CN112366013B - Nuclear test method suitable for heat pipe reactor - Google Patents
Nuclear test method suitable for heat pipe reactor Download PDFInfo
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- CN112366013B CN112366013B CN202011245780.8A CN202011245780A CN112366013B CN 112366013 B CN112366013 B CN 112366013B CN 202011245780 A CN202011245780 A CN 202011245780A CN 112366013 B CN112366013 B CN 112366013B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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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
Abstract
The invention discloses a nuclear test method suitable for a heat pipe reactor, which comprises the following steps: connecting the reactor core for testing with a thermoelectric conversion device or a cooling device through heat pipes according to the design proportion of the heat pipe stack to form a heat pipe stack nuclear test device; the heat pipe reactor nuclear test device is coupled with the existing research reactor or neutron source, and the nuclear integrated test can be directly carried out without building a test reactor. The invention adopts the heat pipe reactor local subcritical module, combines the existing research reactor or other neutron sources, can directly carry out the nuclear integrated test without building the experimental reactor, carries out rapid verification iteration on the design, can effectively reduce the test cost, and improves the research and development speed and the design accuracy.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor physical tests, and particularly relates to a nuclear test method suitable for a heat pipe reactor.
Background
The technical verification of the novel reactor generally needs a plurality of steps such as a local non-nuclear test, a non-nuclear integration test, a nuclear integrated test and the like, the construction of the test reactor and the development of the nuclear test are key links for research and development of the novel reactor, the required research and development period is long, the nuclear fuel consumption is high, the cost is large, and the influence on the research and development progress of the whole design is large.
Disclosure of Invention
In order to shorten the research and development period of the heat pipe reactor and improve the research and development speed and the design accuracy, the invention provides a nuclear test device and a nuclear test method suitable for the heat pipe reactor. The invention adopts the heat pipe reactor local subcritical module, combines the existing research reactor or other neutron sources, can directly carry out the nuclear integrated test without building the experimental reactor, carries out rapid verification iteration on the design, can effectively reduce the test cost, and improves the research and development speed and the design accuracy.
The invention is realized by the following technical scheme:
a method for a nucleated test suitable for use in a heat pipe reactor, the method comprising:
connecting the reactor core for testing with a thermoelectric conversion device or a cooling device through heat pipes according to the design proportion of the heat pipe stack to form a heat pipe stack nuclear test device;
the heat pipe reactor nuclear test device is coupled with the existing research reactor or neutron source, and the nuclear integrated test can be directly carried out without building a test reactor.
Alternatively, the test core of the present invention is constructed by extracting at least 1 fuel rod in a heat pipe reactor and inserting it into a matrix of a simulated core.
Optionally, the number of heat pipes of the present invention is at least 1.
Optionally, the connection of the core for testing and the thermoelectric conversion device or the cooling device through the heat pipe is specifically as follows:
the evaporation section of the heat pipe is connected with the core for testing; and the condensation section of the heat pipe is connected with the thermoelectric conversion device.
Optionally, the thermoelectric conversion device of the present invention is a thermoelectric power generation device, a stirling power generation device, or a brayton power generation device.
Optionally, a stainless steel sleeve is arranged outside the heat pipe stack nuclear test device to isolate water and air.
Optionally, the coupling connection of the heat pipe stack nuclear test device and the existing research stack is specifically as follows:
and placing the heat pipe reactor nuclear test device into the existing research reactor to enable the test reactor core to be in the active section of the reactor core of the research reactor.
Optionally, the coupling connection of the heat pipe stack nuclear test device and the existing research stack is specifically as follows:
and putting the heat pipe pile nuclear test device into an external irradiation pore channel of the existing research pile.
Optionally, the nuclear integration test of the present invention comprises:
fissioning fuel rods in the test core using neutrons from an existing research or neutron source;
fission heat generated by the fuel rod is conducted away by the heat pipe;
the thermoelectric conversion device or the cooling device converts the heat energy carried by the heat pipe into electric energy or directly brings the electric energy out.
Optionally, the nuclear integration test of the present invention further comprises:
and starting the existing research reactor or neutron source, stabilizing the existing research reactor or neutron source at different power levels, measuring the temperature of the reactor core for the test, the temperature of the heat pipe, the thermoelectric conversion power and the waste heat derived power, and obtaining the operating characteristics and key parameters of the heat pipe reactor.
The invention has the following advantages and beneficial effects:
1. the test method provided by the invention has the advantages that the heat pipe stack nuclear test device (the heat pipe stack local subcritical module) is adopted, the existing research stack or neutron source is combined, the nuclear integrated test is directly carried out under the condition that the test stack is not built, the design is rapidly verified and iterated, the test cost can be effectively reduced, and the research and development speed and the design accuracy are improved. The invention can be widely applied to the heat pipe reactor which needs to be verified by the nuclear technology.
2. According to the invention, the heat pipe reactor local module is placed in the research reactor, the local module is cracked by utilizing the neutron of the research reactor, heat is led out to the heat pipe conversion device through the heat pipe, the power of the heat pipe reactor local module is adjusted by researching the reactor power, the design of the heat pipe reactor, the operating characteristics of the reactor and the like can be directly verified, the research value is better than that of a non-nuclear test, the research and development period can be shortened, the design accuracy is improved, and the technical risk is reduced.
3. The invention adopts a small amount of fuel and the heat pipe, thus effectively reducing the cost of the nuclear test; the invention can verify the design of the heat pipe stack with a core in the early stage of design, directly measure key parameters and improve the research and development speed and the design accuracy; the invention can improve the test capability and safety of the nuclear test under different powers by means of the neutron fission of the research reactor (because the research reactor has perfect power regulation and shutdown protection measures).
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic structural diagram of a heat pipe stack nuclear test device of the present invention.
Reference numbers and corresponding part names in the drawings:
1-thermoelectric conversion device or cooling device, 2-heat pipe, 3-core for test, 4-device supporting structure, and 5-sleeve.
Detailed Description
Hereinafter, the term "comprising" or "may include" used in various embodiments of the present invention indicates the presence of the invented function, operation or element, and does not limit the addition of one or more functions, operations or elements. Furthermore, as used in various embodiments of the present invention, the terms "comprises," "comprising," "includes," "including," "has," "having" and their derivatives are intended to mean that the specified features, numbers, steps, operations, elements, components, or combinations of the foregoing, are only meant to indicate that a particular feature, number, step, operation, element, component, or combination of the foregoing, and should not be construed as first excluding the existence of, or adding to the possibility of, one or more other features, numbers, steps, operations, elements, components, or combinations of the foregoing.
In various embodiments of the invention, the expression "or" at least one of a or/and B "includes any or all combinations of the words listed simultaneously. For example, the expression "a or B" or "at least one of a or/and B" may include a, may include B, or may include both a and B.
Expressions (such as "first", "second", and the like) used in various embodiments of the present invention may modify various constituent elements in various embodiments, but may not limit the respective constituent elements. For example, the above description does not limit the order and/or importance of the elements described. The foregoing description is for the purpose of distinguishing one element from another. For example, the first user device and the second user device indicate different user devices, although both are user devices. For example, a first element could be termed a second element, and, similarly, a second element could be termed a first element, without departing from the scope of various embodiments of the present invention.
It should be noted that: if it is described that one constituent element is "connected" to another constituent element, the first constituent element may be directly connected to the second constituent element, and a third constituent element may be "connected" between the first constituent element and the second constituent element. In contrast, when one constituent element is "directly connected" to another constituent element, it is understood that there is no third constituent element between the first constituent element and the second constituent element.
The terminology used in the various embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the various embodiments of the invention. As used herein, the singular forms are intended to include the plural forms as well, unless the context clearly indicates otherwise. Unless otherwise defined, all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art to which various embodiments of the present invention belong. The terms (such as those defined in commonly used dictionaries) should be interpreted as having a meaning that is consistent with their contextual meaning in the relevant art and will not be interpreted in an idealized or overly formal sense unless expressly so defined herein in various embodiments of the present invention.
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Examples
The Heat Pipe Reactor (HPR) is a solid reactor, and directly conducts heat generated by a reactor core of the reactor to a thermoelectric conversion device in a heat pipe self-heat-transfer (pump-free driving) mode.
The method adopts a heat pipe reactor local subcritical module, combines with the existing research reactor or other neutron sources, directly performs the nuclear-carrying integration test without building the test reactor, performs rapid verification iteration on the design, can effectively reduce the test cost, and improves the research and development speed and the design accuracy.
As shown in fig. 1, the heat pipe stack local subcritical module (heat pipe stack nuclear test device) of the present embodiment includes a thermoelectric conversion device or cooling device 1, heat pipes 2, and a test core 3;
the test core 3 is constructed by extracting a small number of fuel rods (at least 1) from the heat pipe reactor and inserting the extracted fuel rods into a simulated core matrix.
The core 3 for testing is connected with the thermoelectric conversion device or the cooling device 1 through at least 1 heat pipe 2, specifically: the evaporation section of the heat pipe 2 is connected with a thermoelectric conversion device or a cooling device 1, and the condensation section of the heat pipe 2 is connected with a reactor core 3 for testing, so that the heat pipe reactor nuclear test device is formed.
The device support structure 4 is used to support the entire test device.
The sleeve 5 is arranged outside the test device and is made of a stainless steel sleeve to isolate water and air and avoid oxidation.
The thermoelectric conversion device 1 of the present embodiment employs, but is not limited to, a thermoelectric power generation device, a stirling power generation device, or a brayton power generation device.
In this embodiment, the testing device is placed in the active region of the research reactor or near the external irradiation pore channel or other neutron sources, neutrons of the research reactor or neutron sources are used to enable the reactor core simulation body fuel rods to be fissured, fission heat generated by the fuel rods is led out by the heat pipes, and the thermoelectric conversion device or the cooling device connected with the condensation sections of the heat pipes converts heat energy carried by the heat pipes into electric energy or directly brings out the electric energy.
The embodiment adopts a small amount of fuel and the heat pipe, so that the cost of the nuclear test can be effectively reduced.
The method provided by the embodiment carries out verification with a core on the design of the heat pipe stack in the early stage of design, directly measures the key parameters, and can improve the research and development speed and the design accuracy.
In the embodiment, because the research reactor has perfect power regulation and shutdown protection measures, the nuclear test capability and safety under different powers can be improved by researching the fission generated by the reactor neutrons.
Through adjusting the neutron flux level in research reactor, control test device power, can measure and verify with the design key design parameter in the experiment, specifically do: and starting the research reactor, stabilizing the research reactor at different power levels, measuring the core temperature of the heat pipe reactor, the temperature of the heat pipe, the thermoelectric generation power and the waste heat derived power, and obtaining the operating characteristics and key parameters of the heat pipe reactor.
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 merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (9)
1. A method for testing a hot tube reactor with a core, which is characterized by comprising the following steps:
connecting the reactor core for testing with a thermoelectric conversion device or a cooling device through heat pipes according to the design proportion of the heat pipe stack to form a heat pipe stack nuclear test device;
the heat pipe reactor nuclear test device is coupled with the existing research reactor or neutron source, and the nuclear integrated test can be directly carried out without building a test reactor; the test core is formed by inserting at least 1 fuel rod in a simulated core matrix by extracting heat pipe reactor.
2. The method of claim 1, wherein the number of heat pipes is at least 1.
3. The method for testing the nuclear reactor with the heat pipe according to claim 1, wherein the connecting the core for testing with the thermoelectric conversion device or the cooling device through the heat pipe comprises:
the evaporation section of the heat pipe is connected with the core for testing; and the condensation section of the heat pipe is connected with a thermoelectric conversion device or a cooling device.
4. The method of claim 1, wherein the thermoelectric conversion device is a thermoelectric power generation device, a Stirling power generation device, or a Brayton power generation device.
5. The method for testing the hot-pipe reactor with the nuclear reactor as claimed in claim 1, wherein a stainless steel sleeve is arranged outside the hot-pipe reactor testing device to isolate water and air.
6. The method for testing the nuclear reactor of the heat pipe reactor according to claim 1, wherein the coupling connection of the device for testing the nuclear reactor of the heat pipe reactor and the existing research reactor is specifically as follows:
and placing the heat pipe reactor nuclear test device into the existing research reactor to enable the test reactor core to be in the active section of the reactor core of the research reactor.
7. The method for testing the nuclear reactor of the heat pipe reactor according to claim 1, wherein the coupling connection of the device for testing the nuclear reactor of the heat pipe reactor and the existing research reactor is specifically as follows:
and putting the heat pipe pile nuclear test device into an external irradiation pore channel of the existing research pile.
8. The method of claim 1, wherein the nucleated integration test comprises:
fissioning fuel rods in the test core using neutrons from an existing research or neutron source;
fission heat generated by the fuel rod is conducted away by the heat pipe;
the thermoelectric conversion device or the cooling device converts the heat energy carried by the heat pipe into electric energy or directly brings the electric energy out.
9. The method of claim 8, wherein the nucleated integration test further comprises:
and starting the existing research reactor or neutron source, stabilizing the existing research reactor or neutron source at different power levels, measuring the temperature of the reactor core for the test, the temperature of the heat pipe, the thermoelectric conversion power and the waste heat derived power, and obtaining the operating characteristics and key parameters of the heat pipe reactor.
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| CN113776869A (en) * | 2021-10-18 | 2021-12-10 | 中国科学院微小卫星创新研究院 | Non-nuclear on-orbit verification method for space nuclear power platform |
| CN113936822B (en) * | 2021-10-19 | 2022-12-09 | 西安交通大学 | Heat-force performance assessment test device and method for reactor core of heat pipe reactor |
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