CN113241204A - Special system for testing reactor reactivity instrument - Google Patents
Special system for testing reactor reactivity instrument Download PDFInfo
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- CN113241204A CN113241204A CN202110543842.1A CN202110543842A CN113241204A CN 113241204 A CN113241204 A CN 113241204A CN 202110543842 A CN202110543842 A CN 202110543842A CN 113241204 A CN113241204 A CN 113241204A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
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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 discloses a special system for testing a reactor reactivity instrument, which comprises a computer with an operation display screen, wherein the computer is used for changing the movement of a control rod or the setting of boron concentration, calculating the neutron fluence rate level of a point reactor in real time to simulate the reactor extrapolation critical process, the routine starting physical test process, boron adjustment, rod falling process, dynamic rod carving process and the like, a data stream representing the neutron fluence rate level generated in the calculation process is sent to the computer in a communication cable mode to generate simulated neutron pulse and current signals, so that all-around tests can be carried out on various reactivity instruments, and the special system can be used for assisting the research and development of novel reactivity instruments, detecting the performance state of the reactivity instruments and carrying out fault diagnosis.
Description
Technical Field
The invention relates to a nuclear reactor reactivity measuring device, in particular to a special system for testing a reactor reactivity meter.
Background
Reactivity meter, refers to an electronic instrument connected to one or more detectors for measuring reactor reactivity and control rod calibration, etc. During research, development, demonstration and inspection of the reactor reactivity instrument under laboratory conditions, an exponential pulse source or a current source is generally adopted to generate a simulation signal, the signal can only simulate gradual periodic working conditions of the reactor, more dynamic working conditions of the reactor cannot be simulated, key dynamic response characteristics and other parameters of the reactivity instrument cannot be inspected, and the comprehensive test of the reactivity instrument cannot be realized in a laboratory.
Disclosure of Invention
The invention aims to solve the problems and provides a special system for testing a reactor reactivity meter, which can simulate all dynamic and steady-state working conditions of a real reactor and realize comprehensive test of the reactivity meter in a laboratory.
Therefore, the technical scheme of the invention is as follows: a special system for testing a reactor reactivity instrument comprises a computer with an operation display screen, wherein the computer is connected with a current signal source module, a pulse signal source module and a voltage signal source module, and the output ends of the current signal source module, the pulse signal source module and the voltage signal source module are respectively connected with a neutron current signal input interface, a pulse signal input interface and a voltage signal input interface of the reactivity instrument to be tested;
the test procedure was as follows:
1) setting reactor core parameter values on an operational display screen: lifetime of prompt neutron and decay constant of precursor nucleus of slow neutroniI group delayed neutron fraction betaiAnd neutron source intensity q;
2) adjusting the rod position or boron concentration of the control rod, and obtaining the reactivity value caused by the change of the rod position or boron concentration of the control rod by utilizing the known differential values of the control rod at various rod positions or the differential values of boron at various boron concentrations; the total reactor core reactivity value rho (t) is the sum of the control rod value and the boron concentration value; calculating a neutron fluence rate value n (t) in real time by a point reactor dynamic equation according to rho (t) and a time variable t;
the formula of the point pile dynamic equation is as follows:
wherein:
rho is reactivity;
n (t) is the average neutron density;
Λ is the lifetime of the prompt neutrons;
beta is the effective share of delayed neutrons,
q is neutron source intensity;
βithe fraction of delayed neutrons in the ith group;
λi(t) is decay constant of the ith group of delayed neutron precursor nuclei;
Ci(t) is the concentration of the delayed neutron precursor nucleus in the ith group, wherein
3) Converting n (t) into a pulse signal and a current signal through the efficiency of the detector, and converting the rod position, the boron concentration and the temperature into an auxiliary voltage signal;
4) inputting the pulse signal, the current signal and the auxiliary voltage signal obtained in the step 3) into a reactivity instrument to be detected by the computer, acquiring a signal value and calculating a reactivity value by the reactivity instrument according to a conventional working process, and then comparing the total reactor core reactivity value rho (t) obtained in the step 2) with the reactivity value calculated by the reactivity instrument to be detected to obtain the calculation precision and accuracy of the reactivity instrument to be detected; or comparing the current value output by the computer with the current value acquired by the reactivity meter to obtain the current acquisition precision of the reactivity meter to be detected.
Preferably, in the step 2), simulating actual reactor operation, adjusting the rod position of a control rod or adjusting the boron concentration of a reactor core, calculating the real-time pulse counting rate and the current value of the reactor detector through point reactor dynamic equation simulation, and driving a pulse signal source module and a current signal source module to output specified pulse signals and current signals in a digital communication mode; the computer can dynamically simulate the neutron fluence rate signals of the reactor, namely neutron pulse and neutron current, and simultaneously transmit the neutron pulse and the neutron current to the reactivity meter to be measured by changing the control rod position, the boron concentration and the reactivity value or the reactor core parameter value.
The invention can calculate the neutron fluence rate level of the point reactor in real time by changing the movement of a control rod or the setting of boron concentration, so as to simulate the reactor extrapolation critical process, the conventional starting physical test process, the boron regulation, the rod falling process, the dynamic rod engraving process and the like, and data flow representing the neutron fluence rate level generated in the calculation process is sent to a computer in a communication cable mode to generate simulated neutron pulse and current signals, so that the invention can carry out all-around test on various reactivity instruments, can be used for assisting the research and development of novel reactivity instruments, can also detect the performance state of the reactivity instruments and carries out fault diagnosis.
Drawings
FIG. 1 is a schematic block diagram of the system of the present invention;
FIG. 2 is a flow chart of the system operation of the present invention.
Detailed Description
See the drawings. The special system comprises a computer with an operation display screen, a USB communication circuit, a pulse signal source module, a current signal source module and a voltage signal source module, wherein reactivity calculation software is arranged in the computer, the computer is connected with a USB-to-serial port module through a USB, the USB-to-serial port module is connected with the current signal source module, the pulse signal source module and the voltage signal source module, and the output ends of the current signal source module, the pulse signal source module and the auxiliary voltage signal source module are respectively connected with a neutron current input interface, a pulse signal input interface and a voltage signal input interface of the reactivity instrument to be detected. The computer can also be directly connected with another computer installed with reactive computing software through an RJ45 network port, and the connection mode can be separated from a hardware part to perform function demonstration of the system from a software layer.
The operating logic of the reactivity calculation software is as follows:
1) the operation display screen of the computer is provided with a system setting interface, and the reactor core parameter value is preset on the system setting interface: instantaneous neutron lifetimeLambda, delayed neutron precursor nucleus decay constant lambdaiI group delayed neutron fraction betaiThe parameters are all determined values for a certain reactor core, and the numerical values of the parameters can be calculated and given through a professional core program;
2) simulating the operation of the reactor, adjusting the rod position of a control rod or adjusting the boron concentration of the reactor core, and obtaining the reactivity value caused by the change of the rod position of the control rod or the boron concentration by utilizing the known differential values of the control rod at various rod positions or the differential values of the boron at various boron concentrations; the total reactor core reactivity value rho (t) is the sum of the control rod value and the boron value; calculating a neutron fluence rate value n (t) in real time by a point reactor dynamic equation according to rho (t) and a time variable t;
the formula of the point pile dynamic equation is as follows:
wherein:
rho is reactivity and is calculated according to the rod position or the boron concentration or is manually specified by a user;
n (t) is the average neutron density;
Λ is the lifetime of the prompt neutrons;
beta is the effective share of delayed neutrons,
q is neutron source intensity;
βithe fraction of delayed neutrons in the ith group;
λi(t) is decay constant of the ith group of delayed neutron precursor nuclei;
Ci(t) is the concentration of the delayed neutron precursor nucleus in the ith group, wherein
3) Converting n (t) into a pulse signal and a current signal through the efficiency of a detector, wherein for a certain reactor core, the efficiency of the detector is a fixed value in a period of time, and multiplying the fixed value by a coefficient determined by different reactor types and the efficiency of the detector to obtain the pulse signal or the current signal, and driving a pulse signal source module and a current signal source module to output the specified pulse signal and the specified current signal in a digital communication mode; the auxiliary signals such as rod position, boron concentration and temperature can also be converted into auxiliary voltage signals, the auxiliary voltage signals are obtained according to a preset mapping relation, x is the control rod and boron concentration, and the like, y is y, and y is f (x), the mapping relation can be set by a user on an operation display screen, and the relation is a linear mapping relation determined by the upper limit and the lower limit of the auxiliary signals and the upper limit and the lower limit of the voltage signals. For example, if the position of a certain reactor control rod is 0-225 steps and a user wants to output a voltage signal of 1-5V, the upper and lower limits of the auxiliary signal can be set to 225 and 0, respectively, and the upper and lower limits of the voltage can be set to 5V and 1V;
4) inputting the pulse signal, the current signal and the auxiliary voltage signal obtained in the step 3) into a reactivity instrument to be detected by the computer, acquiring the signals by the reactivity instrument according to a conventional working process, calculating a reactivity value, and then comparing the total reactor core reactivity value rho (t) obtained in the step 2) with the reactivity value calculated by the reactivity instrument to be detected to obtain the calculation precision and accuracy of the reactivity instrument to be detected; or comparing the current value output by the computer with the current value acquired by the reactivity meter to obtain the current acquisition precision of the reactivity meter to be detected.
After the user adjusts the concentration of the control rod or boron through a system setting interface on a computer operation display screen, the generated neutron fluence rate signal changes immediately, the change process can simulate the most common dynamic working condition of an actual reactor, the response performance of the reactivity instrument to be tested can be tested through the process, and the test process cannot be realized in other laboratory test means of the existing reactivity instrument. This embodiment enables comprehensive steady state and dynamic testing of reactor reactivity meters.
Claims (2)
1. A dedicated system for testing reactor reactivity instrumentation, characterized by: the computer is connected with a current signal source module, a pulse signal source module and a voltage signal source module, and the output ends of the current signal source module, the pulse signal source module and the voltage signal source module are respectively connected with a neutron current signal input interface, a pulse signal input interface and a voltage signal input interface of the reactivity instrument to be tested;
the test procedure was as follows:
1) setting reactor core parameter values on an operational display screen: lifetime of prompt neutron and decay constant of precursor nucleus of slow neutroniI group delayed neutron fraction betaiAnd neutron source intensity q;
2) adjusting the rod position or boron concentration of the control rod, and obtaining the reactivity value caused by the change of the rod position or boron concentration of the control rod by utilizing the known differential values of the control rod at various rod positions or the differential values of boron at various boron concentrations; the total reactor core reactivity value rho (t) is the sum of the control rod value and the boron concentration value; calculating a neutron fluence rate value n (t) in real time by a point reactor dynamic equation according to rho (t) and a time variable t;
the formula of the point pile dynamic equation is as follows:
wherein:
rho is reactivity;
n (t) is the average neutron density;
Λ is the lifetime of the prompt neutrons;
beta is the effective share of delayed neutrons,
q is neutron source intensity;
βithe fraction of delayed neutrons in the ith group;
λi(t) is decay constant of the ith group of delayed neutron precursor nuclei;
Ci(t) is the concentration of the delayed neutron precursor nucleus in the ith group, wherein
3) Converting n (t) into a pulse signal and a current signal through the efficiency of the detector, and converting the rod position, the boron concentration and the temperature into an auxiliary voltage signal;
4) inputting the pulse signal, the current signal and the auxiliary voltage signal obtained in the step 3) into a reactivity instrument to be detected by the computer, acquiring a signal value and calculating a reactivity value by the reactivity instrument according to a conventional working process, and then comparing the total reactor core reactivity value rho (t) obtained in the step 2) with the reactivity value calculated by the reactivity instrument to be detected to obtain the calculation precision and accuracy of the reactivity instrument to be detected; or comparing the current value output by the computer with the current value acquired by the reactivity meter to obtain the current acquisition precision of the reactivity meter to be detected.
2. The proprietary system for testing reactor reactivity instrumentation according to claim 1, wherein: in the step 2), simulating the actual operation of the reactor, adjusting the rod position of a control rod or adjusting the boron concentration of the reactor core, calculating the real-time pulse counting rate and the current value of the reactor detector through simulation of a point reactor dynamic equation, and driving a pulse signal source module and a current signal source module to output specified pulse signals and current signals in a digital communication mode; the computer can dynamically simulate the neutron fluence rate signals of the reactor, namely neutron pulse and neutron current, and simultaneously transmit the neutron pulse and the neutron current to the reactivity meter to be measured by changing the control rod position, the boron concentration and the reactivity value or the reactor core parameter value.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113871040A (en) * | 2021-09-29 | 2021-12-31 | 福州奇正谷科技有限公司 | Reactivity instrument and system with background current correction |
| CN114171220A (en) * | 2021-12-03 | 2022-03-11 | 中国原子能科学研究院 | Method and device for measuring integral value of control rod and/or control drum |
| CN115641973A (en) * | 2022-09-09 | 2023-01-24 | 中国核动力研究设计院 | Verification system and method for reactor core neutron flux measurement system |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113871040A (en) * | 2021-09-29 | 2021-12-31 | 福州奇正谷科技有限公司 | Reactivity instrument and system with background current correction |
| CN114171220A (en) * | 2021-12-03 | 2022-03-11 | 中国原子能科学研究院 | Method and device for measuring integral value of control rod and/or control drum |
| CN114171220B (en) * | 2021-12-03 | 2024-02-20 | 中国原子能科学研究院 | Control rod and/or control drum integral value measuring method and device |
| CN115641973A (en) * | 2022-09-09 | 2023-01-24 | 中国核动力研究设计院 | Verification system and method for reactor core neutron flux measurement system |
| CN115641973B (en) * | 2022-09-09 | 2024-05-07 | 中国核动力研究设计院 | Verification system and method for reactor core neutron flux measurement system |
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Application publication date: 20210810 |