit pipe 3 and be filled with argon gas, by the liquid heavy metal press-in device in storage box 1, meanwhile, by gas path pipe 11, discharge blanket gas, guarantee that liquid heavy metal can access to plant;
3) liquid level gauge 10 indicator signals trigger and show that liquid heavy metal is full of device, and the row of closing fills valve 5 and prevents from backflowing, closeall gas circuit pipe 3, gas circuit pipe 11, eduction column 12;
4) heating power of setting heating component 15 heats;
5) the heat exchange performance number of setting heat interchanger 8 is carried out heat exchange;
6) record the numerical value of Venturi meter 14 and insertion-type thermocouple 7; Record is evenly arranged in plug-in type thermometer 9 temperature parameters on device;
7) according to experiment demand, open eduction column 12 and be filled with gas and carry out gaslift and strengthen circulation experiment, need to open gas circuit pipe 11 simultaneously and carry out exhaust;
8) after operation is tested or tested, stop heating system and cooling system, the row of opening fills valve 5 liquid lead bismuth is flowed into storage box 1.
The content not being described in detail in instructions of the present invention belongs to the known prior art of professional and technical personnel in the field.
The above is only the preferred embodiment of the present invention; it should be pointed out that for those skilled in the art, under the premise without departing from the principles of the invention; can also make some improvements and modifications, these improvements and modifications also should be considered as protection scope of the present invention.
Claims (4)
1. the liquid heavy metal natural circulating device of a slice type, it is characterized in that described device comprises: storage box (1), liquid level gauge (2), gas circuit pipe (3), row fills pipe (4), and row fills valve (5), rectangular-shaped loops main body (6), insertion-type thermocouple (7), heat interchanger (8), trunk for expansion (9), liquid level gauge (10), gas circuit pipe (11), eduction column (12), upper baffle (13), Venturi meter (14), heating component (15), lower baffle (16); Storage box (1) is positioned at the liquid heavy metal of device below storage, is equipped with liquid level gauge (2) and gas circuit pipe (3); Row fills the row that valve (5) is positioned between storage box (1) and rectangular-shaped loops main body (6) and fills on pipe (4); Insertion-type thermocouple (7) is distributed on rectangular-shaped loops main body (6) surface, surveys liquid heavy metal temperature field; Heat interchanger (8) lays respectively at top and the bottom in rectangular-shaped loops main body (6) with heating component (15); Trunk for expansion (9), is equipped with liquid level gauge (10) and gas circuit pipe (11) at device topmost; Eduction column (12) is fixed on the flange of trunk for expansion (9); Baffle (13) and baffle (16) are arranged in the upper and lower of rectangular-shaped loops main body (6); Venturi meter (14) is positioned at the upper end of heating component (15), for flow measurement.
2. the liquid heavy metal natural circulating device of a kind of slice type according to claim 1, it is characterized in that: described rectangular-shaped loops main body (6) is rectangle slice type square box, by insertion-type thermocouple (7), measure liquid heavy metal Temperature Distribution parameter of overall importance in rectangular-shaped loops main body (6), qualitative examination reactor core flow characteristics.
3. the liquid heavy metal natural circulating device of a kind of slice type according to claim 1, it is characterized in that: in described rectangular-shaped loops main body (6), be designed with dismountable baffle (13) and baffle (14), the auxiliary mobilization that strengthens is played in liquid towards heavy metal flow field, and the temperature field of modeling effort reactor upper chamber and lower chambers and velocity field distribute.
4. the liquid heavy metal natural circulating device of a kind of slice type according to claim 1, it is characterized in that: described Venturi meter (14) is positioned at heating component (15) upper end, under the prerequisite of the liquid heavy metal flow of assurance measurement, do not destroy the import and export flow field environment of heating component (15), guarantee that data are accurate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410472751.3A CN104200853B (en) | 2014-09-16 | 2014-09-16 | A kind of slice type liquid heavy metal natural circulating device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410472751.3A CN104200853B (en) | 2014-09-16 | 2014-09-16 | A kind of slice type liquid heavy metal natural circulating device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104200853A true CN104200853A (en) | 2014-12-10 |
| CN104200853B CN104200853B (en) | 2017-03-15 |
Family
ID=52086129
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410472751.3A Active CN104200853B (en) | 2014-09-16 | 2014-09-16 | A kind of slice type liquid heavy metal natural circulating device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104200853B (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106409354A (en) * | 2016-09-28 | 2017-02-15 | 哈尔滨工程大学 | Open passive heat extraction system suitable for long-term operation condition |
| CN108028083A (en) * | 2015-07-03 | 2018-05-11 | 阿海珐核能公司 | IRWST water storage boxes include the nuclear reactor of filtration apparatus |
| CN108520786A (en) * | 2018-02-05 | 2018-09-11 | 中广核研究院有限公司 | A kind of new natural circulating cooling lead base fast reactor |
| CN111680405A (en) * | 2020-05-25 | 2020-09-18 | 西安理工大学 | Natural circulation capacity hydraulic characteristic calculation method |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5442668A (en) * | 1993-06-03 | 1995-08-15 | Massachusetts Institute Of Technology | Passive pressure tube light water cooled and moderated reactor |
| US20090207963A1 (en) * | 2006-05-19 | 2009-08-20 | Vera Van Uitert-Zoet | Nuclear reactor |
| US20120085448A1 (en) * | 2010-10-06 | 2012-04-12 | Searete Llc | Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid |
| CN102446564A (en) * | 2011-12-06 | 2012-05-09 | 华北电力大学 | Passive natural-circulation lead bismuth heat exchange device and method for discharging heat out of reactor core |
| CN102831941A (en) * | 2012-06-11 | 2012-12-19 | 华北电力大学 | 0-shaped lead-bismuth heat exchange device |
| CN103413579A (en) * | 2013-07-08 | 2013-11-27 | 华北电力大学 | Natural circulation loop system of lead-bismuth alloy |
| CN103714868A (en) * | 2014-01-12 | 2014-04-09 | 中国科学技术大学 | In-pile heat separation system of liquid heavy metal cooling natural circulating pool type reactor |
-
2014
- 2014-09-16 CN CN201410472751.3A patent/CN104200853B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5442668A (en) * | 1993-06-03 | 1995-08-15 | Massachusetts Institute Of Technology | Passive pressure tube light water cooled and moderated reactor |
| US20090207963A1 (en) * | 2006-05-19 | 2009-08-20 | Vera Van Uitert-Zoet | Nuclear reactor |
| US20120085448A1 (en) * | 2010-10-06 | 2012-04-12 | Searete Llc | Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid |
| CN102446564A (en) * | 2011-12-06 | 2012-05-09 | 华北电力大学 | Passive natural-circulation lead bismuth heat exchange device and method for discharging heat out of reactor core |
| CN102831941A (en) * | 2012-06-11 | 2012-12-19 | 华北电力大学 | 0-shaped lead-bismuth heat exchange device |
| CN103413579A (en) * | 2013-07-08 | 2013-11-27 | 华北电力大学 | Natural circulation loop system of lead-bismuth alloy |
| CN103714868A (en) * | 2014-01-12 | 2014-04-09 | 中国科学技术大学 | In-pile heat separation system of liquid heavy metal cooling natural circulating pool type reactor |
Non-Patent Citations (2)
| Title |
|---|
| 吴宜灿 等: "ITER中国液态铿铅实验包层模块设计研究与实验策略", 《核科学与工程》 * |
| 汪卫华 等: "液态金属回路DRAGON-Ⅱ锂铅合金流动与传热三维数值模拟", 《核科学与工程》 * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108028083A (en) * | 2015-07-03 | 2018-05-11 | 阿海珐核能公司 | IRWST water storage boxes include the nuclear reactor of filtration apparatus |
| CN106409354A (en) * | 2016-09-28 | 2017-02-15 | 哈尔滨工程大学 | Open passive heat extraction system suitable for long-term operation condition |
| CN108520786A (en) * | 2018-02-05 | 2018-09-11 | 中广核研究院有限公司 | A kind of new natural circulating cooling lead base fast reactor |
| CN111680405A (en) * | 2020-05-25 | 2020-09-18 | 西安理工大学 | Natural circulation capacity hydraulic characteristic calculation method |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104200853B (en) | 2017-03-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106981321B (en) | Simulate the experimental rig and method of sodium-cooled fast reactor fuel assembly hot-working hydraulic characteristic | |
| CN112164482B (en) | Comprehensive thermal hydraulic test device for containment | |
| CN106952669B (en) | Stagnation pressure external container cooling test rack in a kind of fusant heap | |
| CN103810930A (en) | Thermal hydraulic feature experimental simulation device for secondary side passive residual heat removal system | |
| Mascari et al. | Sensitivity analysis of the MASLWR helical coil steam generator using TRACE | |
| CN104200853A (en) | Sliced natural circulation device for heavy liquid metal | |
| Gnanadhas et al. | PATH–An experimental facility for natural circulation heat transfer studies related to Post Accident Thermal Hydraulics | |
| CN109493982A (en) | A kind of spentnuclear fuel pool boiling test-bed | |
| Mascari et al. | Analyses of the OSU‐MASLWR Experimental Test Facility | |
| Schultz et al. | Identification and characterization of thermal fluid phenomena associated with selected operating/accident scenarios in modular high temperature gas-cooled reactors | |
| Chen et al. | Post-test simulation of the HTR-10 reactivity insertion without scram | |
| Park et al. | Two-phase natural circulation flow of air and water in a reactor cavity model under an external vessel cooling during a severe accident | |
| CN103413579A (en) | Natural circulation loop system of lead-bismuth alloy | |
| Yang et al. | Experimental validation of the helical steam generator model in the TASS/SMR code | |
| CN105758630B (en) | A kind of experimental provision and method of steam generator elbow region | |
| Zhu et al. | Steam condensation separate effect tests in core make-up tank | |
| Feng et al. | Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor | |
| Boros et al. | Analysis of thermal stratification in the primary circuit of a VVER-440 reactor with the CFX code | |
| Men et al. | Calculation method of passive residual heat removal heat exchanger and numerical simulation | |
| Zhukov et al. | Emergency cooling down of fast-neutron reactors by natural convection (a review) | |
| Mascari et al. | TRACE code analyses for the IAEA ICSP on “Integral PWR design natural circulation flow stability and thermo-hydraulic coupling of containment and primary system during accidents” | |
| Ke et al. | Study on the thermal hydraulic characteristics of a simulated pressurizer during the blowdown process | |
| Herer | Questions relative to chf testing for new pressurized water reactor advanced fuel assemblies | |
| Meloni et al. | RELAP5 and CATHARE2 benchmarking assessment on two LOFA transients conducted in HE-FUS3 helium facility | |
| Racca et al. | Trace code validation for BWR spray cooling injection and CCFL condition based on GÖTA facility experiments |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |