CN114420330A - Full natural circulation integrated reactor inlet and outlet temperature measuring device - Google Patents
Full natural circulation integrated reactor inlet and outlet temperature measuring device Download PDFInfo
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- CN114420330A CN114420330A CN202210107647.9A CN202210107647A CN114420330A CN 114420330 A CN114420330 A CN 114420330A CN 202210107647 A CN202210107647 A CN 202210107647A CN 114420330 A CN114420330 A CN 114420330A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
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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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- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of temperature measurement in a small reactor, in particular to a device for measuring the inlet and outlet temperature of a full natural circulation integrated reactor, which comprises: the reactor comprises a pressure vessel, a reactor core support lower plate and a reactor core, wherein the reactor core support lower plate is arranged in the pressure vessel, and the reactor core is arranged above the reactor core support lower plate; a platinum resistance thermometer disposed at a shoulder of the pressure vessel and distal from the reactor core, the platinum resistance thermometer capable of measuring an outlet temperature of the reactor core; a K-type thermocouple disposed below an active area of a reactor core and above the core support lower plate, the K-type thermocouple capable of measuring an inlet temperature of the reactor core. The invention can accurately and reliably measure the temperature of the inlet and the outlet of the reactor.
Description
Technical Field
The invention relates to the technical field of temperature measurement in a small reactor, in particular to a device for measuring the inlet and outlet temperature of a full natural circulation integrated reactor.
Background
The temperature of the inlet and the outlet of the reactor is mainly used as a parameter for controlling and protecting a nuclear power plant and is also used for calculating the thermal power of the reactor, and the temperature is an important parameter for the safe operation of the reactor. In summary, the temperature measurement of the integrated full natural circulation reactor must not be affected by the high irradiation environment, and the arrangement position and the number are reasonable, so that the accurate temperature parameter can be obtained, and therefore, a device for measuring the inlet and outlet temperature of the full natural circulation integrated reactor is needed.
There are the following problems:
1. it is inconvenient to accurately and reliably measure the temperature of the inlet and the outlet of the reactor.
Disclosure of Invention
Aiming at the defects of the prior art, the invention provides a full natural circulation integrated reactor inlet and outlet temperature measuring device, which solves the problem that the reactor inlet and outlet temperature is inconvenient to accurately and reliably measure.
In order to achieve the purpose, the invention provides the following technical scheme:
a full natural circulation integrated reactor inlet and outlet temperature measuring device comprises:
the reactor comprises a pressure vessel, a reactor core support lower plate and a reactor core, wherein the reactor core support lower plate is arranged in the pressure vessel, and the reactor core is arranged above the reactor core support lower plate;
a platinum resistance thermometer disposed at a shoulder of the pressure vessel and distal from the reactor core, the platinum resistance thermometer capable of measuring an outlet temperature of the reactor core;
a K-type thermocouple disposed below an active area of a reactor core and above the core support lower plate, the K-type thermocouple capable of measuring an inlet temperature of the reactor core.
In a preferred embodiment of the present invention, an in-core measuring guide duct is vertically formed in the pressure vessel, the K-type thermocouple is formed in the in-core measuring guide duct, and a bottom of the K-type thermocouple passes through the core active region of the reactor and is fixed above the core support lower plate.
As a preferable technical scheme of the invention, the number of the K-type thermocouples is 10-18.
As a preferred technical scheme of the invention, a two-loop heat exchange assembly is arranged in the pressure vessel, a primary loop coolant is arranged in the pressure vessel, and the primary loop coolant can realize natural circulation by virtue of density difference.
As a preferred technical solution of the present invention, the platinum resistance thermometers are fixed at the inlet positions of the two-loop heat exchange assembly and are uniformly distributed in the circumferential direction of the pressure vessel.
As a preferable technical scheme of the invention, the number of the platinum resistance thermometers is 8-10.
Compared with the prior art, the invention has the following beneficial effects:
the invention sets platinum resistance thermometer on the shoulder of the pressure vessel, uses the platinum resistance thermometer to measure the outlet temperature of the reactor core, sets K-type thermocouple under the active area of the reactor core and above the core support lower plate, and uses the K-type thermocouple to measure the inlet temperature of the reactor core, thereby accurately and reliably measuring the inlet and outlet temperatures of the reactor.
Drawings
FIG. 1 is a schematic structural view of the present invention;
FIG. 2 is a schematic view of the circumferential arrangement of reactor outlet temperature measurements according to the present invention;
FIG. 3 is a schematic view of a reactor inlet temperature measurement arrangement of the present invention;
FIG. 4 is a schematic diagram of a type K thermocouple of the present invention in the channel of a measurement conduit in a stack.
Detailed Description
The technical solutions in the embodiments of the present invention will be 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 of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1-4, in this embodiment: a full natural circulation integrated reactor inlet and outlet temperature measuring device comprises:
the reactor comprises a pressure vessel 1, wherein a reactor core supporting lower plate 2 is installed inside the pressure vessel 1, and a reactor core 3 is arranged above the reactor core supporting lower plate 2;
a platinum resistance thermometer 4 disposed at a shoulder of the pressure vessel 1 and distal from the reactor core 3, the platinum resistance thermometer 4 capable of measuring an outlet temperature of the reactor core 3; in this embodiment, the platinum resistance thermometer 4 is far from the active area of the reactor core 3, and the gamma irradiation dose has little influence on the measurement accuracy.
A K-type thermocouple 5 disposed below an active area of the reactor core 3 and above the core support lower plate 2, the K-type thermocouple 5 being capable of measuring an inlet temperature of the reactor core 3. In this embodiment, the reactor inlet temperature is measured as a control parameter, and a K-type thermocouple 5 with good irradiation resistance is used for measurement, where the K-type thermocouple 5 is closer to the reactor core 3, and the surrounding metal is heated after being irradiated, so that the measured temperature is higher, but the uncertainty requirement as the control parameter can be satisfied.
In the present invention, the platinum resistance thermometer 4 is installed on the shoulder of the pressure vessel 1, the outlet temperature of the reactor core 3 is measured by the platinum resistance thermometer 4, the K-type thermocouple 5 is installed below the active area of the reactor core 3 and above the core support lower plate 2, and the inlet temperature of the reactor core 3 is measured by the K-type thermocouple 5, so that the inlet and outlet temperatures of the reactor can be accurately and reliably measured.
In an embodiment of the invention, the pressure vessel 1 is vertically provided with an in-core measuring guide duct channel 6 in the inside, the K-type thermocouple 5 is arranged in the in-core measuring guide duct channel 6, and the bottom of the K-type thermocouple 5 passes through the core 3 active area of the reactor and is fixed above the core support lower plate 2. In particular, the K-type thermocouple 5 is integrated with other in-reactor measuring instruments and extends to the bottom of the reactor core 3 along the in-reactor measuring conduit channel 6, so that the measurement operation is simple and the use is more convenient.
Optionally, the number of the K-type thermocouples 5 is 10-18.
In an embodiment of the present invention, a first and a second loop heat exchange assemblies 7 are arranged inside the pressure vessel 1, and a first loop coolant is arranged inside the first and the second loop heat exchange assemblies 7, and the first loop coolant can realize natural circulation by virtue of a density difference. In this embodiment, after the primary coolant passes through the core support lower plate 2 and enters the reactor core 3, the temperature of the inlet of the reactor core 3 can be measured by the K-type thermocouple 5; the primary coolant flows through the reactor core 3 to be heated and continues to flow upwards, and the temperature of the outlet of the reactor core 3 can be measured by the platinum resistance thermometer 4 before flowing to the inlet of the secondary heat exchange assembly 7.
In an embodiment of the present invention, the platinum resistance thermometers 4 are fixed at the inlet positions of the two-loop heat exchange assembly 7 and are uniformly distributed in the circumferential direction of the pressure vessel 1. In this embodiment, the temperature of the primary coolant of the first and second loop heat exchange assemblies 7 is equal to the outlet temperature of the reactor core 3, and the temperature distribution is uniform.
In the invention, holes can be opened on the shoulder part of the pressure container 1 and uniformly arranged in the circumferential direction, and the number of the holes is 8-10. A platinum resistance thermometer 4 was attached to the opening through a sleeve. The number of the platinum resistance thermometers 4 is 8-10, so that more accurate reactor core outlet temperature parameters can be obtained, and the uncertainty requirement as a protection parameter can be met.
Finally, it should be noted that: although the present invention has been described in detail with reference to the foregoing embodiments, those skilled in the art will understand that various changes, modifications and substitutions can be made without departing from the spirit and scope of the invention as defined by the appended claims. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (6)
1. The utility model provides a full natural circulation integration reactor inlet and outlet temperature measuring device which characterized in that includes:
the reactor comprises a pressure vessel (1), wherein a reactor core supporting lower plate (2) is installed inside the pressure vessel (1), and a reactor core (3) is arranged above the reactor core supporting lower plate (2);
a platinum resistance thermometer (4) arranged at a shoulder of the pressure vessel (1) and remote from the reactor core (3), the platinum resistance thermometer (4) being capable of measuring an outlet temperature of the reactor core (3);
a K-type thermocouple (5) disposed below an active area of a reactor core (3) and above the core support lower plate (2), the K-type thermocouple (5) being capable of measuring an inlet temperature of the reactor core (3).
2. The full natural circulation integrated reactor inlet and outlet temperature measuring device according to claim 1, characterized in that: an in-core measuring guide pipe channel (6) vertically penetrates through the pressure vessel (1), the K-type thermocouple (5) penetrates through the in-core measuring guide pipe channel (6), and the bottom of the K-type thermocouple (5) penetrates through the core (3) active area of the reactor and is fixed above the core support lower plate (2).
3. The full natural circulation integrated reactor inlet and outlet temperature measuring device according to claim 2, characterized in that: the number of the K-type thermocouples (5) is 10-18.
4. The full natural circulation integrated reactor inlet and outlet temperature measuring device according to claim 1, characterized in that: the pressure vessel (1) is internally provided with a two-loop heat exchange assembly (7), a loop coolant is arranged in the pressure vessel (1), and the loop coolant can realize natural circulation by means of density difference.
5. The full natural circulation integrated reactor inlet and outlet temperature measuring device according to claim 4, characterized in that: the platinum resistance thermometers (4) are fixed at the inlet positions of the two-loop heat exchange assembly (7) and are uniformly distributed in the circumferential direction of the pressure container (1).
6. The full natural circulation integrated reactor inlet and outlet temperature measuring device according to claim 5, characterized in that: the number of the platinum resistance thermometers (4) is 8-10.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210107647.9A CN114420330A (en) | 2022-01-28 | 2022-01-28 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210107647.9A CN114420330A (en) | 2022-01-28 | 2022-01-28 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
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| Publication Number | Publication Date |
|---|---|
| CN114420330A true CN114420330A (en) | 2022-04-29 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210107647.9A Pending CN114420330A (en) | 2022-01-28 | 2022-01-28 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115410728A (en) * | 2022-08-30 | 2022-11-29 | 上海核工程研究设计院有限公司 | Full natural circulation reactor body system |
| CN115410728B (en) * | 2022-08-30 | 2024-06-07 | 上海核工程研究设计院股份有限公司 | Full natural circulation reactor body system |
-
2022
- 2022-01-28 CN CN202210107647.9A patent/CN114420330A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115410728A (en) * | 2022-08-30 | 2022-11-29 | 上海核工程研究设计院有限公司 | Full natural circulation reactor body system |
| CN115410728B (en) * | 2022-08-30 | 2024-06-07 | 上海核工程研究设计院股份有限公司 | Full natural circulation reactor body system |
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Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |