CN103871526B - A kind of detection device for reactor core neutron flux and temperature - Google Patents
A kind of detection device for reactor core neutron flux and temperature Download PDFInfo
- Publication number
- CN103871526B CN103871526B CN201210540619.2A CN201210540619A CN103871526B CN 103871526 B CN103871526 B CN 103871526B CN 201210540619 A CN201210540619 A CN 201210540619A CN 103871526 B CN103871526 B CN 103871526B
- Authority
- CN
- China
- Prior art keywords
- self
- sleeve
- package shell
- neutron detector
- reactor core
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
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 detection device for reactor core neutron flux and temperature, including package shell, self-power neutron detector group, internal seal structure, connector, end seal plug；Self-power neutron detector group is fixed in package shell, and it includes N number of self-power neutron detector, and N number of self-power neutron detector is arranged along package shell uniform intervals the most from bottom to top；Connector seals the upper end being fixed on package shell；End seal plug seals the lower end being fixed on package shell；Internal seal structure seals the inside being held within the package shell above self-power neutron detector group；The armored cable of N number of rhodium self-power neutron detector is tied up and fixes, and extends axially upward along package shell, through internal seal structure, is finally fixed on the stitch of connector.The present invention can quickly respond the change of reactor core neutron flux, in real time measurement reactor core neutron flux and fuel assembly outlet temperature；Reduce the design requirement to transmission cable.
Description
Technical field
The present invention relates to nuclear power station reactor core neutron flux and field of temperature measurement, be specifically related to one
Detection device for reactor core neutron flux and temperature.
Background technology
Generally reactor core neutron and temperature measuring instrument can be set at nuclear power station reactor core, be used for measuring heap
Core neutron flux and fuel assembly outlet temperature, measure the signal obtained and divide for monitoring reactor core three-dimensional power
The reactor operation situations such as cloth, Core cooling state.
The measuring instruments type that the nuclear power station of different heap-type is arranged is different.Existing metering system is, use from
Thermocouple is inserted at top, inserts the metering system of Miniature movable fission chamber from bottom, measures fuel assembly
Outlet temperature and reactor core neutron flux, as Qinshan Phase II NPP second phase and ridge Australia all use this kind the nuclear power second phase
Metering system and corresponding measuring instruments.Use this metering system and measuring instruments, need at pressure vessel
Bottom opening, arranges and substantial amounts of runs through pipe, will increase the risk of reactor coolant leakage.
Along with nuclear plant safety requirement is improved constantly and technological progress, reduce reactor coolant
The risk of leakage, needs to be placed on reactor core by the instrument of core temperature and neutron measurement, i.e. in-pile instrument
Entrance reactor core is run through, not in main pipeline pressure below container side wall and bottom opening from top.Enter
And need to adapt to the detection device of the new neutron flux of this constructive variations and temperature.
Summary of the invention
The present invention to solve the technical problem that being to provide one can enter reactor core from heap tip cutting and be fixed on heap
In-core, the quickly change of response reactor core neutron flux, in real time measurement reactor core neutron flux and fuel assembly go out
Mouthful temperature, and reduce heap and back down hole number, reduce the detector that transmission cable design requirement.
In order to solve above-mentioned technical problem, the technical scheme is that, a kind of in reactor core
The detection device of sub-flux and temperature, including package shell, self-power neutron detector group, inner sealing
Structure, connector, end seal plug；
Described self-power neutron detector group is fixed in described package shell, and it includes in N number of self-supporting energy
Sub-detector, described N number of self-power neutron detector along described package shell axially the most uniformly between
Every layout；Sensitive section of centre distance reactor combustion of i-th rhodium self-power neutron detector from bottom to top
The vertical dimension of material lower surface, module activity district isWherein i=1,2,3 ..., N, H are reactor
The axial height of fuel assembly active region；
Described connector seals the upper end being fixed on described package shell；Described end seal plug seals fixing
Lower end at described package shell；
Described internal seal structure seals be held within above described self-power neutron detector group described
The inside of package shell；
The armored cable of described N number of rhodium self-power neutron detector is tied up and fixes, and along described assembly
Shell extends axially upward, and through described internal seal structure, is finally fixed at the stitch of described connector
On.
Described internal seal structure upper area cold junction compensation it is positioned in also including being fixed on described package shell
Device, described cold junction compensation device includes 4 lead-in wires；Described 4 lead-in wires patch described in being connected respectively to
On 4 stitch of part.
Described cold junction compensation device is Pt100 four-wire system thermometer.
The thermoelectricity of described internal seal structure lower zone it is positioned in also including being fixed on described package shell
Even；Described thermocouple is connected on the stitch of described connector by thermocouple extension line.
Described end seal plug is bullet shaped structure, and its outer surface processes through polishing grinding.
Described package shell includes the first sleeve and the second sleeve；Described first sleeve is axial equal diameter set
Tubular construction；Described second sleeve include a major diameter sleeve structure, a minor diameter sleeve structure and
It is connected described major diameter sleeve structure and the conical surface tubular construction of described minor diameter sleeve structure；Described minor diameter
Sleeve structure end is tightly fixed in the upper end of described first sleeve.
Described second sleeve outer surface of described connector bottom is provided with first annular groove, described being positioned at
Second sleeve outer surface of first annular groove bottom is provided with the second annular groove.
The minor diameter tube-in-tube structure of described second sleeve is as the sealing with described containment vessel penetration piece
Position.
Beneficial effects of the present invention:
(1) a kind of detection device for reactor core neutron flux and temperature of the present invention can be from heap top
Insert reactor core and be fixed on the change of heap in-core, quickly response reactor core neutron flux, measure reactor core in real time
Neutron flux and fuel assembly outlet temperature；
(2) measure the neutron detector of neutron flux by being used for and be used for thermometric thermocouple and use
Device in cold junction compensation is integrated in a detector assembly, reduces heap and backs down hole number and reduce biography
The design requirement of transmission cable；
(3) signal that this detector assembly obtains is utilized, it is possible to achieve calculating reactor core three-dimensional power distribution,
Fuel assembly linear power density (LPD), departure from nucleate boiling ratio (DNBR), monitor Core cooling situation
Etc. function.
Accompanying drawing explanation
Fig. 1 is the signal of a kind of detection device for reactor core neutron flux and temperature of the present invention
Figure；
Fig. 2 is that a kind of outside for the detection device of reactor core neutron flux and temperature of the present invention shows
It is intended to；
Fig. 3 is being installed on of a kind of detection device for reactor core neutron flux and temperature of the present invention
Schematic diagram in containment.
In figure: 1-plug connector, 2-cold junction compensation device, 3-internal seal structure, 4-thermocouple, 401-heat
Galvanic couple extended line, 5-package shell, 501-the first sleeve, 502-the second sleeve, the first annular groove of 503-,
504-the second annular groove, 6-self-power neutron detector group, 7-end seal plug, 8-fuel assembly activity
District, 9-pressure vessel, 901-upper cover.
Detailed description of the invention
Below in conjunction with Fig. 1, Fig. 2 and embodiment, the present invention is described further.
Nuclear power plant reactor is provided with a kind of for measuring reactor core neutron flux and fuel assembly outlet temperature
Reactor core neutron and temperature detection device.
A kind of detection device for reactor core neutron flux and temperature of the present invention as shown in Figure 1, bag
Include package shell 5, self-power neutron detector group 6, thermocouple 4, internal seal structure 3, cold end benefit
Repay device 2, connector 1, end seal plug 7；
Described package shell 5 includes the first sleeve 501 and the second sleeve 502；Described first sleeve 501
For axial equal diameter sleeve structure；Described second sleeve 502 include a major diameter sleeve structure, one
Minor diameter sleeve structure and be connected described major diameter sleeve structure and the conical surface of described minor diameter sleeve structure
Tubular construction；Described minor diameter sleeve structure end is tightly enclosed within the upper end of described first sleeve 501, and passes through
It is welded and fixed；Described end seal plug 7 is bullet-shaped structure, and its end face weld is connected on described first sleeve
The lower end of 501, seals the first sleeve 501；The outer surface of end seal plug 7 is beaten through polishing
Mill processes, and to meet the requirement of surface roughness, reduces assembly and inserts the friction of instrument conduit.Described
One sleeve 501 and the second sleeve 502 use stainless steel material.
Described self-power neutron detector group 6 is fixed in described first sleeve 501, and it includes N number of rhodium
Self-power neutron detector (SPND), described N number of rhodium self-power neutron detector is along described first sleeve
The uniform intervals the most from bottom to top of 501 is arranged；Wherein, N is according to core height and the difference of measurement requirement
And determine, typically taking 3～7, Fig. 1 is as a example by N=7.
When the detection device for reactor core neutron flux and temperature of the present invention is installed on reactor
Time, sensitive section of axial centre distance reactor of its i-th rhodium self-power neutron detector from bottom to top
The vertical dimension of lower surface, fuel assembly active region 8 isWherein i=1,2,3 ..., N；H is anti-
Answer the axial height of heap fuel assembly active region 8；
It is big straight that described internal seal structure 3 is fixed on above the tapered tube configuration of described second sleeve 502
In the sleeve pipe of footpath, and carry out encapsulation process with the tube wall of described second sleeve 502；Described thermocouple 4 is fixed
It is positioned at the region below described internal seal structure 3 in described first sleeve 501；Described cold junction compensation
Device 2 is positioned at the region above described internal seal structure 3 in being fixed on described second sleeve 502；Institute
Stating cold junction compensation device 2 and use Pt100 four-wire system thermometer, it is for the cold junction temperature of Compensative thermoelectric couple.
Described connector 1 includes multiple stitch, and this connector 1 is welded on the upper of described second sleeve 502
End.4 lead-in wires of the described Pt100 four-wire system thermometer pin by connection to described connector 1
On foot.
Thermocouple 4 is connected with one end of thermocouple extension line 401, described thermocouple extension line 401 another
One end is connected through described internal seal structure 3 with 1 stitch of described connector 1；
The armored cable of described N number of rhodium self-power neutron detector is tied up and fixes, and along described first
Sleeve 501 and the second sleeve 502 extend axially upward, and through described internal seal structure 3, finally weld
It is connected on the stitch of connector 1.
The outside for the detection device of reactor core neutron flux and temperature of the present invention can be such as Fig. 2
Shown in；It is provided with first annular recessed at described second sleeve 502 outer surface being positioned at described connector 1 bottom
Groove 503, is provided with second at the second sleeve 502 outer surface being positioned at described first annular groove 503 bottom
Annular groove 504；Described first annular groove 503 is used for and reactor roof support means；Described
Second ring groove 504 is for coordinating with reactor lifting device；
As it is shown on figure 3, the present invention is for the end of the detection device of reactor core neutron flux and temperature
Sealing-plug 7 one end penetrate containment vessel upper cover 901 and enter in fuel assembly gauge pipe in,
Make each rhodium self-powered detector be in appropriate position, thus reactor core is monitored；Described second
The minor diameter tube-in-tube structure outer surface of sleeve 502 is carried out as with described containment vessel upper cover 901
The sealing station that cutting ferrule seals, with realizing the detection device of the present invention and the close of containment upper cover 901
Envelope.
Claims (2)
1. one kind is used for reactor core neutron flux and the detection device of temperature, it is characterised in that: include outside assembly
Shell, self-power neutron detector group, internal seal structure, connector and end seal plug；
Described self-power neutron detector group is fixed in described package shell, and it includes N number of self-supporting moderate energy neutron detection
Device, described N number of self-power neutron detector is arranged along described package shell uniform intervals the most from bottom to top；
Sensitive section of centre distance reactor fuel assemblies active region of i-th self-power neutron detector from bottom to top
The vertical dimension of lower surface is
Wherein i=1,2,3 ..., N, H are the axial height of reactor fuel assemblies active region；
Described connector seals the upper end being fixed on described package shell；Described end seal plug seals solid
It is scheduled on the lower end of described package shell；
Described internal seal structure seals the institute being held within above described self-power neutron detector group
State the inside of package shell；
The armored cable of described N number of self-power neutron detector is tied up and fixes, and along described assembly
Shell extends axially upward, and through described internal seal structure, is finally fixed at the pin of described connector
On foot,
Described package shell includes the first sleeve and the second sleeve；Described first sleeve is axial equal diameter
Sleeve structure；Described second sleeve includes a major diameter sleeve structure, a minor diameter sleeve structure
And it is connected described major diameter sleeve structure and the conical surface tubular construction of described minor diameter sleeve structure；Described
Minor diameter sleeve structure end is tightly fixed in the upper end of described first sleeve.
2. according to the detection device for reactor core neutron flux and temperature described in claim 1,
It is being positioned at: described second sleeve outer surface of described connector bottom is provided with first annular groove, in place
The second sleeve outer surface in described first annular groove bottom is provided with the second annular groove.
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 |
Applications Claiming Priority (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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103871526A CN103871526A (en) | 2014-06-18 |
| CN103871526B true CN103871526B (en) | 2016-12-21 |
Family
ID=50909965
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201210540619.2A Active CN103871526B (en) | 2012-12-14 | 2012-12-14 | A kind of detection device for reactor core neutron flux and temperature |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN103871526B (en) |
Families Citing this family (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104217775B (en) * | 2014-08-14 | 2016-06-08 | 西京学院 | The method measuring Nuclear Reactor Neutron Flux Density with thermal analysis system |
| 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 |
| 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 |
| 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 |
| 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 |
| CN111175808B (en) * | 2020-01-02 | 2022-06-28 | 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 |
| 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 |
| 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 |
| 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 |
| 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 |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1470201A (en) * | 1973-08-24 | 1977-04-14 | Combustion Eng | Multi-sensor radiation detector system |
| GB1495175A (en) * | 1975-07-23 | 1977-12-14 | Rozenbljum N | Device for measuring neutron-flux distribution density |
| EP0496998A1 (en) * | 1991-01-30 | 1992-08-05 | Combustion Engineering, Inc. | Extending in-core instrument life |
| CN1230282A (en) * | 1996-09-12 | 1999-09-29 | 法国原子能委员会 | Quick response, self-power-supplied miniaturised device for sensing multistage neutron flux, in particular in nuclear reactor |
| CN1244715A (en) * | 1998-03-17 | 2000-02-16 | 东芝株式会社 | Nuclear measuring instrument system of reactor, reactor output distribution monitoring system and monitoring method |
| CN1292554A (en) * | 1999-07-05 | 2001-04-25 | 法玛通公司 | Method for monitoring at least one running parameter of pile core of nuclear pile and its system |
| CN101421798A (en) * | 2006-04-13 | 2009-04-29 | 阿海珐核能公司 | Internal instrumentation system for a nuclear reactor, having a variable electronic card and corresponding method of modifying an internal instrumentation system for a nuclear reactor |
| CN203026177U (en) * | 2012-12-14 | 2013-06-26 | 中国核动力研究设计院 | Neutron flux and temperature detecting device applied to reactor core |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8445839B2 (en) * | 2010-10-14 | 2013-05-21 | Areva Np Inc. | Self-calibrating, highly accurate, long-lived, dual rhodium vanadium emitter nuclear in-core detector |
| US8767903B2 (en) * | 2011-01-07 | 2014-07-01 | Westinghouse Electric Company Llc | Wireless in-core neutron monitor |
-
2012
- 2012-12-14 CN CN201210540619.2A patent/CN103871526B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1470201A (en) * | 1973-08-24 | 1977-04-14 | Combustion Eng | Multi-sensor radiation detector system |
| GB1495175A (en) * | 1975-07-23 | 1977-12-14 | Rozenbljum N | Device for measuring neutron-flux distribution density |
| EP0496998A1 (en) * | 1991-01-30 | 1992-08-05 | Combustion Engineering, Inc. | Extending in-core instrument life |
| CN1230282A (en) * | 1996-09-12 | 1999-09-29 | 法国原子能委员会 | Quick response, self-power-supplied miniaturised device for sensing multistage neutron flux, in particular in nuclear reactor |
| CN1244715A (en) * | 1998-03-17 | 2000-02-16 | 东芝株式会社 | Nuclear measuring instrument system of reactor, reactor output distribution monitoring system and monitoring method |
| CN1292554A (en) * | 1999-07-05 | 2001-04-25 | 法玛通公司 | Method for monitoring at least one running parameter of pile core of nuclear pile and its system |
| CN101421798A (en) * | 2006-04-13 | 2009-04-29 | 阿海珐核能公司 | Internal instrumentation system for a nuclear reactor, having a variable electronic card and corresponding method of modifying an internal instrumentation system for a nuclear reactor |
| CN203026177U (en) * | 2012-12-14 | 2013-06-26 | 中国核动力研究设计院 | Neutron flux and temperature detecting device applied to reactor core |
Non-Patent Citations (3)
| Title |
|---|
| 李文平 等.秦山核电二期工程堆芯测量系统设计.《核动力工程》.2003,第24卷(第2期), * |
| 李树成 等.铑自给能探测器电流信号计算方法及影响因素.《核电子学与探测技术》.2011,第31卷(第5期), * |
| 陈道龙 等.高通量工程试验堆堆芯燃料元件温度和流量测量.《中国核科技报告》.1988, * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN103871526A (en) | 2014-06-18 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103871526B (en) | A kind of detection device for reactor core neutron flux and temperature | |
| CN203026177U (en) | Neutron flux and temperature detecting device applied to reactor core | |
| JP5729788B2 (en) | Radio reactor neutron monitor | |
| CN107767974B (en) | Nuclear reactor core neutron and temperature detection device | |
| US10438708B2 (en) | In-core instrument thimble assembly | |
| US9395227B2 (en) | Reactor water-level measurement system | |
| JP6034232B2 (en) | System and apparatus for monitoring cores, reactors | |
| JP5758012B2 (en) | Self-powered radio in-core detector | |
| CN106531245B (en) | Used in nuclear power station in-pile instrument sheath assembly | |
| US4406011A (en) | Gamma thermometer based reactor core liquid level detector | |
| CN105513656A (en) | System and method for monitoring reactor core parameters of nuclear power plant | |
| JPS5853759B2 (en) | Local power measurement device within the reactor fuel assembly | |
| CN103106935A (en) | Apparatus and method for detecting position of annulus spacer between concentric tubes | |
| CN207503654U (en) | Nuclear reactor neutron and temperature detection device | |
| CN105513657A (en) | Nuclear power plant integrated in-core instrumentation assembly | |
| JP2013140150A (en) | Methods and apparatuses for monitoring nuclear reactor core conditions | |
| JP2014530364A (en) | Pool water level indication system | |
| CN206194382U (en) | Reactor core appearance gauge sleeve pipe assembly for nuclear power station | |
| CN1012657B (en) | Pipe for supporting and positioning measuring device in core of nuclear reactor | |
| CN111326269A (en) | Reactor core measuring sensor based on self-powered detector and thermocouple | |
| JPH06265686A (en) | Power measuring device for reactor and its producing method | |
| Abou-Sena et al. | Development of the IFMIF tritium release test module in the EVEDA phase | |
| KR101358927B1 (en) | Irradiation capsule for an improved temperature control by using a liquid and solid thermal media | |
| US11289221B2 (en) | Detection apparatus, system, and method for detection of coolant flow rate and temperature in a nuclear environment | |
| CN210271807U (en) | Coolant hot section temperature measuring device and pressure vessel with same |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |