CN103871526A - Detection apparatus for neutron flux and temperature of reactor core - Google Patents
Detection apparatus for neutron flux and temperature of reactor core Download PDFInfo
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- CN103871526A CN103871526A CN201210540619.2A CN201210540619A CN103871526A CN 103871526 A CN103871526 A CN 103871526A CN 201210540619 A CN201210540619 A CN 201210540619A CN 103871526 A CN103871526 A CN 103871526A
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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 invention relates to a detection apparatus for a neutron flux and a temperature of a reactor core. The detection apparatus comprises an assembly housing, a self-powered neutron detector set, an internal sealing structure, a connector and a terminal portion sealing plug, wherein the self-powered neutron detector set is fixed inside the assembly housing and comprises N self-powered neutron detectors, the N self-powered neutron detectors are uniformly arranged at intervals from bottom to top along the axial direction of the assembly housing, the connector is sealedly fixed on the upper end of the assembly housing, the terminal portion sealing plug is sealedly fixed on the lower end of the assembly housing, the internal sealing structure is sealedly fixed in the internal of the assembly housing positioned above the self-powered neutron detector set, and the armoured cables of the N rhodium self-powered neutron detectors are bundled up and fixed, upwardly extend along the axial direction of the assembly housing, penetrate through the internal sealing structure, and finally are fixed on the pin of the connector. According to the present invention, the neutron flux change of the reactor core can be rapidly responded, the reactor core neutron flux and the fuel assembly outlet temperature can be real-timely measured, and the design requirements of the transmission cable can be reduced.
Description
Technical field
The present invention relates to nuclear power station reactor core neutron flux and temperature survey field, be specifically related to a kind of sniffer for reactor core neutron flux and temperature.
Background technology
Conventionally at nuclear power station reactor core, reactor core neutron and temperature measuring instrument can be set, be used for measuring reactor core neutron flux and fuel assembly outlet temperature, the signal measuring is for monitoring the reactor operation situations such as the three-dimensional power distribution of reactor core, Core cooling state.
The measurement instrument type difference that the nuclear power station of different heap types arranges.Existing metering system is, adopt and insert thermopair from top, insert the metering system of Miniature movable fission chamber from bottom, measure fuel assembly outlet temperature and reactor core neutron flux, what all adopt the nuclear power second phase as Qinshan Phase II NPP second phase and ridge Australia is this kind of metering system and measurement instrument accordingly.Adopt this metering system and measurement instrument, need to be in pressure vessel bottom opening, a large amount of pipes that runs through is set, will increase the risk of reactor coolant leakage.
Along with improving constantly and technical progress that nuclear plant safety is required, reduce the risk of reactor coolant leakage, the instrument of core temperature and neutron measurement need to be placed on reactor core, be that in-pile instrument runs through and enters reactor core from top, do not allow pressure vessel sidewall and bottom opening below main pipeline.And then need to adapt to the new neutron flux of this constructive variations and the sniffer of temperature.
Summary of the invention
The technical matters that will solve of the present invention is to provide and a kind ofly can enters reactor core and be fixed on heap in-core, respond the variation of reactor core neutron flux fast, measure reactor core neutron flux and fuel assembly outlet temperature in real time from heap tip cutting, and reduces the detector that heap backs down hole number, reduces the designing requirement to transmission cable.
In order to solve the problems of the technologies described above, technical scheme of the present invention is that a kind of sniffer for reactor core neutron flux and temperature, comprises package shell, self-power neutron detector group, internal seal structure, connector, end part seal plug;
Described self-power neutron detector group is fixed in described package shell, and it comprises N self-power neutron detector, a described N self-power neutron detector along described package shell axially from bottom to top evenly interval arrange; The vertical range of the lower surface, sensitive section of centre distance reactor fuel assemblies active region of i rhodium self-power neutron detector is from bottom to top
wherein i=1,2,3 ..., N, H is the axial height of reactor fuel assemblies active region;
Described connector sealing is fixed on the upper end of described package shell; Described end part seal plug sealing is fixed on the lower end of described package shell;
Described internal seal structure sealing is fixed on the inside of the described package shell that is positioned at described self-power neutron detector group top;
The sheathed cable of described N rhodium self-power neutron detector is tied up and fixes, and axially upwards extends along described package shell, through described internal seal structure, is finally fixed on the stitch of described connector.
Also comprise being fixed in described package shell being positioned at described internal seal structure upper area cold junction compensation device, described cold junction compensation device comprises 4 lead-in wires; Described 4 lead-in wires are connected respectively on 4 stitch of described connector.
Described cold junction compensation device is Pt100 four-wire system thermometer.
Also comprise and be fixed on the thermopair that is positioned at described internal seal structure lower zone in described package shell; Described thermopair is connected on the stitch of described connector by thermopair extended line.
Described end part seal plug is bullet shaped structure, and its outside surface is through polishing grinding processing.
Described package shell comprises the first sleeve and the second sleeve; Described the first sleeve is axial equal diameter sleeve structure; Described the second sleeve comprises a major diameter sleeve structure, a minor diameter sleeve structure and is connected the conical surface tubular construction of described major diameter sleeve structure and described minor diameter sleeve structure; Described minor diameter sleeve structure end is tightly fixed in the upper end of described the first sleeve.
Described second sleeve outer surface of described connector bottom is provided with first ring connected in star, is provided with the second annular groove at the second sleeve outer surface that is positioned at described first ring connected in star bottom.
The minor diameter tube-in-tube structure of described the second sleeve as with the sealing station of described containment vessel penetration piece.
Beneficial effect of the present invention:
(1) a kind of sniffer for reactor core neutron flux and temperature of the present invention can enter reactor core and be fixed on heap in-core, responds the variation of reactor core neutron flux fast, measures reactor core neutron flux and fuel assembly outlet temperature in real time from heap tip cutting;
(2) be integrated in a detector assembly by the neutron detector for measuring neutron flux with for thermometric thermopair and for the device of cold junction compensation, reduce heap and back down hole number and reduce the designing requirement to transmission cable;
(3) signal that utilizes this detector assembly to obtain, can realize and calculate the three-dimensional power distribution of reactor core, fuel assembly linear power density (LPD), departure from nucleate boiling ratio (DNBR), the functions such as monitoring Core cooling situation.
Accompanying drawing explanation
Fig. 1 is the schematic diagram of a kind of sniffer for reactor core neutron flux and temperature of the present invention;
Fig. 2 is the outside schematic diagram of a kind of sniffer for reactor core neutron flux and temperature of the present invention;
Fig. 3 is the schematic diagram in containment that is installed on of a kind of sniffer for reactor core neutron flux and temperature of the present invention.
In figure: 1-plug connector, 2-cold junction compensation device, 3-internal seal structure, 4-thermopair, 401-thermopair extended line, 5-package shell, 501-the first sleeve, 502-the second sleeve, 503-first ring connected in star, 504-the second annular groove, 6-self-power neutron detector group, 7-end part seal plug, 8-fuel assembly active region, 9-pressure vessel, 901-upper cover.
Embodiment
Below in conjunction with Fig. 1, Fig. 2 and embodiment, the present invention is described further.
In nuclear power plant reactor, be provided with a kind of reactor core neutron and temperature detection device that is used for measuring reactor core neutron flux and fuel assembly outlet temperature.
A kind of sniffer for reactor core neutron flux and temperature of the present invention, comprises package shell 5, self-power neutron detector group 6, thermopair 4, internal seal structure 3, cold junction compensation device 2, connector 1, end part seal plug 7 as shown in Figure 1;
Described package shell 5 comprises the first sleeve 501 and the second sleeve 502; Described the first sleeve 501 is axial equal diameter sleeve structure; Described the second sleeve 502 comprises a major diameter sleeve structure, a minor diameter sleeve structure and is connected the conical surface tubular construction of described major diameter sleeve structure and described minor diameter sleeve structure; Described minor diameter sleeve structure end is tightly enclosed within the upper end of described the first sleeve 501, and by being welded and fixed; Described end part seal plug 7 is bullet-shaped structure, and its end face is welded on the lower end of described the first sleeve 501, and the first sleeve 501 is sealed; The outside surface of end part seal plug 7, through polishing grinding processing, to meet the requirement of surfaceness, reduces the friction of assembly insertion instrument conduit.Described the first sleeve 501 and the second sleeve 502 adopt stainless steel material.
Described self-power neutron detector group 6 is fixed in described the first sleeve 501, and it comprises N rhodium self-power neutron detector (SPND), described N rhodium self-power neutron detector along described the first sleeve 501 axially from bottom to top evenly interval arrange; Wherein, N according to core height and measure require difference and determine, generally get 3～7, Fig. 1 is take N=7 as example.
In the time that the sniffer for reactor core neutron flux and temperature of the present invention is installed on reactor, sensitive section of axial centre of its i rhodium self-power neutron detector from bottom to top apart from the vertical range of 8 lower surfaces, reactor fuel assemblies active region is
wherein i=1,2,3 ..., N; H is the axial height of reactor fuel assemblies active region 8;
Described internal seal structure 3 is fixed in the major diameter sleeve pipe of tapered tube superstructure of described the second sleeve 502, and carries out encapsulation process with the tube wall of described the second sleeve 502; Described thermopair 4 is fixed on the region that is positioned at described internal seal structure 3 belows in described the first sleeve 501; Described cold junction compensation device 2 is fixed on the region that is positioned at described internal seal structure 3 tops in described the second sleeve 502; Described cold junction compensation device 2 adopts Pt100 four-wire system thermometer, and it is for the cold junction temperature of Compensative thermoelectric couple.
Described connector 1 comprises multiple stitch, and this connector 1 is welded on the upper end of described the second sleeve 502.4 lead-in wires of described Pt100 four-wire system thermometer by connection to the stitch of described connector 1.
Thermopair 4 is connected with one end of thermopair extended line 401, and the other end of described thermopair extended line 401 is connected with 1 stitch of described connector 1 through described internal seal structure 3;
The sheathed cable of described N rhodium self-power neutron detector is tied up and fixes, and axially upwards extends along described the first sleeve 501 and the second sleeve 502, through described internal seal structure 3, is finally welded on the stitch of connector 1.
The outside of the sniffer for reactor core neutron flux and temperature of the present invention can be as shown in Figure 2; Be provided with first ring connected in star 503 at described the second sleeve 502 outside surfaces that are positioned at described connector 1 bottom, be provided with the second annular groove 504 at the second sleeve 502 outside surfaces that are positioned at described first ring connected in star 503 bottoms; Described first ring connected in star 503 for reactor roof bracing or strutting arrangement; Described the second annular groove 504 is for coordinating with reactor lifting device;
As shown in Figure 3, the present invention penetrates containment vessel upper cover 901 and enters in the gauge pipe in fuel assembly for end part seal plug 7 one end of the sniffer of reactor core neutron flux and temperature, make each rhodium self-powered detector all in appropriate position, thereby reactor core is monitored; The minor diameter tube-in-tube structure outside surface of described the second sleeve 502 is as the sealing station that carries out cutting ferrule sealing with described containment vessel upper cover 901, with the sealing with realizing sniffer of the present invention and containment upper cover 901.
Claims (8)
1. for a sniffer for reactor core neutron flux and temperature, it is characterized in that: comprise package shell, self-power neutron detector group, internal seal structure, connector, end part seal plug;
Described self-power neutron detector group is fixed in described package shell, and it comprises N self-power neutron detector, a described N self-power neutron detector along described package shell axially from bottom to top evenly interval arrange; The vertical range of the lower surface, sensitive section of centre distance reactor fuel assemblies active region of i rhodium self-power neutron detector is from bottom to top
wherein i=1,2,3 ..., N, H is the axial height of reactor fuel assemblies active region;
Described connector sealing is fixed on the upper end of described package shell; Described end part seal plug sealing is fixed on the lower end of described package shell;
Described internal seal structure sealing is fixed on the inside of the described package shell that is positioned at described self-power neutron detector group top;
The sheathed cable of described N rhodium self-power neutron detector is tied up and fixes, and axially upwards extends along described package shell, through described internal seal structure, is finally fixed on the stitch of described connector.
2. according to the sniffer for reactor core neutron flux and temperature claimed in claim 1, it is characterized in that: also comprise being fixed in described package shell being positioned at described internal seal structure upper area cold junction compensation device, described cold junction compensation device comprises 4 lead-in wires; Described 4 lead-in wires are connected respectively on 4 stitch of described connector.
3. according to the sniffer for reactor core neutron flux and temperature claimed in claim 2, it is characterized in that: described cold junction compensation device is Pt100 four-wire system thermometer.
4. according to the sniffer for reactor core neutron flux and temperature claimed in claim 2, it is characterized in that: also comprise and be fixed on the thermopair that is positioned at described internal seal structure lower zone in described package shell; Described thermopair is connected on the stitch of described connector by thermopair extended line.
5. according to the sniffer for reactor core neutron flux and temperature claimed in claim 1, it is characterized in that: described end part seal plug is bullet shaped structure, its outside surface is through polishing grinding processing.
6. according to the sniffer for reactor core neutron flux and temperature claimed in claim 1, it is characterized in that: described package shell comprises the first sleeve and the second sleeve; Described the first sleeve is axial equal diameter sleeve structure; Described the second sleeve comprises a major diameter sleeve structure, a minor diameter sleeve structure and is connected the conical surface tubular construction of described major diameter sleeve structure and described minor diameter sleeve structure; Described minor diameter sleeve structure end is tightly fixed in the upper end of described the first sleeve.
7. according to the sniffer for reactor core neutron flux and temperature claimed in claim 6, be positioned at: described second sleeve outer surface of described connector bottom is provided with first ring connected in star, be provided with the second annular groove at the second sleeve outer surface that is positioned at described first ring connected in star bottom.
8. according to the sniffer for reactor core neutron flux and temperature claimed in claim 6, be positioned at: the minor diameter tube-in-tube structure of described the second sleeve as with the sealing station of described containment vessel penetration piece.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210540619.2A CN103871526B (en) | 2012-12-14 | 2012-12-14 | A kind of detection device for reactor core neutron flux and temperature |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210540619.2A CN103871526B (en) | 2012-12-14 | 2012-12-14 | A kind of detection device for reactor core neutron flux and temperature |
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| CN103871526A true CN103871526A (en) | 2014-06-18 |
| CN103871526B CN103871526B (en) | 2016-12-21 |
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Cited By (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104217775A (en) * | 2014-08-14 | 2014-12-17 | 西京学院 | Method for measuring neutron flux density of nuclear reactor through thermal analysis technology |
| CN104882176A (en) * | 2015-04-09 | 2015-09-02 | 中国核动力研究设计院 | Delay eliminating method for signal of self-powered rhodium detector based on Luenberger-form H-infinity filtering |
| CN105513656A (en) * | 2015-11-30 | 2016-04-20 | 中广核工程有限公司 | System and method for monitoring reactor core parameters of nuclear power plant |
| CN106501614A (en) * | 2016-11-25 | 2017-03-15 | 中国核动力研究设计院 | Self-powered detector insulation resistance on-line monitoring method and monitoring device |
| CN106531245A (en) * | 2016-11-25 | 2017-03-22 | 浙江伦特机电有限公司 | Thimble assembly of in-core instrument for nuclear power station |
| CN107767974A (en) * | 2017-11-14 | 2018-03-06 | 国核自仪系统工程有限公司 | Nuclear reactor neutron and temperature detection device |
| CN111175808A (en) * | 2020-01-02 | 2020-05-19 | 中国原子能科学研究院 | Assembly and testing method based on assembly |
| CN111326269A (en) * | 2020-02-28 | 2020-06-23 | 中广核研究院有限公司 | Reactor core measuring sensor based on self-powered detector and thermocouple |
| CN111504485A (en) * | 2020-05-09 | 2020-08-07 | 安徽春辉仪表线缆集团有限公司 | Thermometer and method for producing a thermometer |
| CN112259265A (en) * | 2020-10-21 | 2021-01-22 | 中国核动力研究设计院 | Out-of-pile high-sensitivity neutron detector and layout system |
| CN112420230A (en) * | 2020-11-18 | 2021-02-26 | 中国核动力研究设计院 | In-reactor neutron detector assembly for passive start of nuclear power plant |
| CN112652412A (en) * | 2020-12-18 | 2021-04-13 | 中广核研究院有限公司 | Nuclear power station neutron and temperature monitoring device |
| CN112863714A (en) * | 2020-12-29 | 2021-05-28 | 中国原子能科学研究院 | Structure for measuring neutron flux density of light water reactor |
| CN113029388A (en) * | 2021-02-24 | 2021-06-25 | 中国核动力研究设计院 | Positioning device capable of improving positioning precision of reactor core detector assembly sensor |
| CN114420330A (en) * | 2022-01-28 | 2022-04-29 | 上海核工程研究设计院有限公司 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
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|---|---|---|---|---|
| CN104217775B (en) * | 2014-08-14 | 2016-06-08 | 西京学院 | The method measuring Nuclear Reactor Neutron Flux Density with thermal analysis system |
| CN104217775A (en) * | 2014-08-14 | 2014-12-17 | 西京学院 | Method for measuring neutron flux density of nuclear reactor through thermal analysis technology |
| CN104882176A (en) * | 2015-04-09 | 2015-09-02 | 中国核动力研究设计院 | Delay eliminating method for signal of self-powered rhodium detector based on Luenberger-form H-infinity filtering |
| CN105513656A (en) * | 2015-11-30 | 2016-04-20 | 中广核工程有限公司 | System and method for monitoring reactor core parameters of nuclear power plant |
| CN106501614A (en) * | 2016-11-25 | 2017-03-15 | 中国核动力研究设计院 | Self-powered detector insulation resistance on-line monitoring method and monitoring device |
| CN106531245A (en) * | 2016-11-25 | 2017-03-22 | 浙江伦特机电有限公司 | Thimble assembly of in-core instrument for nuclear power station |
| CN106531245B (en) * | 2016-11-25 | 2018-11-13 | 浙江伦特机电有限公司 | Used in nuclear power station in-pile instrument sheath assembly |
| CN107767974B (en) * | 2017-11-14 | 2024-04-16 | 国核自仪系统工程有限公司 | Nuclear reactor core neutron and temperature detection device |
| CN107767974A (en) * | 2017-11-14 | 2018-03-06 | 国核自仪系统工程有限公司 | Nuclear reactor neutron and temperature detection device |
| CN111175808A (en) * | 2020-01-02 | 2020-05-19 | 中国原子能科学研究院 | Assembly and testing method based on assembly |
| CN111326269A (en) * | 2020-02-28 | 2020-06-23 | 中广核研究院有限公司 | Reactor core measuring sensor based on self-powered detector and thermocouple |
| CN111504485A (en) * | 2020-05-09 | 2020-08-07 | 安徽春辉仪表线缆集团有限公司 | Thermometer and method for producing a thermometer |
| CN112259265B (en) * | 2020-10-21 | 2023-11-07 | 中国核动力研究设计院 | Off-stack high-sensitivity neutron detector and layout system |
| CN112259265A (en) * | 2020-10-21 | 2021-01-22 | 中国核动力研究设计院 | Out-of-pile high-sensitivity neutron detector and layout system |
| CN112420230A (en) * | 2020-11-18 | 2021-02-26 | 中国核动力研究设计院 | In-reactor neutron detector assembly for passive start of nuclear power plant |
| CN112652412A (en) * | 2020-12-18 | 2021-04-13 | 中广核研究院有限公司 | Nuclear power station neutron and temperature monitoring device |
| CN112652412B (en) * | 2020-12-18 | 2023-01-20 | 中广核研究院有限公司 | Nuclear power station neutron and temperature monitoring device |
| CN112863714A (en) * | 2020-12-29 | 2021-05-28 | 中国原子能科学研究院 | Structure for measuring neutron flux density of light water reactor |
| CN112863714B (en) * | 2020-12-29 | 2022-11-25 | 中国原子能科学研究院 | Structure for measuring neutron flux density of light water reactor |
| CN113029388A (en) * | 2021-02-24 | 2021-06-25 | 中国核动力研究设计院 | Positioning device capable of improving positioning precision of reactor core detector assembly sensor |
| CN113029388B (en) * | 2021-02-24 | 2022-03-25 | 中国核动力研究设计院 | Positioning device capable of improving positioning precision of reactor core detector assembly sensor |
| CN114420330A (en) * | 2022-01-28 | 2022-04-29 | 上海核工程研究设计院有限公司 | Full natural circulation integrated reactor inlet and outlet temperature measuring device |
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