CN108492897A - A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics - Google Patents
A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics Download PDFInfo
- Publication number
- CN108492897A CN108492897A CN201810429291.4A CN201810429291A CN108492897A CN 108492897 A CN108492897 A CN 108492897A CN 201810429291 A CN201810429291 A CN 201810429291A CN 108492897 A CN108492897 A CN 108492897A
- Authority
- CN
- China
- Prior art keywords
- glass tube
- quartz glass
- nuclear reactor
- fuel rod
- container body
- 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.)
- Pending
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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
A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics, the experimental provision is to study the analog fuel stick fusion process based on alternative materials to study the experimental provision of reactor core fuel rod Melting Mechanism indirectly, main body experimental piece is positioned in transparent quartz glass tube, to realize that the visualization of experimentation records；In an experiment, deionized water is injected into quartz glass tubular container by water filling device, then the heating rod in analog fuel stick is carried out being heated to material using electric system to melt；In an experiment, the different location of analog fuel stick is measured into trip temperature, shooting record is carried out to analog fuel stick fusion process using high-speed camera instrument, obtain the characteristics such as surface change procedure and the fusing drop candleization flowing in analog fuel stick fusion process；The present invention provides important experimental provision for the high temperature melting and candleization mechanism study of fuel rod during nuclear reactor major accident core meltdown.
Description
Technical field
The present invention relates to fuel rod fusing in nuclear power plant's major accident and candleization mechanism study technical fields, and in particular to one
The visual experimental apparatus of kind research nuclear reactor fuel rod fusing.
Background technology
When major accident occurs for nuclear power plant's presurized water reactor, if reactor core cannot be winding is effectively cooled, it is molten that reactor core will occur
Change；Nuclear reactor fusing is a staged evolution, reactor core material successively occur at different temperature fusing or
Liquefaction, while there is also oxidation, the physical-chemical reactions of eutectic and the complexity such as molten that disappears between reactor core material；Fuel rod is as nuclear reaction
The core component of heap, is made of uranium dioxide pellet and zirconium alloy cladding, during nuclear reactor major accident, with
Core temperature increases, and with the vapor in reactor core oxidation reaction will occur for zirconium alloy cladding, to form oxygen in involucrum outer surface
Change zirconium and discharges hydrogen；Zirconium oxide has higher fusing point, and fuel element geometry can be delayed to fail, and limits fuel rod melting
Object repositions process；In view of the different degree of oxidation of zirconium alloy cladding, when core temperature is increased to 1800 DEG C to 2000 DEG C areas
Between when, zirconium alloy cladding will melt；Zircaloy fusant is in contact with uranium dioxide pellet immediately, due between the two
Non- thermodynamic stability will generate significant chemical reaction between them, and cause uranium dioxide pellet in the temperature less than its fusing point
Disappear under degree molten, and forms U-O-Zr watery fusion objects；Therefore, zircaloy fusant disappears to the chemistry of uranium dioxide pellet molten
Process will cause reactor core internal combustion charge bar initial failure, accelerate core melt down accident process；While disappearing molten uranium dioxide pellet,
Zircaloy fusant also the zirconium oxide layer on involucrum will disappear it is molten, so as to cause involucrum fail；In fuel rod fusion process,
U-O-Zr watery fusions object will be fallen with the shape of similar candle drop along involucrum, i.e. candleization process；
Zircaloy fusant is migrated by reactor core high-temperature region to reactor core lower part low-temperature space during candleization, heat fusant with
Transmission between involucrum will cause zircaloy melt temperature to reduce or solidify, therefore zircaloy oxidation process will be limited
System, to reduce the heat and hydrogen that oxidation reaction is discharged；The reactor core material solidified again will reduce core coolant flow and lead to face
Product blocks coolant channel, to the cooling capacity of fuel rod in reduction accident, and aggravates fuel rod fusing degree；Candleization
Zircaloy fusant causes involucrum to fail also by the zirconium oxide layer on molten involucrum surface of continuing to disappear in journey；After involucrum substantially fails, heap
Long-pending fuel pellet will cave in, and what is accumulated in fuel assembly there is radioactive gaseous state or volatile fission product will largely release
It puts；Therefore, candleization process is a multicomponent for being related to complicated physical-chemical reaction, multi phase state, various dimensions flow process, right
The development process and major accident consequence of core meltdown major accident have great influence；
It can be seen that zircaloy to the chemistry of uranium dioxide pellet and zirconium dioxide disappear molten and fusant along involucrum candle
Behavior will generate core meltdown disintegration, the generation of hydrogen, release of radioactive fission product etc. in major accident most important
Influence；Carry out fuel rod disappear molten and candleization mechanism and key technology research will be seen that and be familiar with nuclear reactor major accident
Process reduces the uncertainty of major accident analysis, and perfect severe accident relieving strategy and precautionary measures are formulated for nuclear power station
Technical support is provided, to reduce the possibility of nuclear reactor major accident generation.
Invention content
The purpose of the present invention is overcome the deficiencies of the prior art and provide a kind of research nuclear reactor fuel rod pre-arcing characterisitics
Visual experimental apparatus can provide the temperature change in fuel rod fusion process, the variation of fusion process medium rod configuration of surface
Data and image.
In order to achieve the above object, the present invention adopts the following technical scheme that：
A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics, the simulation combustion of the experimental provision
Charge bar is a kind of alternative materials stick based on nuclear reactor fuel rod structure design, by being placed in a quartz glass tube
The visualization for reaching experimentation, including quartz glass tube container body 1, electric system 2, measurement are tested in container
System 3, water filling device 4 and drainage system device 5；
The quartz glass tube container body 1 includes quartz glass tube 102, is arranged in 102 top and the bottom of quartz glass tube
Detachable guartz glass tube top cover board 106 and detachable guartz glass tube lower part cover board 105, pass through top spud pile
104 and bottom spud pile 103 be fixed on quartz glass tube top cover board 106 and detachable guartz glass tube lower part cover board 105
Between analog fuel stick 101；
The analog fuel stick 101 includes the heating rod 101-1 and involucrum 101-2 being coated on outside heating rod 101-1；
The material of the involucrum 101-2 is Wood's metal；
The electric system 2 be quartz glass tube container body 1 in heating bar device 101-1 and measuring system 3 carry
Power supply source；
The measuring system 3 includes that the temperature measurement system of temperature monitoring is carried out to quartz glass tube container body 1
301, the first high-speed camera instrument 302, the second high-speed camera instrument 303 and measuring scale of position 304；The first high-speed camera instrument 302
1 outer both sides of quartz glass tube container body are separately positioned on the second high-speed camera instrument 303, records simulated in experimentation in real time
The fusion process and configuration of surface of fuel rod 101 change；The measuring scale of position 304 is placed on by involucrum 101-2, is first high
The shooting of fast video camera 302 and the second high-speed camera instrument 303 provides location information；
The setting of the water filling device 4 is arranged in 1 top of quartz glass tube container body, drainage system device 5 in quartzy glass
1 bottom of glass tubular container main body.
Detachable guartz glass tube lower part cover board 105 in the quartz glass tube container body 1 includes cover board master
Body portion 105-1 and the cooling water outlet channel being opened on the 105-1 of cover plate main body part being connect with drainage system device 5
105-2。
Temperature measurement system 301 in the measuring system 3 is included in what the outer length directions of involucrum 101-2 were evenly arranged
It four thermocouples for measuring the variation of 101 surface temperature of analog fuel stick and is arranged in water in quartz glass tube 102
To measure water temperature change a thermocouple.
The water filling device 4 includes external pipe and Water filling valve 401.
The drainage system device 5 includes external pipe, filter screen 501 and water discharging valve 502, and filter screen 501 is arranged
The cooling water outlet channel junctions 105-2 on external pipe and cover plate main body part 105-1, prevent quartz glass tubular container
Interior envelope 101-2 melts solidification fragment, which enters drainage pipeline, causes water discharging valve 502 to block.
Compared to the prior art compared with, the invention has the advantages that：
1, experimental provision of the invention, was melted as molten material research fuel rod using alternative materials Wood's metal
The characteristics such as surface change procedure and fusing drop candleization flowing in journey, material price is cheap, and it is convenient to obtain；
2, experimental provision of the invention, was melted as molten material research fuel rod using alternative materials Wood's metal
The characteristics such as surface change procedure and fusing drop candleization flowing in journey, Wood's metal fusing point is relatively low, and experimental implementation is strong, peace
Quan Xinggao；
3, experimental provision of the invention has used a transparent quartz glass tube as container, can be in experimentation
Shooting record comprehensively is carried out to the fusion process of analog fuel stick, facilitates the metamorphosis etc. for obtaining melt in migration course
Data information.
Description of the drawings
Fig. 1 is that a kind of overall structure of the visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics of the present invention is shown
It is intended to.
Fig. 2 is the front view of quartz glass tube container body in experimental provision of the present invention.
Fig. 3 is the radial cutaway view of analog fuel stick in experimental provision of the present invention.
Fig. 4 is the vertical view of detachable guartz glass tube lower part cover board in experimental provision of the present invention.
Fig. 5 is the measuring system schematic diagram in experimental provision of the present invention.
Fig. 6 is the flood pattern front view in experimental provision of the present invention.
Fig. 7 is the drainage system device front view in experimental provision of the present invention.
Specific implementation mode
The present invention is described in detail with reference to the accompanying drawings and detailed description：
As shown in Figure 1, Figure 2, shown in Fig. 3 and Fig. 5, a kind of visualization of research nuclear reactor fuel rod pre-arcing characterisitics of the present invention is real
The analog fuel stick of experiment device, the experimental provision is a kind of alternative materials based on nuclear reactor fuel rod structure design
Stick, by being placed in the visualization for being tested to reach experimentation in a quartz glass tubular container, including stone
English glass tube container body 1, electric system 2, measuring system 3, water filling device 4 and drainage system device 5；The quartz glass
Tubular container main body 1 includes quartz glass tube 102, is arranged on the detachable guartz glass tube of 102 top and the bottom of quartz glass tube
Portion's cover board 106 and detachable guartz glass tube lower part cover board 105 are fixed by top spud pile 104 and bottom spud pile 103
Analog fuel stick 101 between quartz glass tube top cover board 106 and detachable guartz glass tube lower part cover board 105；It is described
Analog fuel stick 101 include the heating rod 101-1 and involucrum 101-2 that is coated on outside heating rod 101-1；The involucrum 101-
2 material is Wood's metal；The electric system 2 is heating bar device 101-1 and survey in quartz glass tube container body 1
Amount system 3 provides power supply；The measuring system 3 includes that the temperature survey of temperature monitoring is carried out to quartz glass tube container body 1
Amount system 301, the first high-speed camera instrument 302, the second high-speed camera instrument 303 and measuring scale of position 304；First high-speed camera
Instrument 302 and the second high-speed camera instrument 303 are separately positioned on 1 outer both sides of quartz glass tube container body, record experimentation in real time
The fusion process and configuration of surface of middle analog fuel stick 101 change；The measuring scale of position 304 is placed on by involucrum 101-2, is
The shooting of first high-speed camera instrument 302 and the second high-speed camera instrument 303 provides location information；The water filling device 4 is arranged in stone
1 top of English glass tube container body, drainage system device 5 are arranged in 1 bottom of quartz glass tube container body.
As shown in Fig. 4, Fig. 6 and Fig. 7, detachable guartz glass tube lower part cover board 105 provides a cooling water outlet
Channel 105-2, same detachable guartz glass tube top cover board 106 also provide a cooling water inlet channel.Installation
Preceding needs are first arranged thermocouple measurement point, are respectively 50mm, 150mm, 250mm in 101 position height of analog fuel stick
With four thermocouples of location arrangements of 350mm and compensating line is drawn, by the bottom spud pile of analog fuel stick 101 when installation
103 are fixed on 105 upper center position of detachable guartz glass tube lower part cover board, are then placed in analog fuel stick 101
On bottom spud pile 103, quartz glass tube 102 is inserted in and is carried out sealing, measuring scale of position 304 is placed on quartz glass tube
In 102, top spud pile 104 is first fixed on 106 lower section of detachable guartz glass tube top cover board, is then inserted in mould
101 top of quasi- fuel rod；Analog fuel stick 101 is connected into electric system 2；The is placed around quartz glass tube container body 1
One high-speed camera instrument 302 and the second high-speed camera instrument 303 are used to shoot surface when analog fuel stick 101 melts in experimentation
Metamorphosis；In detachable guartz glass tube lower part, cover board 105 is pre-placed a filter screen 501, and installs drainage system
Device 5 installs water filling device 4；
When experiment starts, the water discharging valve 502 of drainage system device 5 is closed, opens the Water filling valve 401 of water filling device 4
And cooling water is injected into quartz glass tube 102 until water surface flooding inundation simulation fuel rod 101, measuring system 3 is opened, electric power is opened
System 2 is powered to the heating rod 101-1 in analog fuel stick 101, pays attention to voltage swing, observes temperature change, keeps temperature slow
Slow to rise, Wood's metal fusing point is 70 DEG C, when fusing point of the temperature rise to Wood's metal honor, reduces input voltage again, sternly
Lattice record the content of the records such as the parameter, including time, temperature, high-speed camera of experimentation, until analog fuel stick 101
Molten material involucrum 101-2 stops experiment after melting part, closes electric system 2, closes measuring system 3, waits for that experimental section cools down
Afterwards, the water discharging valve 501 of drainage system device 5, the residue in drained water post-processing experimental provision are opened, experiment terminates.
Claims (5)
1. a kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics, it is characterised in that：The experiment dress
The analog fuel stick set is a kind of alternative materials stick based on nuclear reactor fuel rod structure design, by being placed in one
The visualization for reaching experimentation, including quartz glass tube container body (1), electricity are tested in quartz glass tubular container
Force system (2), measuring system (3), water filling device (4) and drainage system device (5)；
The quartz glass tube container body (1) includes quartz glass tube (102), setting quartz glass tube (102) up and down
The detachable guartz glass tube top cover board (106) and detachable guartz glass tube lower part cover board (105) in portion pass through top
Spud pile (104) and bottom spud pile (103) are fixed on quartz glass tube top cover board (106) and detachable guartz glass tube
Analog fuel stick (101) between lower part cover board (105)；
The analog fuel stick (101) includes heating rod (101-1) and is coated on the involucrum of heating rod (101-1) outside
(101-2)；The material of the involucrum (101-2) is Wood's metal；
The electric system (2) is heating bar device (101-1) and measuring system in quartz glass tube container body (1)
(3) power supply is provided；
The measuring system (3) includes that the temperature measurement system of temperature monitoring is carried out to quartz glass tube container body (1)
(301), the first high-speed camera instrument (302), the second high-speed camera instrument (303) and measuring scale of position (304)；First high speed is taken the photograph
Picture instrument (302) and the second high-speed camera instrument (303) are separately positioned on quartz glass tube container body (1) outer both sides, record in real time
Fusion process and the configuration of surface variation of analog fuel stick (101) in experimentation；The measuring scale of position (304) is placed on packet
Shell (101-2) is other, and the shooting for the first high-speed camera instrument (302) and the second high-speed camera instrument (303) provides location information；
At the top of quartz glass tube container body (1), drainage system device (5) is arranged in quartz for water filling device (4) setting
Glass tube container body (1) bottom.
2. a kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics according to claim 2, special
Sign is：Detachable guartz glass tube lower part cover board (105) in the quartz glass tube container body (1) includes cover board
Main part (105-1) and the cooling water being opened on cover plate main body part (105-1) being connect with drainage system device (5) go out
Mouth channel (105-2).
3. a kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics according to claim 1, special
Sign is：It is uniform that temperature measurement system (301) in the measuring system (3) is included in involucrum (101-2) outer length direction
Four thermocouples for measuring the variation of analog fuel stick (101) surface temperature of arrangement and in the quartz glass tube (102)
Arranged in water to measure water temperature change a thermocouple.
4. a kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics according to claim 1, special
Sign is：The water filling device (4) includes external pipe and Water filling valve (401).
5. a kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics according to claim 1, special
Sign is：The drainage system device (5) includes external pipe, filter screen (501) and water discharging valve (502), filter screen
(501) junction cooling water outlet channel (105-2) of setting on external pipe and cover plate main body part (105-1), prevents
Quartz glass tubular container interior envelope (101-2) melt solidification fragment, which enters drainage pipeline, causes water discharging valve (502) to block.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810429291.4A CN108492897A (en) | 2018-05-08 | 2018-05-08 | A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810429291.4A CN108492897A (en) | 2018-05-08 | 2018-05-08 | A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN108492897A true CN108492897A (en) | 2018-09-04 |
Family
ID=63354096
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201810429291.4A Pending CN108492897A (en) | 2018-05-08 | 2018-05-08 | A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN108492897A (en) |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN109557124A (en) * | 2019-01-21 | 2019-04-02 | 上海交通大学 | A kind of pneumatic visualization device of crash-proof fuel rod quenching experiment |
| CN109659042A (en) * | 2018-12-27 | 2019-04-19 | 中国科学院近代物理研究所 | A kind of visualization fuel rod |
| CN110867263A (en) * | 2019-11-07 | 2020-03-06 | 西安交通大学 | Experimental device and method for researching failure behavior of fuel element in severe accident of nuclear reactor |
| CN111540491A (en) * | 2020-05-14 | 2020-08-14 | 中国核动力研究设计院 | Rod-shaped fuel source item release characteristic research experimental device and using method thereof |
| CN112037950A (en) * | 2020-09-24 | 2020-12-04 | 中国核动力研究设计院 | Fuel rod fission product release simulation device and use method thereof |
| CN112086211A (en) * | 2020-09-15 | 2020-12-15 | 华北电力大学 | Experimental device and experimental method for simulating secondary hydrogen embrittlement phenomenon of zirconium alloy cladding |
| CN112289468A (en) * | 2020-09-27 | 2021-01-29 | 西安交通大学 | Experimental device and method for determining ultra-high temperature oxidation melting behavior of double-sided cooling fuel |
| CN112331371A (en) * | 2020-11-02 | 2021-02-05 | 西安交通大学 | Nuclear reactor plate type fuel stream melting and transferring behavior experimental device and method |
| CN112509715A (en) * | 2020-11-16 | 2021-03-16 | 中国原子能科学研究院 | Seven subassembly flow measurement experiment sections |
| CN113782234A (en) * | 2021-08-19 | 2021-12-10 | 苏州热工研究院有限公司 | Underwater fuel rod simulation device and installation control method thereof |
| KR20230046634A (en) | 2021-09-30 | 2023-04-06 | 한국원자력연구원 | Nuclear fuel cladding multidimensional behavior experiment apparatus |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106409349A (en) * | 2016-09-30 | 2017-02-15 | 中山大学 | Experimental system for forming characteristic of sodium-cooled fast reactor debris bed |
| CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
| CN106992028A (en) * | 2017-04-05 | 2017-07-28 | 中山大学 | The experimental system visualizing of molten fuel pond slosh during sodium-cooled fast reactor major accident |
-
2018
- 2018-05-08 CN CN201810429291.4A patent/CN108492897A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106409349A (en) * | 2016-09-30 | 2017-02-15 | 中山大学 | Experimental system for forming characteristic of sodium-cooled fast reactor debris bed |
| CN106525895A (en) * | 2016-11-11 | 2017-03-22 | 西安交通大学 | Device and method for high temperature melt growth choking experiment |
| CN106992028A (en) * | 2017-04-05 | 2017-07-28 | 中山大学 | The experimental system visualizing of molten fuel pond slosh during sodium-cooled fast reactor major accident |
Non-Patent Citations (1)
| Title |
|---|
| 王帅: "竖直锡包壳熔化过程的实验分析和数值模拟", 《中国优秀硕士学位论文全文数据库（电子期刊）工程科技Ⅱ辑》 * |
Cited By (19)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| 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 |
| CN109659042A (en) * | 2018-12-27 | 2019-04-19 | 中国科学院近代物理研究所 | A kind of visualization fuel rod |
| CN109557124A (en) * | 2019-01-21 | 2019-04-02 | 上海交通大学 | A kind of pneumatic visualization device of crash-proof fuel rod quenching experiment |
| CN110867263A (en) * | 2019-11-07 | 2020-03-06 | 西安交通大学 | Experimental device and method for researching failure behavior of fuel element in severe accident of nuclear reactor |
| CN111540491A (en) * | 2020-05-14 | 2020-08-14 | 中国核动力研究设计院 | Rod-shaped fuel source item release characteristic research experimental device and using method thereof |
| CN111540491B (en) * | 2020-05-14 | 2022-04-01 | 中国核动力研究设计院 | Rod-shaped fuel source item release characteristic research experimental device and using method thereof |
| CN112086211A (en) * | 2020-09-15 | 2020-12-15 | 华北电力大学 | Experimental device and experimental method for simulating secondary hydrogen embrittlement phenomenon of zirconium alloy cladding |
| CN112086211B (en) * | 2020-09-15 | 2022-04-15 | 华北电力大学 | Experimental device and experimental method for simulating secondary hydrogen embrittlement phenomenon of zirconium alloy cladding |
| CN112037950B (en) * | 2020-09-24 | 2022-02-11 | 中国核动力研究设计院 | Fuel rod fission product release simulation device and use method thereof |
| CN112037950A (en) * | 2020-09-24 | 2020-12-04 | 中国核动力研究设计院 | Fuel rod fission product release simulation device and use method thereof |
| CN112289468A (en) * | 2020-09-27 | 2021-01-29 | 西安交通大学 | Experimental device and method for determining ultra-high temperature oxidation melting behavior of double-sided cooling fuel |
| CN112289468B (en) * | 2020-09-27 | 2021-10-22 | 西安交通大学 | Experimental device and method for determining ultra-high temperature oxidation melting behavior of double-sided cooling fuel |
| CN112331371B (en) * | 2020-11-02 | 2021-11-09 | 西安交通大学 | Nuclear reactor plate type fuel stream melting and transferring behavior experimental device and method |
| CN112331371A (en) * | 2020-11-02 | 2021-02-05 | 西安交通大学 | Nuclear reactor plate type fuel stream melting and transferring behavior experimental device and method |
| CN112509715A (en) * | 2020-11-16 | 2021-03-16 | 中国原子能科学研究院 | Seven subassembly flow measurement experiment sections |
| CN112509715B (en) * | 2020-11-16 | 2022-08-05 | 中国原子能科学研究院 | Seven subassembly flow measurement experiment sections |
| CN113782234A (en) * | 2021-08-19 | 2021-12-10 | 苏州热工研究院有限公司 | Underwater fuel rod simulation device and installation control method thereof |
| KR20230046634A (en) | 2021-09-30 | 2023-04-06 | 한국원자력연구원 | Nuclear fuel cladding multidimensional behavior experiment apparatus |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN108492897A (en) | A kind of visual experimental apparatus of research nuclear reactor fuel rod pre-arcing characterisitics | |
| CN108447573B (en) | A kind of nuclear reactor fuel rod fusing visual experimental apparatus and method | |
| Kissane | On the nature of aerosols produced during a severe accident of a water-cooled nuclear reactor | |
| CN115132385B (en) | Experimental system and method for interaction of lead-based reactor core melt and coolant | |
| CN106251919A (en) | Reactor pressure vessel security test system under major accident operating mode | |
| KR100963472B1 (en) | Metallic fuel rod in metal sheath including metallic fuel particles and a preparation method thereof | |
| Song et al. | A use of prototypic material for the investigation of severe accident progression | |
| Yamano et al. | Basic visualization experiments on eutectic reaction between boron carbide and stainless steel under sodium-cooled fast reactor conditions | |
| Hózer et al. | Behavior of VVER fuel rods tested under severe accident conditions in the CODEX facility | |
| Kim et al. | Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactor | |
| US3446703A (en) | Method of operating a nuclear reactor | |
| Wu et al. | Experimental study on fuel rod melting based on alternative materials | |
| Chatelard et al. | Overview of the independent ASTEC V2. 0 validation by SARNET partners | |
| Prasad et al. | Experimental investigation of heat transfer during severe accident of a Pressurized Heavy Water Reactor with simulated decay heat generation in molten pool inside calandria vessel | |
| Rahman et al. | Simulation of molten metal freezing behavior on to a structure | |
| Zeng et al. | A scoping study on remelting process of a debris bed in the lower head of reactor pressure vessel | |
| Tan et al. | Experimental investigation on the characteristics of molten lead–bismuth non-eutectic alloy fragmentation in water | |
| An et al. | Corium configuration and penetration tube failure for Fukushima Daiichi nuclear power plant | |
| Matsuba et al. | Mechanism of upward fuel discharge during core disruptive accident in sodium-cooled fast reactors | |
| Tsuchiya et al. | In-situ tritium release behavior from Li2TiO3 pebble-bed | |
| Cheng et al. | Study on the effect of jet cross section shape on molten fuel fragmentation behavior with simulant experiments | |
| Dickerman et al. | TREAT meltdown of irradiated metallic fast-reactor fuel in an inert atmosphere | |
| Kudashov et al. | Numerical investigation of the fuel cladding disruption in contact with the molten metallic fuel of a sodium-cooled fast reactor | |
| Soner et al. | Experimental investigation of solid–liquid mixtures freezing behavior in flow channels | |
| Lobanov et al. | Experimental modeling of fuel pins cladding melting while severe accident in lead cooled reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20180904 |
|
| WD01 | Invention patent application deemed withdrawn after publication |