CN109859860A - Research reactor - Google Patents
Research reactor Download PDFInfo
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- CN109859860A CN109859860A CN201910106353.2A CN201910106353A CN109859860A CN 109859860 A CN109859860 A CN 109859860A CN 201910106353 A CN201910106353 A CN 201910106353A CN 109859860 A CN109859860 A CN 109859860A
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- Prior art keywords
- core
- reactor
- fuel
- neutron
- heavy water
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- 238000011160 research Methods 0.000 title claims abstract description 33
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 claims abstract description 54
- 239000000446 fuel Substances 0.000 claims description 52
- 238000000429 assembly Methods 0.000 claims description 21
- 230000000712 assembly Effects 0.000 claims description 21
- 239000011148 porous material Substances 0.000 claims description 17
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 5
- 229910052782 aluminium Inorganic materials 0.000 claims description 5
- 229910052770 Uranium Inorganic materials 0.000 claims description 4
- 239000000945 filler Substances 0.000 claims description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 4
- 238000001228 spectrum Methods 0.000 abstract description 5
- 238000002474 experimental method Methods 0.000 abstract description 4
- 230000004992 fission Effects 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 230000004907 flux Effects 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000002349 favourable effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000001956 neutron scattering Methods 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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 present invention 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
The present disclosure relates to the field of nuclear applications, and further relates to a research reactor.
Background
At present, research reactors comprise two types of neutron traps and anti-neutron traps, and the anti-neutron trap type reactor is a type of reactor which is favored internationally. This type of stack typically uses a compact core of high enriched uranium, as opposed to a neutron trap stack, which forms a neutron fluence peak in the core, where a large number of fission neutrons are not sufficiently moderated in the core, but rather enter the moderator surrounding the core to be moderated to form a high neutron fluence peak, which is the source of the anti-neutron trap stack. Currently, this research reactor is mainly used internationally to carry out neutron scattering experiments, so it is also called neutron beam flow pattern research reactor, but its use is single, and it can not adapt to the application of many demands.
Disclosure of Invention
Technical problem to be solved
In view of the above, it is an object of the present disclosure to provide a research reactor to at least partially solve the above technical problems.
(II) technical scheme
To achieve the above object, the present invention provides a research reactor comprising:
a compactly arranged core and a heavy water reflecting layer disposed around the core; wherein,
a fast neutron irradiation pore canal is arranged in the reactor core to provide a fast neutron irradiation space;
vertical and/or horizontal pore canals are/is arranged in the heavy water reflecting layer to provide thermal neutron irradiation and experimental application space.
In a further embodiment, the core comprises: a plurality of fuel assemblies in close proximity to one another forming an array of compact arrangements, the array being located within the core vessel; the fast neutron irradiation pore canal is arranged outside the array-structured fuel assembly reactor core and is positioned in the reactor core container.
In a further embodiment, an aluminum filler plug is disposed between the array-structured fuel assemblies and the core vessel.
In further embodiments, the research reactor further comprises: the central fuel assembly is replaced with a central irradiation tunnel providing thermal neutron fluence rate peak space.
In a further embodiment, the fuel assembly is a plate fuel assembly.
In a further embodiment, the fuel of the fuel assembly is low enriched uranium.
In a further embodiment, the fuel plate gaps of the fuel assembly are arranged as unequal gap flow channels to solve the problem of unequal thermal power distribution.
In a further embodiment, the heavy water reflecting layer irradiation hole channel is provided with a horizontal hole channel which is arranged tangentially to the circumference of the cross section of the reactor core besides being arranged in the vertical direction so as to lead out thermal neutrons to the outside of the heavy water reflecting layer.
In further embodiments, the research reactor further comprises: and the control rod follower fuel assemblies are arranged in the array fuel assemblies so as to realize the control of the reactor and maintain the characteristics of a compact reactor core of the reactor.
In a further embodiment, the central location of the fuel core is replaced with a central irradiation tunnel, providing a thermal neutron irradiation application space.
(III) advantageous effects
The fast neutron irradiation pore canal is arranged in the reactor core, and the heavy water reflecting layer irradiation pore canal is arranged in the heavy water reflecting layer, so that the energy spectrum separation of the compact reactor core is realized, and neutrons (fast neutrons and thermal neutrons) with different energy spectrums can be utilized to meet the experiments of various requirements;
the reactor core characteristics of the anti-neutron trap and the neutron trap are realized simultaneously by replacing the fuel assembly at the center of the reactor core with a central irradiation pore channel;
the research reactor adopts the plate-shaped fuel assembly and low-enriched uranium to meet the design requirement of a compact small-size reactor core.
Drawings
FIG. 1 is a top view of an anti-neutron trap type research reactor in accordance with an embodiment of the present invention.
Fig. 2 is a graph of the investigational reactor thermal neutron fluence rate profile of fig. 1.
Fig. 3 is a top view of a research reactor with simultaneous implementation of anti-neutron and neutron trap types according to an embodiment of the present invention.
Fig. 4 is a graph of the investigational reactor thermal neutron fluence rate profile of fig. 3.
Detailed Description
The technical solutions in the embodiments of the present invention are clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments of the present invention without making any creative effort, shall fall within the protection scope of the present invention.
The research reactor (also referred to as a research reactor) according to the present invention is a nuclear reactor for the purpose of research and development.
According to the basic concept of the invention, a research reactor is provided, and multiple utilization purposes of neutrons are achieved by arranging neutron irradiation pore canals in the heavy water reflecting layers inside and outside the reactor core.
FIG. 1 is a top view of a research reactor in accordance with an embodiment of the present invention. As shown in fig. 1, the research reactor includes: a core vessel 7 containing a compactly arranged fuel core and a heavy water reflecting layer 1 disposed around the core; wherein, a fast neutron irradiation pore canal 2 is arranged in the reactor core container 7 to provide a fast neutron irradiation space; the heavy water reflecting layer 1 is internally provided with a heavy water reflecting layer vertical irradiation pore canal 3 and/or a horizontal pore canal 9, so as to provide a thermal neutron irradiation space and extract thermal neutrons.
The compactly arranged fuel core contained in the core container 7 is a core structure commonly used in nuclear reaction, is used for performing nuclear fission reaction in the core container, can generate neutrons with higher neutron energy in the reaction process, namely the neutron energy spectrum is hard, and can be called fast neutrons, and the fast neutron irradiation pore channel 2 is arranged in an aluminum filling plug in the core container, so that the neutrons with the hard neutron energy spectrum are provided.
The compact arrangement is such that the fuel assemblies within the core vessel 7 are closely spaced such that fission neutrons generated during the fission reaction of the fuel are not sufficiently moderated within the core vessel 7 and leak outside the core vessel 7 to be sufficiently moderated to form thermal neutrons.
In addition, the heavy water reflecting layer 1 is arranged around the outside of the reactor core container 7, and is used as a moderator to collide with neutrons coming out of the fuel reactor core, so that the energy of the neutrons is reduced, and thermal neutrons with relatively low energy are formed. In the embodiment of the invention, the heavy water reflecting layer irradiation pore channel 3 is arranged on the heavy water reflecting layer 1, so that thermal neutrons with higher fluence rate can be obtained, and the thermal neutrons are applied to an experimental environment with thermal neutron demand, which is the source of an anti-neutron trap type reactor.
In some embodiments, the core vessel 7 includes a plurality of fuel assemblies 5, the fuel assemblies are close to each other to form an array structure (the array structure is not strictly the same in number of rows, but is only a compact arrangement), the fast neutron irradiation channels 3 are disposed outside the array structure fuel assemblies 5 but inside the core vessel 7 in the aluminum filler plug 4, the moderating effect is limited because the atomic weight of aluminum is greater than the molecular weight of heavy water, and the neutron energy inside the fast neutron irradiation channels 3 inside the filler plug is still greater than that of the external heavy water reflecting layer. Thus obtaining a fast neutron irradiation space.
In some embodiments, the fuel assembly is a plate fuel assembly; the existing fuel assemblies can be involute fuel assemblies, plate fuel assemblies and rod fuel assemblies, and the inventor analyzes and compares various assemblies and finds that the plate fuel assemblies can meet the requirement of a compact core.
In some embodiments, control rods may be provided within the core vessel 7 at a number of fuel assembly locations within the core fuel assembly array for controlling the reactor; this problem is effectively avoided by designing the control rods of conventional design to follow the bulk fuel assembly control rods 6, taking into account the significant increase in local fuel thermal load caused by the water cavity formed by the control rod lift.
In some embodiments, the fuel plate runner gaps of the fuel assemblies 5 in the core may be set to unequal gaps to overcome the problems associated with unequal distribution of core thermal power. One possible arrangement is that the flow channel gap in the fuel assembly near the irradiation tunnel or the heavy water reflecting layer is larger than the flow channel gap far from the neutron irradiation tunnel or the heavy water reflecting layer. Because the fuel power close to the irradiation pore canal is higher, the corresponding cooling requirement is also higher, so the flow passage clearance is enlarged, the cooling is more favorable, and the thermal performance of the whole reactor core is improved.
In some embodiments, the heavy water reflecting layer can be provided with vertical irradiation channels 3 for thermal neutron irradiation application, and can also be provided with horizontal channels 9 which are horizontally tangential to the circumference of the cross section of the reactor core and lead thermal neutrons out of the heavy water reflecting layer to the outside for experimental application.
Through the arrangement of the embodiment, the peak value of the thermal neutron flux rate of the heavy water reflecting layer can be improved, as shown in fig. 2 (the ordinate is the thermal neutron flux rate, and the abscissa is the diameter direction of the cross-sectional view in fig. 1), the introduction ports of the horizontal pore channels are arranged in the peak area of the thermal neutron flux rate, and the space for providing thermal neutron utilization is greatly increased. This is a typical embodiment of an anti-neutron trap type research stack.
In the above embodiment, the central fuel assembly location of the research reactor is replaced by a central irradiation tunnel 8, as shown in fig. 3, in which moderator moderates the core fission fast neutrons to form a peak thermal neutron fluence rate, as shown in fig. 4 (thermal neutron fluence rate on ordinate, and diameter direction on abscissa in cross-section in fig. 3), which may provide some special thermal neutron irradiation space. This is a typical embodiment of a neutron trap type research stack.
The thermal neutron fluence rate peak in the central irradiation tunnel 8 in the middle of fig. 4, plus the thermal neutron fluence rate peak in the region of the heavy water reflecting layer irradiation tunnel 3, indicates that the embodiment simultaneously realizes the research reactor characteristics of the anti-neutron trap and the neutron trap cores.
It will be clear to those skilled in the art that, for convenience and simplicity of description, the foregoing division of the functional modules is merely used as an example, and in practical applications, the above function distribution may be performed by different functional modules according to needs, that is, the internal structure of the device is divided into different functional modules to perform all or part of the above described functions.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are only exemplary embodiments of the present invention and are not intended to limit the present invention, and any modifications, equivalents, improvements and the like made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (9)
1. A research reactor, comprising:
a compactly arranged fuel core and a heavy water reflector disposed around the core; wherein,
a fast neutron irradiation pore channel is arranged in the reactor core to provide space for fast neutron irradiation;
vertical and/or horizontal pore channels are arranged in the heavy water reflecting layer, so that space for applying thermal neutrons is provided.
2. The research reactor of claim 1, wherein the core comprises:
a plurality of fuel assemblies in close proximity to one another forming an array of compact arrangements, the array being located within the core vessel;
the fast neutron irradiation pore canal is arranged outside the array-structured fuel assembly and is positioned in the reactor core container.
3. The research reactor of claim 2, wherein an aluminum filler plug is disposed between the array-structured fuel assemblies and the core vessel.
4. The research reactor of claim 1, wherein the fuel used within the fuel assembly is low enriched uranium.
5. The research reactor of claim 2, wherein the fuel assemblies are plate fuel assemblies.
6. The research reactor of claim 1, wherein the fuel plate gap of the fuel assembly is designed as an unequal gap flow channel.
7. The research reactor of claim 1, wherein said heavy water reflecting layer irradiation tunnel is provided with a horizontal tunnel arranged tangentially to the circumference of the core cross-section in addition to being vertically disposed to guide thermal neutrons out of the heavy water reflecting layer.
8. The research reactor of claim 2, further comprising:
and the control rod follower fuel assemblies are arranged in the array fuel assemblies so as to realize the control of the reactor and maintain the characteristics of a compact reactor core of the reactor.
9. The research reactor of claim 1, wherein the center location of the fuel core is replaced with a central irradiation tunnel providing a space for application of thermal neutron irradiation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910106353.2A CN109859860A (en) | 2019-02-01 | 2019-02-01 | Research reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910106353.2A CN109859860A (en) | 2019-02-01 | 2019-02-01 | Research reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN109859860A true CN109859860A (en) | 2019-06-07 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
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| CN201910106353.2A Pending CN109859860A (en) | 2019-02-01 | 2019-02-01 | Research reactor |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114488271A (en) * | 2022-01-04 | 2022-05-13 | 中国原子能科学研究院 | Method for establishing thermal neutron reference radiation field |
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Cited By (1)
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