CN209607418U - Research reactor - Google Patents
Research reactor Download PDFInfo
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- CN209607418U CN209607418U CN201920184628.XU CN201920184628U CN209607418U CN 209607418 U CN209607418 U CN 209607418U CN 201920184628 U CN201920184628 U CN 201920184628U CN 209607418 U CN209607418 U CN 209607418U
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- core
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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 utility model relates to a kind of research reactors, comprising: compact cores and the heavy water reflector around reactor core setting；Wherein, fast neutron irradiated duct is arranged in the heap in-core, provides fast neutron irradiated space, vertically and horizontally duct is arranged in the heavy water reflector, provides Thermal Neutron Irradiation and experiment utilizes space.By being respectively provided with duct inside and outside reactor core, the neutron of different power spectrums can be utilized simultaneously, facilitates and carries out various neutron experiments researchs.
Description
Technical field
This disclosure relates to core application field, further to a kind of research reactor.
Background technique
Currently, research reactor, there is neutron sink and antineutron trap two types, antineutron trap type reactor is in the world
Compare a kind of heap-type favored.For in the neutron well-type heap that heap in-core forms neutron fluence rate peak, this heap-type
Usually using high-enriched uranium compact cores, a large amount of fission neutrons do not obtain abundant slowing down in heap in-core, but enter and surround reactor core
Slowing down forms high neutron fluence rate peak in moderator, and here it is the origin of antineutron trap type heap.This is currently mainly utilized in the world
Kind research reactor development neutron scattering experiment, therefore also referred to as neutron beam flow pattern research reactor, but its purposes is relatively simple, does not adapt to
The application of a variety of demands.
Utility model content
(1) technical problems to be solved
In view of this, the disclosure is designed to provide a kind of research reactor, at least partly to solve above-mentioned skill
Art problem.
(2) technical solution
To achieve the above object, the utility model provides a kind of research reactor, comprising:
The reactor core of compact Layout and the heavy water reflector being arranged around reactor core；Wherein,
The heap in-core is equipped with fast neutron irradiated duct, provides fast neutron irradiated space；
It is equipped with vertical and/or horizontal hole in the heavy water reflector, Thermal Neutron Irradiation and experimental applications space are provided.
In a further embodiment, the reactor core includes: multiple fuel assemblies, adjacent to each other to each other, forms battle array
Column compact Layout structure, the array architecture are located in core vessel；The fast neutron irradiated duct is set to array knot
Except structure fuel assembly reactor core but it is located within core vessel.
In a further embodiment, aluminium is provided between the array architecture fuel assembly and core vessel
Filler plug.
In a further embodiment, research reactor further include: center fuel component replaces with central irradiation port
Road provides thermal neutron fluence rate peak space.
In a further embodiment, the fuel assembly is plate fuel assembly.
In a further embodiment, the fuel of the fuel assembly is slightly enriched uranium.
In a further embodiment, the fuel assembly fuel slab gap setting is not wait gaps runner, to solve
Thermal power is unevenly distributed the puzzlement of weighing apparatus.
In a further embodiment, the heavy water reflector irradiation channel except vertical direction setting it is outer, also set up and
The horizontal hole of reactor core cross-sectional periphery arranged tangential, thermal neutron is led to outside heavy water reflector.
In a further embodiment, research reactor further include: multiple control rod follower fuel assemblies, setting
Inside array fuel assembly, to realize the control of reactor and keep the characteristic of its compact cores.
In a further embodiment, fuel reactor core center replaces with central irradiation channel, provides and hankers
Son irradiation application space.
(3) beneficial effect
Fast neutron irradiated duct is set in heap in-core by setting and heavy water reflector spoke is set in heavy water reflector
According to duct, realizes the separation of compact core-spectrum, can use the neutron (fast neutron and thermal neutron) of different power spectrums, meet various
The experiment of demand；
By the way that reactor core center fuel assembly is replaced with central irradiation channel, to realize antineutron trap and neutron simultaneously
Trap reactor core characteristic；
This research reactor uses slightly enriched uranium by using plate fuel assembly, to meet compact small size reactor core
Design requirement.
Detailed description of the invention
Fig. 1 is a kind of top view of antineutron trap type research reactor of the utility model embodiment.
Fig. 2 is the research reactor thermal neutron fluence rate distribution map of Fig. 1.
Fig. 3 is that the antineutron trap type of the utility model embodiment and neutron well-type while the research reactor realized are bowed
View.
Fig. 4 is the research reactor thermal neutron fluence rate distribution map of Fig. 3.
Specific embodiment
Below with reference to the attached drawing in the utility model embodiment, the technical scheme in the embodiment of the utility model is carried out clear
Chu is fully described by, it is clear that the described embodiments are only a part of the embodiments of the utility model, rather than whole realities
Apply example.Based on the embodiments of the present invention, those of ordinary skill in the art are obtained without making creative work
The every other embodiment obtained, belongs to the protection scope of the utility model.
It should be noted that the research reactor (also referred to as research reactor) of the utility model meaning, refers to using scientific research as mesh
Nuclear reactor.
Basic conception according to the present utility model provides a kind of research reactor, by outside heap in-core and reactor core
Heavy water reflector in neutron irradiation duct is set simultaneously, reach a variety of using purpose of neutron.
Fig. 1 is a kind of top view of research reactor of the utility model embodiment.As shown in fig. 1, the research
Reactor includes: the core vessel 7 for containing compact Layout fuel reactor core and the heavy water reflector 1 around reactor core setting；Wherein, heap
It is equipped with fast neutron irradiated duct 2 in core container 7, fast neutron irradiated space is provided；It hangs down in heavy water reflector 1 equipped with heavy water reflector
Straight irradiation channel 3 and/or horizontal hole 9 provide Thermal Neutron Irradiation space and draw thermal neutron.
Here the compact Layout fuel reactor core contained in core vessel 7 common core structure when being nuclear reaction,
For carrying out nuclear fission reaction wherein, the higher neutron of neutron energy, that is, neutron energy spectrum can be generated in reaction process
It is harder, it is properly termed as fast neutron, by the way that fast neutron irradiated duct 2 is arranged in the aluminium filler plug inside core vessel, is provided
The harder neutron of neutron energy spectrum.
Here compact Layout is arranged closely between 7 fuel component of core vessel, when making fuel that fission reaction occur
The fission neutron of generation does not obtain abundant slowing down in core vessel 7, and leaking to 7 outside of core vessel, just sufficiently slowing down forms heat
Neutron.
In addition, 7 external rings of core vessel, around setting heavy water reflector 1, heavy water reflector is used for as moderator and from combustion
The neutron collision that material heap in-core comes out reduces the energy of neutron, forms the relatively low thermal neutron of energy.The utility model is implemented
By the way that heavy water reflector irradiation channel 3 is arranged in heavy water reflector 1 in example, the higher thermal neutron of fluence rate can be obtained, by it
In experimental situation applied to thermal neutron demand, this is the origin of antineutron trap type heap.
It in some embodiments, include multiple fuel assemblies 5 in the core vessel 7, between fuel assembly to each other mutually
Close, can forming array architecture, (array architecture here is not that stringent each line number amount is identical, and only compact is arranged
Column), fast neutron irradiated duct 3 is set to the aluminium filler plug except array architecture fuel assembly 5 but being located within core vessel 7
In 4, since aluminium atom amount is greater than the molecular weight of heavy water, moderating effect is limited, in the fast neutron irradiated duct 3 in the filler plug
The neutron energy of external heavy water reflector is still greater than in neutron energy.Therefore fast neutron irradiated space is obtained.
In some embodiments, the fuel assembly is plate fuel assembly；Existing fuel assembly can be involute
Fuel assembly, plate fuel assembly and rod shape fuel component, utility model people are compared by having carried out analysis to various assemblies, are sent out
Compact cores requirement now can satisfy using plate fuel assembly.
In some embodiments, in core vessel 7 at several fuel assembly positions in reactor fuel assembly array
Control rod be can be set to control reactor；In view of the control rod water cavity to be formed since control rod is promoted of conventional design
Lead to significantly improving for local burnup's thermic load, is designed to follower fuel assembly control rod 6, efficiently avoids this and ask
Topic.
In some embodiments, the fuel plate runner gap of the fuel assembly 5 in reactor core can be set to not equal gaps, with
Overcome the problems, such as that the unbalanced distribution of core thermal power is brought.It is a kind of can with set-up mode be, close to irradiation channel or heavy water
Runner gap in the fuel assembly in reflecting layer is greater than the runner gap far from neutron irradiation duct or heavy water reflector.Due to leaning on
Fuel power in nearly irradiation channel is higher, and corresponding cooling requirement is also higher, so runner gap increases, is more advantageous to cold
But, the thermal property of entire reactor core is improved.
In some embodiments, the settable vertical irradiation channel 3 of heavy water reflector is used for Thermal Neutron Irradiation application, simultaneously
The also settable horizontal hole 9 with reactor core cross-sectional periphery horizontal tangential, by thermal neutron by heavy water reflector lead to it is external for
Experimental applications.
Heavy water reflector thermal neutron fluence rate peak value can be improved in setting through the foregoing embodiment, (vertical as shown in Figure 2
Coordinate is thermal neutron fluence rate, and abscissa is the diametrical direction of the middle section Fig. 1 figure), the inlet port of horizontal hole is just arranged in
The peak region of thermal neutron fluence rate substantially increases and provides the space that thermal neutron utilizes.Here it is antineutron trap type researchs
The exemplary embodiments of heap.
In the above-described embodiments, as shown in figure 3, research reactor center fuel module position is replaced with central irradiation
Duct 8, reactor core fission Moderation of the fast neutrons is formed thermal neutron fluence rate peak value by the moderator in the duct, (vertical to sit as shown in Figure 4
It is designated as thermal neutron fluence rate, abscissa is the diametrical direction of the middle section Fig. 3 figure), it is possible to provide the thermal neutron spoke of certain special requirements
According to space.Here it is the exemplary embodiments of neutron well-type research reactor.
8 thermal neutron fluence rate peak value of central irradiation channel among Fig. 4, in addition 3 region of heavy water reflector irradiation channel
Thermal neutron fluence rate peak value shows the embodiment while realizing the research reactor characteristic of antineutron trap and neutron sink reactor core.
It is apparent to those skilled in the art that for convenience and simplicity of description, only with above-mentioned each function
The division progress of module can according to need and for example, in practical application by above-mentioned function distribution by different function moulds
Block is completed, i.e., the internal structure of device is divided into different functional modules, to complete all or part of function described above
Energy.
Particular embodiments described above has carried out into one the purpose of this utility model, technical scheme and beneficial effects
Step is described in detail, it should be understood that the foregoing is merely specific embodiment of the utility model, are not limited to this reality
With novel, within the spirit and principle of the utility model, any modification, equivalent substitution, improvement and etc. done should all include
It is within the protection scope of the utility model.
Claims (9)
1. a kind of research reactor, comprising:
The fuel reactor core of compact Layout and the heavy water reflector being arranged around reactor core；Wherein,
Fast neutron irradiated duct is arranged in the heap in-core, provides fast neutron irradiated space；
Vertical and/or horizontal hole is set in the heavy water reflector, the space of thermal neutron application is provided.
2. research reactor according to claim 1, which is characterized in that the reactor core includes:
Multiple fuel assemblies, it is adjacent to each other to each other, array compact Layout structure is formed, which is located at reactor core appearance
In device；
The fast neutron irradiated duct is set to except array architecture fuel assembly but is located within core vessel.
3. research reactor according to claim 2, which is characterized in that the array architecture fuel assembly with
Aluminium filler plug is provided between core vessel.
4. research reactor according to claim 2, which is characterized in that the fuel used in the fuel assembly is low
Dense uranium.
5. research reactor according to claim 2, which is characterized in that the fuel assembly is plate fuel assembly.
6. research reactor according to claim 2, which is characterized in that the fuel sheet separation of the fuel assembly, if
It is calculated as not equal gaps runner.
7. research reactor according to claim 1, which is characterized in that the heavy water reflector irradiation channel is except vertical
Setting is outer, also sets up the horizontal hole with reactor core cross-sectional periphery arranged tangential, thermal neutron is led to outside heavy water reflector.
8. research reactor according to claim 2, feature further include:
Multiple control rod follower fuel assemblies, are set to inside array fuel assembly, to realize control and the guarantor of reactor
Hold the characteristic of its compact cores.
9. research reactor according to claim 1, which is characterized in that fuel reactor core center replaces with central spoke
According to duct, Thermal Neutron Irradiation application space is provided.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920184628.XU CN209607418U (en) | 2019-02-01 | 2019-02-01 | Research reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920184628.XU CN209607418U (en) | 2019-02-01 | 2019-02-01 | Research reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN209607418U true CN209607418U (en) | 2019-11-08 |
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| CN201920184628.XU Active CN209607418U (en) | 2019-02-01 | 2019-02-01 | Research reactor |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109859860A (en) * | 2019-02-01 | 2019-06-07 | 中国原子能科学研究院 | Research reactor |
| CN111508621A (en) * | 2020-04-28 | 2020-08-07 | 中国原子能科学研究院 | Reactor core |
-
2019
- 2019-02-01 CN CN201920184628.XU patent/CN209607418U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109859860A (en) * | 2019-02-01 | 2019-06-07 | 中国原子能科学研究院 | Research reactor |
| CN111508621A (en) * | 2020-04-28 | 2020-08-07 | 中国原子能科学研究院 | Reactor core |
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