CN109949950A - Reactor clad failure simulated experiment platform - Google Patents
Reactor clad failure simulated experiment platform Download PDFInfo
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- CN109949950A CN109949950A CN201910231960.1A CN201910231960A CN109949950A CN 109949950 A CN109949950 A CN 109949950A CN 201910231960 A CN201910231960 A CN 201910231960A CN 109949950 A CN109949950 A CN 109949950A
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- simulating piece
- reactor
- single channel
- reactor core
- core single
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The present invention provides a kind of reactor clad failure simulated experiment platforms, which is characterized in that including fuel rod simulating piece (1), end plug (2), hermetic collar (3) and reactor core single channel simulating piece (4)；The fuel rod simulating piece (1) is removably mounted on reactor core single channel simulating piece (4), and is realized and sealed and fixed by hermetic collar (3)；The end plug (2) is mounted on reactor core single channel simulating piece (4), and is realized and sealed and fixed by hermetic collar (3)；It is provided in the reactor core single channel simulating piece (4) and transports medium.The present invention can be used under various working clad failure and simulate, and measure under different hydraulics, under different patterns crack and different internal temperatures gas release conditions and internal pressure situation of change off field.
Description
Technical field
The present invention relates to nuclear power breakage experimental technique fields, and in particular, to a kind of nuclear reactor clad failure simulation is real
Test platform more particularly to a kind of vertical nuclear reactor clad failure simulated experiment platform for being equipped with sealing device.
Background technique
Nuclear power is of great significance for Chinese energy safety.In nuclear power station operation, the fuel rod in reactor can be held
Continuous accumulation radioactive product, operational process fuel can may because of various physical chemistry in terms of the problem of occur it is damaged.
If breakage occurs, needs to judge damaged degree in time according to detection data, judge accident (Crash) severity, to decide whether shutdown.
In order to accurate judgement breakage, need largely to test to determine the relationship between damaged degree and coolant activity level.
International experiment is carried out on experimental reactor mostly at present, and experimental variable is substantially stationary, and experimental result lacks expansion.
A kind of involucrum of light-water reactor fuel rod as disclosed in patent document CN108770361A, comprising: core comprising
By pure molybdenum or the matrix being made of molybdenum-base alloy；And external protection, the external protection are selected from :-it is deposited on the appearance of the core
Chromium base coating on face, the chromium base coating includes by pure chromium or at least one the chromium base coating layer being made of chromium-base alloy；It is logical
Cross the chromium base diffusion layer that chromium is diffused into core from the outer surface of core and is obtained；It is a series of by by chromium from the outer surface of core
Be diffused into core and the chromium that forms of the chromium base diffusion layer that obtains and chromium on the outer surface by being deposited on the core or chromium-base alloy
Base coating.
Above-mentioned existing involucrum technology is the experiment that cannot achieve under a variety of Breakage Patterns.Therefore a set of simulation involucrum is needed
Damaged device can adjust experimental variable more flexiblely, reduce experimental cost.
Summary of the invention
For the defects in the prior art, the object of the present invention is to provide a kind of reactor clad failure simulated experiment platforms.
A kind of reactor clad failure simulated experiment platform provided according to the present invention, including it is fuel rod simulating piece, end plug, close
Seal cutting ferrule and reactor core single channel simulating piece；
The fuel rod simulating piece is removably mounted on reactor core single channel simulating piece, and is realized by hermetic collar
It seals and fixes；
The end plug is mounted on reactor core single channel simulating piece, and is sealed and fixed by hermetic collar realization；
It is provided in the reactor core single channel simulating piece and transports medium.
Preferably, the reactor core single channel simulating piece is mounted in loop；The medium that transports is water, and as defeated
It transports any parameter in flow velocity, pressure and the temperature of the water of medium or appoints many kinds of parameters combination that can be conditioned.
Preferably, 4 diameters are provided at the top of the reactor core single channel simulating piece for the hole of 32mm, between the center of circle of adjacent holes
Away from the ratio of diameter be 1.3.
Preferably, the hermetic collar includes hex screw and sealing ring；The fuel rod simulating piece and end plug pass through
Hex screw is mounted on reactor core single channel simulating piece, is realized and is sealed by sealing ring.
Preferably, the runner for transporting medium can be adjusted to set by the setting of fuel rod simulating piece and end plug position
Fixed form.
Preferably, the fuel rod simulating piece includes lifting handle, heating rod and experiment stick housing；The lifting handle
Setting is in experiment stick housing far from reactor core single channel simulating piece side；The heating rod setting is inside experiment stick housing.
Preferably, the outer diameter of the experiment stick housing is 32mm, including first part and second part, the first part
It is connected with second part by coupling part；The internal diameter of the first part is 26mm, length 440mm；The second part
Internal diameter be 20mm, length 350mm；The internal diameter gradual change of the coupling part, and setting specification is provided on coupling part
Experimental port；Second part is the part for testing stick housing close to reactor core single channel simulating piece side.
Preferably, the experiment stick housing further includes measuring instrument interface；The measuring instrument interface can be surveyed with air pressure
Any one of measuring appratus, thermometric instruments and moisture instruments appoint more person's combinations to be connected.
Preferably, the experiment stick housing further includes bleeding point；The bleeding point diameter is 10mm；The fuel stick simulating
The internal pressure of part can be adjusted to setting value by bleeding point.
Preferably, the outer diameter of the heating rod is 14mm, is internally provided with resistance wire；The heating rod can pass through sealing
Mating connection part is filled in, so that experimental port is closed.
Compared with prior art, the present invention have it is following the utility model has the advantages that
1, reactor clad failure simulated experiment platform provided by the invention, with structure is simple, using flexible, cost is relatively low
The advantages of；
2, reactor clad failure simulated experiment platform provided by the invention is that the simulation of nuclear reactor fuel rod clad failure is real
Platform is tested, targeted experiment content is cooperated, the country there is no such experimental bench；
3, the fuel rod simulating piece in reactor clad failure simulated experiment platform provided by the invention can be according to requiring to replace
At the cut of different size, internal pressure and temperature it is adjustable and monitoring；
4, reactor clad failure simulated experiment platform provided by the invention, it is mountable in loop, simulate a variety of water
Power operating condition reduces experimental cost.
Detailed description of the invention
Upon reading the detailed description of non-limiting embodiments with reference to the following drawings, other feature of the invention,
Objects and advantages will become more apparent upon:
Fig. 1 is the structural schematic diagram of reactor clad failure simulated experiment platform preference provided by the invention；
Fig. 2 is the assembling schematic diagram of reactor clad failure simulated experiment platform preference provided by the invention；
Fig. 3 is that the structure of fuel rod simulating piece in reactor clad failure simulated experiment platform preference provided by the invention is shown
It is intended to；
Fig. 4 is that the assembly of fuel rod simulating piece in reactor clad failure simulated experiment platform preference provided by the invention is shown
It is intended to；
Fig. 5 is the processing that stick housing (12) are tested in reactor clad failure simulated experiment platform preference provided by the invention
Schematic diagram.
It is shown in figure:
Fuel rod simulating piece 1
End plug 2
Hermetic collar 3
Reactor core single channel simulating piece 4
Perpendicular fastener screw 5
Lateral fastening screw 6
O-ring seal 7
Lifting handle 11
Test stick housing 12
Heating rod 13
Sealing-plug 14
Specific embodiment
The present invention is described in detail combined with specific embodiments below.Following embodiment will be helpful to the technology of this field
Personnel further understand the present invention, but the invention is not limited in any way.It should be pointed out that the ordinary skill of this field
For personnel, without departing from the inventive concept of the premise, several changes and improvements can also be made.These belong to the present invention
Protection scope.
For the defects in the prior art, the object of the present invention is to provide a kind of reactor clad failure simulated experiment platforms.
A kind of reactor clad failure simulated experiment platform provided according to the present invention, including fuel rod simulating piece 1, end plug 2,
Hermetic collar 3 and reactor core single channel simulating piece 4；The fuel rod simulating piece 1 is removably mounted on the simulation of reactor core single channel
On part 4, and sealed and fixed by the realization of hermetic collar 3；The end plug 2 is mounted on reactor core single channel simulating piece 4, and
It is sealed and fixed by the realization of hermetic collar 3；It is provided in the reactor core single channel simulating piece 4 and transports medium.
Specifically, the reactor core single channel simulating piece 4 is mounted in loop；The medium that transports is water, and conduct
It transports any parameter in flow velocity, pressure and the temperature of the water of medium or appoints many kinds of parameters combination that can be conditioned.It is described
The hole that 4 diameters are 32mm is provided at the top of reactor core single channel simulating piece 4, the center of circle spacing of adjacent holes and the ratio of diameter are
1.3.The hermetic collar 3 includes hex screw and sealing ring；The fuel rod simulating piece 1 and end plug 2 pass through hex screw
It is mounted on reactor core single channel simulating piece 4, is realized and sealed by sealing ring.The runner for transporting medium can pass through fuel rod
The setting of 2 position of simulating piece 1 and end plug is adjusted to the form of setting.The fuel rod simulating piece 1 includes lifting handle 11, heating
Stick 13 and experiment stick housing 12；The setting of lifting handle 11 is in experiment stick housing 12 far from reactor core single channel simulating piece 4 one
Side；The setting of heating rod 13 is inside experiment stick housing 12.The outer diameter of the experiment stick housing 12 is 32mm, including first
Divide and second part, the first part are connected with second part by coupling part；The internal diameter of the first part is 26mm,
Length is 440mm；The internal diameter of the second part is 20mm, length 350mm；The internal diameter gradual change of the coupling part, and even
The experimental port of setting specification is provided in socket part point；Second part is to test stick housing 12 close to reactor core single channel simulating piece 4 one
The part of side.The experiment stick housing 12 further includes measuring instrument interface；The measuring instrument interface can be with gas-pressure survey meter
Any one of device, thermometric instruments and moisture instruments appoint more person's combinations to be connected.The experiment stick housing 12
It further include bleeding point；The bleeding point diameter is 10mm；The internal pressure of the fuel rod simulating piece 1 can pass through bleeding point tune
Section is setting value.The outer diameter of the heating rod 13 is 14mm, is internally provided with resistance wire；The heating rod 13 can pass through sealing
14 mating connection parts are filled in, so that experimental port is closed.
More specifically, the purpose of preference of the present invention is to provide a kind of vertical nuclear reactor clad failure simulated experiment platform,
It is a kind of experiment porch that is multi-functional, adapting to kinds of experiments operating condition.The testable content of experimental bench includes
1, gas release conditions under different hydraulics；
2, gas release conditions under different patterns crack；
3, the gas release off field of different internal temperatures and internal pressure situation of change；
The specific technical solution of preference of the present invention includes reactor core single channel simulating piece 4, replaceable fuel rod simulating piece
1, end plug 2,3 sets of sealing card.Fuel rod simulating piece 1 is made of lifting handle 11, heating rod 13 and simulating piece shell.Fuel rod mould
Quasi- part 1 and end plug 2 are mounted on reactor core single channel simulating piece 4, with 3 fixed fuel stick simulating part 1 of hermetic collar, with O-shaped sealing
7 caulking joint gaps are enclosed, the medium that transports inside reactor core single channel simulating piece 4 is water.Vertical nuclear reactor clad failure simulated experiment platform
Fuel rod simulating piece 1 be mounted on reactor core single channel simulating piece 4, fuel rod simulating piece 1 and end plug 2 hermetic collar 3 and O-shaped
Sealing ring 7 guarantees sealing；Reactor core single channel simulating piece 4 is mountable in relevant loop, adjusts flow velocity, the pressure of internal water
The conditions such as power and temperature, end plug 2 and fuel rod simulating piece 1, which are mounted on its top, can form specific configuration, control runner form.Institute
It states fuel rod simulating piece 1 and is formed by being able to achieve self-locking lifting handle 11, heating rod 13, experiment stick housing 12, and can root
It is replaced according to requirement of experiment.The outer diameter of the simulating piece shell is 32mm, and upper half internal diameter is 26mm, long 440mm, lower half internal diameter
For 20mm, long 350mm, there is converging transition in centre, there is the experimental port of specific standard on converging transition.There are two measurements for simulating piece shell
Tool interface system, above mountable other instruments, monitoring air pressure inside variation, humidity variation or temperature change.Simulating piece shell
There are also the bleeding points of diameter 10mm, can adjust fuel rod simulating piece internal pressure from outside pumping or inflation.The heating rod 13
Outer diameter is 14mm, and resistance wire is filled in inside, there is heating function, and heating rod 13 is fixed on sealing-plug 14, can with outside simulating piece
The converging transition of shell cooperates, and blocks experimental port.The lifting handle 11 can control the inside and outside connection of simulating piece.Simulated experiment platform can
To be simulated for clad failure under various working, and measures under different hydraulics, is warm with Bu Tong inside under different patterns crack
Spend gas release conditions off field and internal pressure situation of change.
Further, preference of the present invention is described further in conjunction with attached drawing.
Such as Fig. 1, a kind of main composition components of nuclear reactor fuel rod clad failure simulated experiment platform are as follows:
Fuel rod simulating piece 1, end plug 2, hermetic collar 3, reactor core single channel simulating piece 4.
Fig. 2 is the installation diagram of nuclear reactor fuel rod clad failure simulated experiment platform, wherein further comprising other component:
Perpendicular fastener screw 5, lateral fastening screw 6, O-ring seal 7
As shown in Fig. 2, hermetic collar 3 is aligned with reactor core single channel simulating piece 4 in advance, fuel rod simulating piece 1 and end plug 2
It is mounted on hermetic collar 3, is then kept fixed with transverse direction fastening screw 6,7 sets of O-ring seal in fuel rod simulating piece 1 and end
On plug 2, fill in the circular groove below hermetic collar 3, then hermetic collar 3 is mounted on reactor core list with perpendicular fastener screw 5
Runner simulating piece 4, while also O-ring seal 7 guarantee sealing.
As shown in Figure 3 and Figure 4, fuel rod simulating piece is divided into four parts:
Lifting handle 11 tests stick housing 12, heating rod 13, sealing-plug 14
Heating rod 13 can be fixed on lifting handle 11, by being threadably mounted at experiment stick housing on lifting handle 11
In 12, sealing-plug 14 is rubber resistant to high temperature, is fixed on heating rod 13, and after lifting handle 11 is subdued, sealing-plug 14 can tightly
It pushes down at the necking in experiment stick housing 12, there is the breakage of experiment above, realize sealing.When being tested, need to only lift
Lifting handle 11, so that it may open gap, be tested.
The detailed results of stick housing 12 are tested as shown in figure 5, upper part is there are two hickey, it can be with jointing temp or pressure
The monitoring instrument of power.
In the description of the present application, it is to be understood that term " on ", "front", "rear", "left", "right", " is erected at "lower"
Directly ", the orientation or positional relationship of the instructions such as "horizontal", "top", "bottom", "inner", "outside" is orientation based on the figure or position
Relationship is set, description the application is merely for convenience of and simplifies description, rather than the device or element of indication or suggestion meaning are necessary
It with specific orientation, is constructed and operated in a specific orientation, therefore should not be understood as the limitation to the application.
Specific embodiments of the present invention are described above.It is to be appreciated that the invention is not limited to above-mentioned
Particular implementation, those skilled in the art can make a variety of changes or modify within the scope of the claims, this not shadow
Ring substantive content of the invention.In the absence of conflict, the feature in embodiments herein and embodiment can any phase
Mutually combination.
Claims (10)
1. a kind of reactor clad failure simulated experiment platform, which is characterized in that including fuel rod simulating piece (1), end plug (2), close
Seal cutting ferrule (3) and reactor core single channel simulating piece (4)；
The fuel rod simulating piece (1) is removably mounted on reactor core single channel simulating piece (4), and passes through hermetic collar
(3) it realizes and seals and fixes；
The end plug (2) is mounted on reactor core single channel simulating piece (4), and is realized and sealed and fixed by hermetic collar (3)；
It is provided in the reactor core single channel simulating piece (4) and transports medium.
2. reactor clad failure simulated experiment platform according to claim 1, which is characterized in that the reactor core single channel mould
Quasi- part (4) are mounted in loop；The medium that transports is water, and the flow velocity as the water for transporting medium, pressure and temperature
Any parameter or a many kinds of parameters combination can be conditioned in degree.
3. reactor clad failure simulated experiment platform according to claim 1, which is characterized in that the reactor core single channel mould
The hole that 4 diameters are 32mm is provided at the top of quasi- part (4), the center of circle spacing of adjacent holes and the ratio of diameter are 1.3.
4. reactor clad failure simulated experiment platform according to claim 1, which is characterized in that the hermetic collar (3)
Including hex screw and sealing ring；The fuel rod simulating piece (1) and end plug (2) are mounted on reactor core list stream by hex screw
On road simulating piece (4), is realized and sealed by sealing ring.
5. reactor clad failure simulated experiment platform according to claim 1, which is characterized in that the stream for transporting medium
Road can be adjusted to the form of setting by the setting of fuel rod simulating piece (1) and end plug (2) position.
6. reactor clad failure simulated experiment platform according to claim 1, which is characterized in that the fuel rod simulating piece
It (1) include lifting handle (11), heating rod (13) and experiment stick housing (12)；Lifting handle (11) setting is in experiment stick
Shell (12) is far from reactor core single channel simulating piece (4) side；Heating rod (13) setting is internal in experiment stick housing (12).
7. reactor clad failure simulated experiment platform according to claim 6, which is characterized in that the experiment stick housing
(12) outer diameter is 32mm, including first part and second part, and the first part and second part pass through interconnecting piece split-phase
Even；The internal diameter of the first part is 26mm, length 440mm；The internal diameter of the second part is 20mm, length 350mm；
The internal diameter gradual change of the coupling part, and the experimental port of setting specification is provided on coupling part；Second part is outside experiment stick
Part of the shell (12) close to reactor core single channel simulating piece (4) side.
8. reactor clad failure simulated experiment platform according to claim 6, which is characterized in that the experiment stick housing
It (12) further include measuring instrument interface；The measuring instrument interface can be with barometric surveying instrument, thermometric instruments and wet
Any one of degree measuring instrument appoints more person's combinations to be connected.
9. reactor clad failure simulated experiment platform according to claim 6, which is characterized in that the experiment stick housing
It (12) further include bleeding point；The bleeding point diameter is 10mm；The internal pressure of the fuel rod simulating piece (1) can pass through pumping
Port is adjusted to setting value.
10. reactor clad failure simulated experiment platform according to claim 7, which is characterized in that the heating rod (13)
Outer diameter be 14mm, be internally provided with resistance wire；The heating rod (13) can be made by sealing-plug (14) mating connection part
Obtain experimental port closing.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910231960.1A CN109949950B (en) | 2019-03-26 | 2019-03-26 | Reactor cladding breakage simulation experiment table |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910231960.1A CN109949950B (en) | 2019-03-26 | 2019-03-26 | Reactor cladding breakage simulation experiment table |
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| Publication Number | Publication Date |
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| CN109949950A true CN109949950A (en) | 2019-06-28 |
| CN109949950B CN109949950B (en) | 2021-04-02 |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110517797A (en) * | 2019-08-16 | 2019-11-29 | 西安交通大学 | A kind of nuclear reactor annular fuel damage experimental provision and experimental method |
| 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 |
| CN112382421A (en) * | 2020-10-09 | 2021-02-19 | 国家电投集团科学技术研究院有限公司 | Test device for simulating nuclear reactor fuel rod |
| CN114043430A (en) * | 2021-12-03 | 2022-02-15 | 中国原子能科学研究院 | Device for operating a hold-down assembly |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110517797A (en) * | 2019-08-16 | 2019-11-29 | 西安交通大学 | A kind of nuclear reactor annular fuel damage experimental provision and experimental method |
| 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 |
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| CN114043430A (en) * | 2021-12-03 | 2022-02-15 | 中国原子能科学研究院 | Device for operating a hold-down assembly |
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| Publication number | Publication date |
|---|---|
| CN109949950B (en) | 2021-04-02 |
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