CN218513185U - Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel - Google Patents

Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel Download PDF

Info

Publication number
CN218513185U
CN218513185U CN202123447642.0U CN202123447642U CN218513185U CN 218513185 U CN218513185 U CN 218513185U CN 202123447642 U CN202123447642 U CN 202123447642U CN 218513185 U CN218513185 U CN 218513185U
Authority
CN
China
Prior art keywords
reactor core
neutron flux
self
pressure vessel
detector
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
Application number
CN202123447642.0U
Other languages
Chinese (zh)
Inventor
张琪
洪源平
王兴
高鸣
郎德嵩
黄尧
苏鑫
汪娜
苏本新
潘泽飞
谢金平
薛长江
王勇
杨杰
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Jiangsu Nuclear Power Corp
Original Assignee
Jiangsu Nuclear Power Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Jiangsu Nuclear Power Corp filed Critical Jiangsu Nuclear Power Corp
Priority to CN202123447642.0U priority Critical patent/CN218513185U/en
Application granted granted Critical
Publication of CN218513185U publication Critical patent/CN218513185U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The utility model belongs to the technical field of the reactor, concretely relates to reactor core neutron flux continuous measurement system that is used for pressure vessel bottom to get into. The utility model discloses a 50 dactylotheca pipes, 50 dactylotheca pipes are installed to the reactor core stand pipe in to it is sealed with the stand pipe fastening. The system also comprises 50 self-powered neutron detector complexes, and the 50 self-powered neutron detector complexes are introduced. Each self-powered neutron detector complex is provided with a plurality of self-powered detectors and a plurality of temperature-measuring thermocouple detectors. After the 50 self-powered neutron detector complexes are installed to the specified coordinates and height positions of the reactor core, the reactor core will be combined with the inlet of the finger sleeve and sealed and fastened. The system also comprises a signal acquisition processing cabinet matched with the self-powered detector. The utility model discloses can realize the continuous measurement of reactor core neutron flux.

Description

Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel
Technical Field
The utility model belongs to the technical field of the reactor, concretely relates to a reactor core neutron flux continuous measurement system that is used for pressure vessel bottom to get into.
Background
The reactor core neutron measurement system is used for periodically measuring the neutron flux levels of different regions of the reactor core, drawing a reactor core neutron flux distribution diagram and providing power range calibration coefficients for the LOCA monitoring system and the out-of-reactor nuclear instrument system. The system is an off-line measuring system, a neutron detector for measuring neutron flux is a movable fission type which is only used for measuring neutron flux, the detector and a driving chain are integrated into a whole, the driving chain is wound on a wheel disc of a driving motor and is connected with the driving motor, and the feeding into a reactor core and the pumping back of the detector are realized through the driving and the pumping back of the driving motor.
The reactor core neutron flux detector is an extractable component, and due to the limitation of structural materials of the reactor core neutron flux detector, the reactor core neutron flux detector is rapidly lost in a high-neutron-flux horizontal environment of the reactor core for a long time, and the sensitivity and the measurement precision of the detector can be influenced. During the operation of the unit, a worker regularly performs the neutron flux measurement of the reactor core, enters the neutron flux detector of the reactor core into the designated area of the reactor core and the height of the reactor core as required to perform the measurement in the neutron flux measurement process, and is immediately sent to a special storage channel between the reactor core instruments for offline storage after the measurement is finished.
The discontinuous reactor core neutron measurement system has the advantages that the technology is backward, the reactor core neutron flux parameters cannot be displayed in real time, the system structure is complex, the failure rate is high, and the operation and the maintenance are inconvenient.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a reactor core neutron flux continuous measurement system that is used for pressure vessel bottom to get into is provided to the research of factory building space between reactor core neutron flux measurement system inner structure and reactor core instrument, realizes the continuous measurement of reactor core neutron flux.
The utility model adopts the technical proposal that:
a reactor core neutron flux continuous measurement system for pressure vessel bottom entry comprises 50 thimble tubes, wherein the 50 thimble tubes are installed in a reactor core guide tube and are tightly and tightly sealed with the guide tube.
The system also comprises 50 self-powered neutron detector complexes, and the 50 self-powered neutron detector complexes are introduced.
Each self-powered neutron detector complex is provided with a plurality of self-powered detectors and a plurality of temperature-measuring thermocouple detectors.
After the 50 self-powered neutron detector complexes are installed to the specified coordinates and height positions of the reactor core, the reactor core will be combined with the inlet of the finger sleeve and sealed and fastened.
The system also comprises a signal acquisition processing cabinet matched with the self-powered detector.
And is connected with the detector through a matched cable.
The reactor core neutron flux monitoring system further comprises an upper computer server of the reactor core neutron measuring system, and the upper computer server is used for further processing and displaying the reactor core neutron flux signals in real time.
A lifting boric acid solution water tank is arranged between reactor core instruments, and the thimble tube and the detector are drawn out to a maintenance position during overhaul of the unit.
Compared with the prior art, the beneficial effects of the utility model reside in that:
(1) The utility model provides a reactor core neutron flux continuous measurement system for pressure vessel bottom entering, which is suitable for the structural characteristics of the pressure vessel, the reactor core detector is arranged from the guide pipe pipeline at the bottom of the pressure vessel without changing the bottom structure and the pressure-bearing boundary range of the pressure vessel;
(2) The utility model provides a reactor core neutron flux continuous measurement system for pressure vessel bottom entering, which uses a self-powered neutron detector complex made of low-loss structural materials to realize the purpose of reactor core neutron flux continuous monitoring;
(3) The utility model provides a reactor core neutron flux continuous measurement system for pressure vessel bottom entering, which greatly simplifies the structure and equipment of the existing measurement system, adopts a new reactor core neutron flux measurement system, and no longer needs equipment such as a driving motor and a road bank selector;
(4) The utility model provides a reactor core neutron flux continuous measurement system for pressure vessel bottom entry, according to the needs, can introduce reactor core fuel assembly export entry temperature monitoring thermocouple detector simultaneously;
the installation, operation and maintenance are convenient, the cable connection is completed when the detector is installed, and the continuous monitoring function of the neutron flux in the reactor core can be realized after the unit is started;
(5) The utility model provides a reactor core neutron flux continuous measurement system for pressure vessel bottom entering, the selected neutron detector complex can continuously operate for a plurality of life periods, and the maintenance cost is reduced;
(6) The utility model provides a pair of a reactor core neutron flux continuous measurement system for pressure vessel bottom entering, according to the demand of unit, reactor core neutron flux parameter can realize participating in reactor shutdown protect function.
(7) The utility model provides a pair of a reactor core neutron flux continuous measurement system for pressure vessel bottom entering is applicable to all reactor units of predetermineeing the reactor core from the pressure vessel bottom and measures the pore, installs the thimble pipe that bears a loop pressure in the reactor core measurement pore, and the high position of predetermineeing is installed through the thimble pipe to the self-energy neutron detector complex. A self-powered neutron detector complex made of low-loss structural materials is installed in a reactor core after machine assembly materials are adopted, and the function of continuously monitoring the neutron flux in the reactor core after the unit operates is achieved. Meanwhile, the detector complex can integrate a thermocouple detector as required for monitoring the temperature of the inlet and outlet positions of the reactor core fuel assembly. The reactor core neutron flux measurement mode of the reactor type is thoroughly changed, and the maintenance difficulty is reduced. Meanwhile, the reactor core neutron flux parameter can participate in the reactor shutdown protection function according to the requirement.
Drawings
FIG. 1: a reactor core instrument room equipment installation layout diagram;
FIG. 2: and the corresponding relation diagram of the detector pore passage and the core coordinate position.
Detailed Description
The present invention provides a system for continuously measuring neutron flux in a reactor core entering from the bottom of a pressure vessel, which is described in detail with reference to the accompanying drawings and specific embodiments.
Through the analysis such as to reactor pressure vessel reactor core structure and size research, the workshop space size between the reactor core instrument, current measurement mode, from dactylotheca pipe to the entry wall body between the instrument, have the length to exceed 7 meters space, can be used to 50 and arrange the installation and the change maintenance work of self-powered neutron detector, it is feasible to discover that the reactor core neutron flux measurement system that is used for reactor core neutron flux continuous monitoring is installed in current dactylotheca pipe.
As shown in FIG. 1, the utility model provides a reactor core neutron flux continuous measurement system for bottom entry of a pressure vessel,
in the existing reactor core instrument room, 50 finger sleeves are installed in a reactor core guide pipe and are tightly and tightly sealed with the guide pipe, so that the integrity of a primary circuit pressure boundary is ensured;
introducing 50 self-powered neutron detector complexes (each self-powered neutron detector complex can be provided with a plurality of self-powered detectors and a plurality of thermocouple detectors for temperature measurement according to requirements);
after 50 self-powered neutron detector complexes are installed at the specified coordinates and height positions of the reactor core, the self-powered neutron detector complexes are combined with the inlet of the finger sleeve and are tightly sealed, the unit stays at the corresponding position of the reactor core all the time during the operation, the self-powered neutron detector can bear the operation pressure of a loop, but during the normal operation, the finger sleeve is a pressure-bearing boundary, and the shell of the self-powered neutron detector complex is no longer used as the pressure-bearing boundary of the loop;
configuring a signal acquisition processing cabinet matched with a self-powered detector (a plurality of operation sequences can be set according to requirements);
the matched cable is used for connecting with the detector, and after the cable connection is finished, the measurement signal is transmitted to the matched signal acquisition processing cabinet for signal acquisition and processing;
configuring an upper computer server of the reactor core neutron measurement system for further processing and real-time displaying of the reactor core neutron flux signals;
a lifting boric acid solution water tank is arranged between reactor core instruments, and after the thimble tube and the detector are drawn out to a maintenance position during overhaul of the unit, the thimble tube and the detector are immersed into the boric acid solution water tank so as to reduce the radiation dose level of a site.
According to fig. 1, 50 connection pipes, a movable bracket, a path selector, a main selector and a driving motor between the inter-core-instrument seal assembly and the electric valve are removed, and all the connection pipes are removed;
the finger sleeve and the joint sealing assembly thereof are kept, and the original pressure boundary is kept sealed, namely the original pressure boundary is still complete;
according to the requirements, a lifting plane can be introduced into the position of an original movable support, a rectangular boric acid solution storage tank is introduced above the lifting plane, 50 neutron detector integrated bodies can be immersed into the boric acid solution storage tank at the same time, and the boric acid solution storage tank can be lowered to a height position which does not influence the installation of the detector and the connection of cables according to the requirements;
according to the number corresponding relation of FIG. 2, sequentially installing 50 self-powered neutron detector complexes to the specified position and height of the reactor core;
connecting the pre-laid signal cable with a corresponding detector, and introducing a measurement signal into a signal acquisition and processing cabinet;
the signal acquisition and processing cabinet is connected with the upper computer server cabinet in a network communication mode, so that the reactor core signals are displayed on the upper computer server cabinet in real time.
2. Test verification
After the unit is charged, the self-powered neutron detector complex measures a pore passage from the bottom of the pressure container, is installed at a preset height position, and is reliably sealed with the finger sleeve joint, the detector can bear the operating pressure of a loop, and even if the finger sleeve is damaged during operation, the detector is sealed with the finger sleeve, so that the condition that a loop medium cannot leak out can be ensured. Meanwhile, the detector complex can integrate a thermocouple detector for monitoring the temperature of the inlet and outlet positions of the reactor core fuel assembly. The reactor core neutron flux measuring mode of the reactor type is thoroughly changed, and the function of continuously monitoring the reactor core neutron flux is realized. Meanwhile, according to the requirements of the unit, the reactor core neutron flux parameter can participate in the reactor shutdown protection function, and the expected design requirements are met.
3. Evaluation of Effect
The design introduces a novel reactor core neutron flux continuous measurement system, a self-powered neutron detector complex made of low-loss structural materials is adopted, the reactor core is loaded after machine assembly materials are assembled, the neutron detector complex can continuously run for a plurality of service lives, and meanwhile, the detector complex can integrate a thermocouple detector and is used for monitoring the temperature of the inlet and outlet positions of a fuel assembly of the reactor core. The design of the system is introduced, the reactor core neutron flux measurement mode of the reactor type is thoroughly changed, and the reactor core neutron flux continuous monitoring function is realized. Meanwhile, according to the requirements of the unit, the reactor core neutron flux parameter participating reactor shutdown protection function can be realized. The design scheme is suitable for all reactor units with reactor core measuring pore channels preset from the bottom of the pressure vessel, and has great reference significance.
The above description is only the preferred embodiment of the present invention, but the protection scope of the present invention is not limited thereto, and any person skilled in the art can substitute or change the technical solution of the present invention and the inventive concept thereof equally within the technical scope disclosed in the present invention, and all the modifications should be covered within the protection scope of the present invention.

Claims (8)

1. A system for continuous measurement of neutron flux in a reactor core entering at the bottom of a pressure vessel, characterized by: the reactor core guide tube comprises 50 thimble tubes, wherein the 50 thimble tubes are arranged in a reactor core guide tube and are tightly and hermetically fixed with the guide tube.
2. The system of claim 1 for continuous measurement of in-core neutron flux entering at the bottom of a pressure vessel, wherein: the system also comprises 50 self-powered neutron detector complexes, and the 50 self-powered neutron detector complexes are introduced.
3. The system of claim 2 for continuous measurement of in-core neutron flux entering at the bottom of a pressure vessel, wherein: each self-powered neutron detector complex is provided with a plurality of self-powered detectors and a plurality of temperature-measuring thermocouple detectors.
4. The system of claim 3, wherein the system is configured to continuously measure the neutron flux in the core entering the bottom of the pressure vessel: after the 50 self-powered neutron detector complexes are installed to the specified coordinates and height positions of the reactor core, the reactor core will be combined with the inlet of the finger sleeve and tightly sealed and fastened.
5. The system of claim 4, wherein the reactor core neutron flux continuous measurement system for pressure vessel bottom entry comprises: the system also comprises a signal acquisition processing cabinet matched with the self-powered detector.
6. The system of claim 5 for continuous measurement of in-core neutron flux entering at the bottom of a pressure vessel, wherein: and is connected with the detector through a matched cable.
7. The system of claim 6, wherein the reactor core neutron flux continuous measurement system for pressure vessel bottom entry comprises: the reactor core neutron flux monitoring system further comprises an upper computer server of the reactor core neutron measuring system, and the upper computer server is used for further processing and displaying the reactor core neutron flux signals in real time.
8. The system of claim 7 for continuous measurement of in-core neutron flux entering at the bottom of a pressure vessel, wherein: a lifting boric acid solution water tank is arranged between reactor core instruments, and the thimble tube and the detector are drawn out to a maintenance position during overhaul of the unit.
CN202123447642.0U 2021-12-31 2021-12-31 Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel Active CN218513185U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202123447642.0U CN218513185U (en) 2021-12-31 2021-12-31 Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202123447642.0U CN218513185U (en) 2021-12-31 2021-12-31 Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel

Publications (1)

Publication Number Publication Date
CN218513185U true CN218513185U (en) 2023-02-21

Family

ID=85205364

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202123447642.0U Active CN218513185U (en) 2021-12-31 2021-12-31 Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel

Country Status (1)

Country Link
CN (1) CN218513185U (en)

Similar Documents

Publication Publication Date Title
CA2822808C (en) Wireless in-core neutron monitor
CA2822749C (en) Self-powered wireless in-core detector
CN211350119U (en) Large pressurized water reactor containment overall tightness test measuring system
CN105513656A (en) System and method for monitoring reactor core parameters of nuclear power plant
CN102930907A (en) Nuclear power plant digital radiation monitoring system
CN102081979B (en) Data acquisition and processing system of reactor core neutron fluence rate
CN101727996A (en) Method for detecting deformation of fuel assembly after irradiation of pressurized-water reactor nuclear power plant and implementation device thereof
CN103871526A (en) Detection apparatus for neutron flux and temperature of reactor core
CN104798138A (en) Method of validating nuclear reactor in-vessel detector output signals
KR20180037021A (en) Control rod position indicator
JPH0365696A (en) In-fixed type reactor calibrating apparatus for thermal neutron detector of boiling water reactor
CN201803838U (en) Multifunctional valve testing system
CN218513185U (en) Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel
CN114242281A (en) Reactor core neutron flux continuous measurement system for bottom entering of pressure vessel
CN103033322B (en) Nuclear power station main pump cooling water system runs through part segregaion valve sealing test method
CN109273120B (en) Compact type small nuclear reactor cold section temperature measuring method
CN107705864B (en) Liquid level monitoring system, method and device for containment recycling pit of nuclear power plant
CN213780720U (en) Monitoring system suitable for loop transformation is tested in research heap
CN104538069A (en) Nuclear power station reactor coolant system half tube operation liquid level test system
CN209342156U (en) A kind of monitoring system for radioactive environment
US5333158A (en) Device and method for the measurement of the neutron flux in the core of a nuclear reactor
CN220065196U (en) Out-of-core nuclear measuring instrument for nuclear reactor
CN205879307U (en) A calibration equipment for pit capacitance level gauge in containment
CN216717530U (en) Liquid level measuring device
CN219038080U (en) System for testing flow of branch of each water pipe of SVG water-cooled radiator

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant