CN106057259A - Reactor nuclear measurement system - Google Patents
Reactor nuclear measurement system Download PDFInfo
- Publication number
- CN106057259A CN106057259A CN201610256744.9A CN201610256744A CN106057259A CN 106057259 A CN106057259 A CN 106057259A CN 201610256744 A CN201610256744 A CN 201610256744A CN 106057259 A CN106057259 A CN 106057259A
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- module
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- reactor
- measurement system
- nuclear measurement
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Classifications
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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
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a reactor nuclear measurement system, comprising a detector, an amplification module, a sampling module and a processing module, wherein the detector is used for detecting the particle signal of a reactor at a preset voltage; the amplification module is used for amplifying the particle signal; the sampling module is used for sampling the particle signal at a sampling frequency and converting the particle signal into a digital signal, and the sampling frequency is more than or equal to 10 MHz; and the processing module is used for filtering shaping of the digital signal, extracting the electrical parameters of the digital signal having undergone filtering shaping, and calculating the power data of the reactor according to the electrical parameters. The reactor nuclear measurement system can calculate the power data of the reactor at the level of software in a fully digitized manner, substantially reduces usage of analog devices, overcomes the defects of low control precision, slow dynamic response, inconvenient parameter setting, severe temperature drift and proneness to aging of the analog devices, and has the advantages of high reliability and low failure rate.
Description
Technical field
The present invention relates to a kind of digitized reactor Nuclear measurement system based on high-speed sampling technology.
Background technology
Reactor Nuclear measurement system is one of requisite system of reactor, by monitoring neutron fluence rate
Quickly obtain reactor power level, thus provide reactor information to operator.But, reactor
From starting to Operation at full power, the dynamic range of its core power reaches 11 orders of magnitude, is specially
10-9The rated power of %-200%, is difficult to use a kind of detector in prior art and circuit covers so
Wide range.And 8 independent measurements that the nuclear measurement system of routine generally uses three kinds of different ranges are led to
Reactor capability is measured in road, i.e. 2 source range passages, 2 middle range passages and 4 power
Range passage, each of which is equipped with the detector that different properties is different with the scope of measurement.
In 8 independent Measurement channel of the outer nuclear measurement system of reactor, each passage all includes mutually
The neutron detector connected and the process circuit being made up of full analog circuit, i.e. this process circuit are full simulation
The hardware circuit changed, and the most simulated process circuit make the design of whole out-pile nuclear measurement system complicated,
Realize difficulty in process, and analog circuit itself exists, and control accuracy is low, dynamic response slow, parameter sets not
Convenient, temperature drift seriously, the shortcoming such as the most aging.Therefore, reaction core of the prior art surveys system
System urgently improves.
Summary of the invention
The technical problem to be solved in the present invention is to overcome reactor Nuclear measurement system in prior art to measure
The control accuracy that the process circuit that the power of reactor uses full analog circuit to constitute causes is low, dynamic response
Slowly, parameter set inconvenient, temperature drift seriously, the defect such as the most aging, it is provided that a kind of reaction core
Examining system.
The present invention solves above-mentioned technical problem by following technical proposals:
A kind of reactor Nuclear measurement system, its feature is, including detector, amplification module, sampling module
And processing module；
Described detector is for the particle signal of detection reaction heap under a predeterminated voltage；
Described amplification module is used for amplifying described particle signal；
Described sampling module is used for a sample frequency described particle signal of sampling, and by described particle signal
Being converted into digital signal, described sample frequency is more than or equal to 10MHz (megahertz)；
Described processing module for being filtered shaping to described digital signal, and after extracting filter shape
The electrical parameter of digital signal, calculates the power data of described reactor further according to described electrical parameter.
It is preferred that described electrical parameter includes the pulse information of described digital signal, described digital signal
Square voltage information and the output current information of described digital signal, described processing module is additionally operable to according to institute
State pulse information and calculate the described reactor power data at the first power range, according to described Square voltage
Information calculates the described reactor power data at the second power range, according to described output current information meter
Calculating the described reactor power data at the 3rd power range, described first power range is less than described second
Power range, described second power range is less than described 3rd power range.
It is preferred that described sampling module include a high-speed ADC (Analog to Digital Converter,
Analog-digital converter) chip, described processing module includes a FPGA (Field-Programmable Gate
Array, field programmable gate array) chip.
It is preferred that described predeterminated voltage is in the range of 500v-3000v (volt), and/or, described sampling frequency
Rate in the range of 10MHz-250MHz, and/or, the amplification coefficient of described amplification module is 103-104。
It is preferred that described reactor Nuclear measurement system also includes a switching value receiver module；
Described switching value receiver module is used for receiving a switch controlling signal, and by described switch controlling signal
Send to described processing module；
Described processing module is additionally operable to after receiving described switch controlling signal perform described reactor
The control of Nuclear measurement system.
It is preferred that described reactor Nuclear measurement system also includes a fault detection module；
Described fault detection module for detecting the signal value of each node on described fpga chip, and
Wherein the difference of the signal value of a node and the signal preset value of described node more than a first threshold time send out
Going out alarm signal, described signal value includes magnitude of voltage and current value.
It is preferred that described processing module is additionally operable to judge whether described power data exceedes described power data
Corresponding protection seting value, if so, sends Reactor trip signal.
It is preferred that described reactor Nuclear measurement system also includes an output module, described output module is used for will
Described power data exports after being converted to analog quantity, and/or, it is used for described power data by a bus
Transmission is to external equipment.
It is preferred that described reactor Nuclear measurement system also includes that one arranges module, the described module that arranges is for setting
Put the amplification coefficient of described amplification module, described sample frequency, the factor of influence of described power data and
Described first threshold.
It is preferred that described reactor Nuclear measurement system also includes that an inspection module, described inspection module are used for leading to
Cross a signal generator and send a standard test signal extremely described sampling module, and at described processing module
The result of the digitized described standard test signal of reason and the difference of described standard test signal are more than one
Alarm signal is sent during Second Threshold.
The most progressive effect of the present invention is: the present invention, by being amplified particle signal, utilizes height
Speed Sampling techniques and digital processing technology, operated by the sampling operation and analog digital conversion using module,
And the digitized processing operation of processing module, it is possible to count from software view by the way of total digitalization
Calculate the power data of reactor, greatly reduce the use of analog device, eliminate analog device and control essence
Spend defect low, that dynamic response slow, parameter sets inconvenience, temperature drift is serious and the most aging, tool
There is reliability high and the advantage of failure rate is low.
Accompanying drawing explanation
Fig. 1 is the structural representation of the reactor Nuclear measurement system of one embodiment of the invention.
Detailed description of the invention
Further illustrate the present invention below by the mode of embodiment, but the most therefore limit the present invention to
Among described scope of embodiments.
The present embodiment provides a kind of reactor Nuclear measurement system 100, as it is shown in figure 1, include detector 1,
Amplification module 2, sampling module 3 and processing module 4；
Described detector 1 is for the particle signal of detection reaction heap under a predeterminated voltage；Detector can be
Neutron detector, e.g., proportional coumter, fission chamber, boron chamber etc., it is provided that predeterminated voltage
Enable to detector be operated on rational plateau curve point, and the scope of predeterminated voltage can be
500v-3000v, the present embodiment can be realized detection by the high pressure of a high voltage unit described scope of generation
The power supply of device, and this particle signal can be the neutron signal in reactor.
Described amplification module 2 is used for amplifying described particle signal；The amplification coefficient of described amplification module is
103-104, the waveshape signal of the neutron detected by detector is amplified, it is simple to long range propagation, logical
Often, the multiple of amplification is that the voltage signal of microvolt level or the current signal of microampere order are enlarged into millivolt level
Voltage signal or the current signal of milliampere level.
Described sampling module 3 is used for a sample frequency described particle signal of sampling, and is believed by described particle
Number being converted into digital signal, described sample frequency is more than or equal to 10MHz；Preferably, described sampling frequency
Rate is in the range of 10MHz-250MHz, and described sampling module includes a high-speed ADC chip, with to putting
Big particle signal carries out high-speed sampling.
Described processing module 4 for being filtered shaping to described digital signal, and after extracting filter shape
The electrical parameter of digital signal, calculate the power data of described reactor further according to described electrical parameter.
Described processing module 4 includes a fpga chip, with on the basis of this fpga chip from software
Realizing in aspect being digitized the particle signal after analog digital conversion processing, described electrical parameter includes institute
State the defeated of the pulse information of digital signal, the Square voltage information of described digital signal and described digital signal
Going out current information, described processing module is additionally operable to calculate described reactor first according to described pulse information
The power data of power range, calculates described reactor in the second quantity of power according to described Square voltage information
The power data of journey, calculates the described reactor merit at the 3rd power range according to described output current information
Rate data, described first power range is less than described second power range, and described second power range is less than
Described 3rd power range.
It is corresponding that described processing module 4 is additionally operable to judge whether described power data exceedes described power data
Protection seting value, if so, sends Reactor trip signal.That is, the side that processing module is by logical operations
It is corresponding that formula judges whether the power data that three kinds of modes calculating power data are calculated exceedes under which
Protection seting value, the most then send Reactor trip signal.
The power data of reactor can include the performance number of reactor, the power variation rate of reactor and reaction
One or more in the axial distribution of the power of heap, and pulse information can include umber of pulse and/or pulse
Amplitude spectrum.Calculate the reactor power data at three power ranges, it is possible to be applicable to multiple variety classes
The power range ability of reactor that detected of detector, thus cover the core power of broader reactor
Range ability, to measure the dynamic range of the high order of magnitude of the core power of reactor more reliably.
Described reactor Nuclear measurement system also includes a switching value receiver module 5；
Described switching value receiver module 5 is for receiving a switch controlling signal, and is believed by described on-off control
Number send to described processing module；This switch controlling signal may be from the protection system of outside or controls system
System, and switching value receiver module can be made up of the digital transition components of one group of Phototube Coupling, whole to meet
Measure the requirement of system rejection to disturbance ability.Setting by switching value receiver module, it is possible to realize with outside
Mutual and the control of system.
Described processing module 4 is additionally operable to after receiving described switch controlling signal perform described reactor
The control of Nuclear measurement system, is turned on and off including to original predeterminated voltage environment, by this on-off control
Signal carries out logical combination, with to intrasystem output module, module, fault detection module be set, adopt
Being turned on and off of the functional modules such as original mold block, inspection module, or it is corresponding to make those functional modules perform
Logical operation etc., and such control mode is the most within the scope of the present invention.
Described reactor Nuclear measurement system also includes a fault detection module 6；
Described fault detection module 6 is used for detecting the signal value of each node on described fpga chip, and
When the difference of the signal preset value of the signal value of a node and described node is more than a first threshold wherein
Sending alarm signal, to protect this Nuclear measurement system, described signal value includes magnitude of voltage and current value.
Described reactor Nuclear measurement system also includes an output module 7, and described output module 7 is for by described
Power data exports after being converted to analog quantity, and the result of output can be shown on a display device；This output
The result of the switch controlling signal of the most exportable reception of module, output unit now then can be by multiple
Control relay circuit forms, and/or, described power data is passed by this output module also by a bus
Transport to external equipment, thus realize data transmission with external equipment.
Additionally, described reactor Nuclear measurement system also includes that one arranges module 8, described arrange module 8 for
Arrange the amplification coefficient of described amplification module, described sample frequency, described power data factor of influence with
And described first threshold.Described factor of influence be extract electrical parameter with calculate obtain power data it
Between affecting parameters, this affecting parameters can be certain value or variate.This is arranged module and can be controlled by software
Mode realize the setting to those parameters and amendment.
Described reactor Nuclear measurement system also includes an inspection module 9, and described inspection module 9 is for by one
Signal generator sends a standard test signal to described sampling module, and process in described processing module
The result of digitized described standard test signal and the difference of described standard test signal are more than one second
Alarm signal is sent during threshold value.
When test, the amplification coefficient of described amplification module, described sample frequency, described power are first set
The factor of influence of data, described first threshold and Second Threshold.Reacted by neutron detector collection afterwards
The neutron signal of heap, then this neutron signal is sent to high-speed ADC chip carries out sampling and analog digital conversion,
And be digitized processing by digital data transmission to the fpga chip after conversion, fpga chip logarithm
The neutron signal of word be filtered shaping, DISCHARGE PULSES EXTRACTION, Square voltage calculate, output Current calculation,
The steps such as logical operations, thus calculate the axial distribution of the power of reactor, power variation rate and power.
The hardware that the present embodiment relates to can be high-speed ADC chip and fpga chip, at those hardware
On the basis of realize software processes, owing to being digitized software processes, therefore on the basis of this hardware also
Can integrated plateau curve measure functional module.And arranging in structure, can be by sampling module and process mould
Block is located in integrated chassis, non-plug-in unit pattern of sampling, and connects polytype neutron detector, thus
Reduce standby redundancy number.
The system of the present embodiment is relative to the filtering molding electricity needed for the analog circuit used in prior art
For road, pole-zero cancellation circuit, threshold value arrange the hardware circuit such as circuit, coincident circuit, the hardware related to
Less, compact conformation, add system reliability；And use total digitalization technology, subtracting of maximum possible
Few analog device, eliminates that the control accuracy that original analog circuit exists is low, dynamic response slow, temperature
The defect such as drift about serious and the most aging, moreover it is possible to by the way of software, perform setting and the variable element of parameter
Regulation, and judge by multiple safety detection mode, such as fault detection module, power range, check mould
Block, it is achieved that the safety detection to system, have high reliability, high stability, quickly, electrical isolation,
The feature such as communication isolating, self diagnosis, has fully met the design requirement of nuclear safe level Digitization Software platform.
Although the foregoing describing the detailed description of the invention of the present invention, but those skilled in the art should managing
Solving, these are merely illustrative of, and protection scope of the present invention is defined by the appended claims.This
The technical staff in field, can be to these embodiment party on the premise of without departing substantially from the principle of the present invention and essence
Formula makes various changes or modifications, but these changes and amendment each fall within protection scope of the present invention.
Claims (10)
1. a reactor Nuclear measurement system, it is characterised in that include detector, amplification module, sampling
Module and processing module；
Described detector is for the particle signal of detection reaction heap under a predeterminated voltage；
Described amplification module is used for amplifying described particle signal；
Described sampling module is used for a sample frequency described particle signal of sampling, and by described particle signal
Being converted into digital signal, described sample frequency is more than or equal to 10MHz；
Described processing module for being filtered shaping to described digital signal, and after extracting filter shape
The electrical parameter of digital signal, calculates the power data of described reactor further according to described electrical parameter.
2. reactor Nuclear measurement system as claimed in claim 1, it is characterised in that described electrical parameter
Including the pulse information of described digital signal, the Square voltage information of described digital signal and described numeral letter
Number output current information, described processing module be additionally operable to according to described pulse information calculate described reactor
At the power data of the first power range, calculate described reactor second according to described Square voltage information
The power data of power range, calculates described reactor in the 3rd quantity of power according to described output current information
The power data of journey, described first power range is less than described second power range, described second quantity of power
Journey is less than described 3rd power range.
3. reactor Nuclear measurement system as claimed in claim 1, it is characterised in that described sampling module
Including a high-speed ADC chip, described processing module includes a fpga chip.
4. reactor Nuclear measurement system as claimed in claim 1, it is characterised in that described predeterminated voltage
In the range of 500v-3000v, and/or, described sample frequency in the range of 10MHz-250MHz, and/
Or, the amplification coefficient of described amplification module is 103-104。
5. reactor Nuclear measurement system as claimed in claim 1, it is characterised in that described reaction core
Examining system also includes a switching value receiver module；
Described switching value receiver module is used for receiving a switch controlling signal, and by described switch controlling signal
Send to described processing module；
Described processing module is additionally operable to after receiving described switch controlling signal perform described reactor
The control of Nuclear measurement system.
6. reactor Nuclear measurement system as claimed in claim 3, it is characterised in that described reaction core
Examining system also includes a fault detection module；
Described fault detection module for detecting the signal value of each node on described fpga chip, and
Wherein the difference of the signal value of a node and the signal preset value of described node more than a first threshold time send out
Going out alarm signal, described signal value includes magnitude of voltage and current value.
7. reactor Nuclear measurement system as claimed in claim 2, it is characterised in that described processing module
It is additionally operable to judge whether described power data exceedes the protection seting value that described power data is corresponding, if so,
Send Reactor trip signal.
8. reactor Nuclear measurement system as claimed in claim 1, it is characterised in that described reaction core
Examining system also includes an output module, and described output module is for being converted to analog quantity by described power data
Rear output, and/or, for by a bus by described power data transmission to external equipment.
9. reactor Nuclear measurement system as claimed in claim 6, it is characterised in that described reaction core
Examining system also includes that one arranges module, described arrange module for arrange described amplification module amplification coefficient,
Described sample frequency, the factor of influence of described power data and described first threshold.
10. the reactor Nuclear measurement system as described in any one in claim 1-9, it is characterised in that
Described reactor Nuclear measurement system also includes an inspection module, and described inspection module is for occurring by a signal
Device sends a standard test signal to described sampling module, and described processing module process digitized
Send out when the difference of the result of described standard test signal and described standard test signal is more than a Second Threshold
Go out alarm signal.
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| CN201610256744.9A CN106057259B (en) | 2016-04-22 | 2016-04-22 | Reactor Nuclear measurement system |
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| CN201610256744.9A CN106057259B (en) | 2016-04-22 | 2016-04-22 | Reactor Nuclear measurement system |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107146647A (en) * | 2017-04-20 | 2017-09-08 | 岭东核电有限公司 | A kind of portable neutron detection device |
| CN107967953A (en) * | 2017-11-13 | 2018-04-27 | 中国科学院上海应用物理研究所 | Molten salt reactor protects system |
| CN108198639A (en) * | 2017-12-13 | 2018-06-22 | 中国船舶重工集团公司第七〇九研究所 | A kind of rickle out-pile multiplexed probe device peculiar to vessel, nuclear measurement system and control system |
| CN109887625A (en) * | 2019-03-07 | 2019-06-14 | 中国核动力研究设计院 | Detector failure countermeasure and electric current restoration methods for reactor core on-line monitoring |
| CN112837834A (en) * | 2020-12-31 | 2021-05-25 | 江苏核电有限公司 | Off-line inspection device and method for in-situ measurement channel performance of off-core nuclear measurement system |
| CN113295924A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Neutron noise measurement method and device suitable for nuclear instrument system with frequency output |
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| CN205016255U (en) * | 2015-08-20 | 2016-02-03 | 绵阳市维博电子有限责任公司 | Measure redundant excellent position detecting system |
| CN105427927A (en) * | 2015-11-11 | 2016-03-23 | 中国船舶重工集团公司第七一九研究所 | Reactor outside nuclear measurement system double-ground separation method |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107146647A (en) * | 2017-04-20 | 2017-09-08 | 岭东核电有限公司 | A kind of portable neutron detection device |
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| CN107967953A (en) * | 2017-11-13 | 2018-04-27 | 中国科学院上海应用物理研究所 | Molten salt reactor protects system |
| CN108198639A (en) * | 2017-12-13 | 2018-06-22 | 中国船舶重工集团公司第七〇九研究所 | A kind of rickle out-pile multiplexed probe device peculiar to vessel, nuclear measurement system and control system |
| CN109887625A (en) * | 2019-03-07 | 2019-06-14 | 中国核动力研究设计院 | Detector failure countermeasure and electric current restoration methods for reactor core on-line monitoring |
| CN109887625B (en) * | 2019-03-07 | 2022-04-22 | 中国核动力研究设计院 | Detector failure coping method and current recovery method for reactor core online monitoring |
| CN112837834A (en) * | 2020-12-31 | 2021-05-25 | 江苏核电有限公司 | Off-line inspection device and method for in-situ measurement channel performance of off-core nuclear measurement system |
| CN113295924A (en) * | 2021-05-25 | 2021-08-24 | 中国核动力研究设计院 | Neutron noise measurement method and device suitable for nuclear instrument system with frequency output |
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| CN106057259B (en) | 2018-02-16 |
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