CN114758802A - Doppler heating point power determination method, device and storage medium - Google Patents
Doppler heating point power determination method, device and storage medium Download PDFInfo
- Publication number
- CN114758802A CN114758802A CN202210347720.XA CN202210347720A CN114758802A CN 114758802 A CN114758802 A CN 114758802A CN 202210347720 A CN202210347720 A CN 202210347720A CN 114758802 A CN114758802 A CN 114758802A
- Authority
- CN
- China
- Prior art keywords
- power
- measured
- doppler
- determining
- 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.)
- Granted
Links
- 238000000034 method Methods 0.000 title claims abstract description 40
- 238000010438 heat treatment Methods 0.000 title claims abstract description 36
- 238000012545 processing Methods 0.000 claims description 29
- 230000008859 change Effects 0.000 claims description 21
- 239000000523 sample Substances 0.000 claims description 21
- 238000005259 measurement Methods 0.000 claims description 17
- 230000020169 heat generation Effects 0.000 claims description 16
- 238000001514 detection method Methods 0.000 claims description 14
- 238000012360 testing method Methods 0.000 abstract description 10
- 230000004907 flux Effects 0.000 description 10
- 230000009257 reactivity Effects 0.000 description 10
- 238000010586 diagram Methods 0.000 description 9
- 230000000694 effects Effects 0.000 description 8
- 239000000446 fuel Substances 0.000 description 7
- 230000006870 function Effects 0.000 description 6
- 230000008569 process Effects 0.000 description 5
- 230000003287 optical effect Effects 0.000 description 4
- 238000004590 computer program Methods 0.000 description 3
- 230000007423 decrease Effects 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 239000004568 cement Substances 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000002093 peripheral effect Effects 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000006978 adaptation Effects 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 238000003491 array Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000000977 initiatory effect Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000002243 precursor Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 230000002441 reversible effect Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- 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
- G21C17/108—Measuring reactor flux
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Secondary Cells (AREA)
- Measurement Of Resistance Or Impedance (AREA)
- Measurement Of Radiation (AREA)
Abstract
The disclosure provides a Doppler heating point power determination method, a device and a storage medium, wherein the method comprises the following steps: the method is used for determining the Doppler heating point power intuitively and quickly, and can reduce errors, so that the upper limit value of the power level of a subsequent reactor starting physical test can be determined favorably.
Description
Technical Field
The present disclosure relates to the field of nuclear energy technologies, and in particular, to a doppler heating point power determination method, apparatus, and storage medium.
Background
After the high-temperature gas cooled reactor finishes fuel loading, a reactor starting physical test needs to be carried out, and the test items comprise: performing a first critical test under a helium atmosphere; determining and testing the power of a Doppler heating point; a control rod reactivity value measurement test; absorption ball reactivity value measurement test; a reactor isothermal temperature coefficient measurement test; control rod reactivity measurement for the core precursor, and determination of the doppler power level is a prerequisite for the initiation of the physical test. And the mode of confirming Doppler heating point power in the correlation technique adopts the periodic method, and the cycle is longer, and has the problem such as error. Therefore, how to accurately and intuitively determine the power of the doppler heating point is a problem that needs to be solved at present.
Disclosure of Invention
The present disclosure provides a doppler heat spot power determination method, device and storage medium, which aim to solve at least one of the technical problems in the related art to some extent.
An embodiment of a first aspect of the present disclosure provides a method for determining doppler heating point power, including: obtaining a plurality of detector measurement powers of reactor leakage neutrons within a period of time; processing the plurality of probe measured powers to determine a rate of increase parameter of the plurality of probe measured powers over time; and determining the Doppler heating point power of the reactor according to the change condition of the growth rate parameter.
An embodiment of a second aspect of the present disclosure provides a doppler heating point power determination apparatus, including: the acquisition module is used for acquiring the measured power of a plurality of detectors of the leakage neutrons of the reactor within a period of time; the processing module is used for processing the plurality of detector measurement powers to determine a growth rate parameter of the plurality of detector measurement powers changing along with time; and the determining module is used for determining the Doppler heating point power of the reactor according to the change condition of the growth rate parameter.
An embodiment of a third aspect of the present disclosure provides a computer device, including: at least one processor; and a memory communicatively coupled to the at least one processor; wherein the memory stores instructions executable by the at least one processor to enable the at least one processor to perform the Doppler heat generation Point power determination method of the disclosed embodiments.
A fourth aspect of the present disclosure provides a non-transitory computer-readable storage medium storing computer instructions for causing a computer to execute a doppler heat generation point power determination method disclosed in an embodiment of the present disclosure.
In the embodiment, the power measured by a plurality of detectors for obtaining the leakage neutrons of the reactor within a period of time; processing the plurality of probe measured powers to determine a rate of increase parameter of the plurality of probe measured powers over time; the Doppler heating point power of the reactor is determined according to the change condition of the growth rate parameter, the Doppler heating point power can be accurately and visually determined by measuring the growth rate of the power through the detector, the method is used for determining the Doppler heating point power visually and conveniently, errors can be reduced, and therefore the method is beneficial to determining the upper limit value of the power level of a subsequent reactor starting physical test.
Additional aspects and advantages of the disclosure will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the disclosure.
Drawings
The foregoing and/or additional aspects and advantages of the present disclosure will become apparent and readily appreciated from the following description of the embodiments, taken in conjunction with the accompanying drawings of which:
fig. 1 is a schematic flow chart diagram of a doppler heat generation point power determination method according to an embodiment of the present disclosure;
FIG. 2 is a schematic diagram of a plurality of detectors measuring power over time provided in accordance with an embodiment of the present disclosure;
FIG. 3 is a graphical illustration of a plurality of measured log power values over time provided in accordance with an embodiment of the present disclosure;
FIG. 4 is a schematic flow chart diagram of a Doppler hot spot power determination method according to another embodiment of the disclosure;
FIG. 5 is a schematic diagram of a Doppler hot spot power determination apparatus provided in accordance with another embodiment of the present disclosure;
FIG. 6 illustrates a block diagram of an exemplary computer device suitable for use in implementing embodiments of the present disclosure.
Detailed Description
Reference will now be made in detail to the embodiments of the present disclosure, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are illustrative only for the purpose of explaining the present disclosure, and are not to be construed as limiting the present disclosure. On the contrary, the embodiments of the disclosure include all changes, modifications and equivalents coming within the spirit and terms of the claims appended hereto.
It should be noted that an executing body of the doppler heat generation point power determining method of this embodiment may be a doppler heat generation point power determining device, the device may be implemented by software and/or hardware, the device may be configured in an electronic device, and the electronic device may include, but is not limited to, a terminal, a server, and the like.
Fig. 1 is a schematic flowchart of a doppler heat generation point power determination method according to an embodiment of the present disclosure, as shown in fig. 1, the method includes:
s101: a plurality of detector measurements of power of reactor leak neutrons over a period of time are acquired.
The power measured by the detector is used to describe the power condition of the detector in detecting leakage neutrons of the nuclear reactor, which is related to the neutron flux of the reactor, and the reactor may be, for example, a high temperature gas cooled reactor or other reactors, without limitation.
In practice, one or more detectors may be placed outside the core pressure vessel (e.g., cement shield) of the high temperature gas cooled reactor to detect the change in reactor neutron flux during the critical approach and at zero power conditions. The neutron flux is proportional to the power measured by the detector of the detector, that is, the higher the neutron flux in the reactor core, the more neutrons leak around the reactor, and the higher the power measured by the detector (i.e., also referred to as responsivity). Thus, the detector measurement power can be obtained from the detected amount of leaking neutrons.
Wherein, it is found through research that the doppler effect is usually generated in the detection range of the middle range detector, so the embodiment of the present disclosure may, for example, detect the leaking neutron by using the middle range detector to obtain the detector measurement power, that is: the mid-range detector measures power. In addition, the acquisition, analysis and the like of the measured power of the detector can be controlled through a data acquisition system (DCS) of the power plant, human errors are overcome, and the workload is reduced.
In some embodiments, the leaky neutrons may be detected at a plurality of consecutive time points within a period of time to obtain a plurality of detector measurement powers, where a time interval of each detection may be flexibly set according to an actual application, which is not limited herein.
For example, the power measured by the plurality of detectors is shown in table 1 below:
wherein, the period of time is 21:45:00-21:45:30, the detection time interval is 2 seconds, that is, the reactor is detected once every 2 seconds by using the detector, and the measured power of the detector at the moment (which can be represented by A) is obtained, so that a plurality of continuous measured powers of the detector can be detected in a period of time.
In practical applications, the reactivity p may be introduced in the reactor, for example: a bundle of control rods is lifted to a certain height, and during the lifting (i.e., a period of time), detectors detecting different points in time measure the power.
S102: the plurality of probe measured powers are processed to determine a rate of increase parameter of the plurality of probe measured powers over time.
In order to overcome the influence of large fluctuation of the measured power of the off-stack detector along with time, the measured power of each detector can be processed, namely: after obtaining the plurality of probe measured powers, the plurality of probe measured powers may be further processed, such as natural logarithm processing, to determine a growth rate parameter.
In some embodiments, fig. 2 is a schematic diagram of changes of the measured powers of the multiple detectors according to an embodiment of the present disclosure over time, as shown in fig. 2, in the process of lifting a bundle of control rods, the neutron flux in the reactor is reflected to increase exponentially (that is, the reactor power increases exponentially), and when the power rises to a certain value, the fuel temperature rises significantly, and the fuel temperature rises, which may cause a decrease in reactivity.
Specifically, in the operation of determining the growth rate parameter, the measured powers of the plurality of detectors are first subjected to natural logarithm processing to determine corresponding measured power logarithm values, as shown in table 1 above, that is, the measured powers a of the detector in the third row are subjected to logarithm processing respectively to obtain corresponding measured power logarithm values (the measured power logarithm values in the second row)
And further, determining a growth rate parameter according to the plurality of measured power logarithm values and the corresponding time points of the plurality of detections. The time point of the multiple detections is, for example, the time in the first column in table 1, that is, the growth rate parameter is determined according to the variation relationship between the multiple measured power logarithm values and the time points of the multiple detections.
In some embodiments, a target curve may be fitted based on a plurality of measured power log values and corresponding time points of a plurality of detections, and fig. 3 is a schematic diagram of a plurality of measured power log values over time provided according to an embodiment of the present disclosure, namely: a schematic of the target curve, as shown in fig. 3, the measured log power value over time may be approximated as a straight line that increases linearly. Therefore, the slope of the target curve can be further used as the increase rate parameter.
Therefore, the embodiment of the disclosure can determine the growth rate parameter according to the plurality of measured power logarithm values and the linear growth straight line fitted with the plurality of time points, can overcome the influence of larger fluctuation of the measured power of the off-stack detector along with time, and intuitively reflects the growth condition of the measured power of the detector.
S103: and determining the Doppler heating point power of the reactor according to the change condition of the growth rate parameter.
In practical application, the reactor introduces reactivity, the reactor power continuously rises, if the reactor fission nuclear power reaches a certain degree, the reactor fuel temperature obviously rises, the reactor reactivity is reduced after the fuel temperature rises, and the effect is Doppler effect.
In the embodiment of the disclosure, the doppler heating point power of the reactor can be determined according to the change condition of the growth rate parameter.
The growth rate parameter is determined by the detected power measured by the detector, so that the power of the reactor can be reflected, the power change condition can be determined according to the change condition of the growth rate parameter, and then the position point where the Doppler effect occurs is judged, namely: the doppler heat spot and the power of the doppler heat spot may be referred to as doppler heat spot power.
In the embodiment, the power measured by a plurality of detectors for obtaining the leakage neutrons of the reactor within a period of time; performing natural log processing on the plurality of probe measured powers to determine a rate of increase parameter of the plurality of probe measured powers over time; and determining the power of the Doppler heating point of the reactor according to the change condition of the growth rate parameter, and intuitively and quickly determining the power of the Doppler heating point through the growth rate of the power measured by the detector.
Fig. 4 is a flowchart illustrating a doppler heat generation point power determination method according to another embodiment of the present disclosure, as shown in fig. 4, the method includes:
s401: a plurality of detector measurements of power of reactor leak neutrons over a period of time are acquired.
S402: natural log processing is performed on the plurality of detector measured powers to determine a corresponding plurality of measured power log values.
S403: and fitting a target curve based on the plurality of measured power logarithm values and the corresponding time points of the plurality of detections.
S404: the slope of the target curve is used as the growth rate parameter.
For description of S401 to S404, reference may be made to the foregoing embodiments, which are not described herein again.
S405: and determining a slope-invariant increasing curve in the target curve.
As described in the foregoing embodiments, during the reactor fission reaction, the neutron flux in the reactor is reflected to increase exponentially (i.e., the reactor power increases exponentially), and when the power increases to a certain value, the fuel temperature significantly increases, and the fuel temperature increases to cause the reactivity to decrease, so that the doppler effect occurs. That is, the power measured by the detector increases exponentially before the doppler effect occurs, and the slope of the target curve shown in fig. 3 is constant, and is a straight line.
S506: an inflection point at which the slope of the growth curve first becomes smaller is determined.
That is, the power measured by the detector decreases after the doppler effect occurs, which corresponds to the first decreasing slope of the growth curve of fig. 3.
S507: and taking the power measured by the detector corresponding to the inflection point as the power of the Doppler heating point.
That is, the inflection point is taken as the doppler heat generation point, and the detector measurement power at the inflection point corresponds to the doppler heat generation point power. The power of the Doppler heating point can be intuitively and quickly determined according to the inflection point change of the target curve.
In the embodiment, the power is measured by a plurality of detectors for obtaining reactor leakage neutrons in a period of time; performing natural logarithm processing on the measured power of the plurality of detectors to determine a growth rate parameter of the logarithmic value of the measured power of the plurality of detectors changing along with time; and determining the power of the Doppler heating point of the reactor according to the change condition of the growth rate parameter, and intuitively and quickly determining the power of the Doppler heating point through the growth rate of the power measured by the detector. In addition, the power of the Doppler heating point can be intuitively and accurately determined according to the change of the inflection point of the target curve.
In one embodiment, the doppler heat generation point power determination process is as follows:
1. the cement shielding layer outside the nuclear reactor in Shishidawan is provided with a middle range detector A, B, and the reactor is used for monitoring the change of the neutron flux in the reactor core in the critical approaching process and the zero power state. The higher the reactor core neutron flux, the more neutrons leaking around the reactor, the higher the middle range detector response, and the middle range A, B power is proportional to the reactor core neutron flux.
2. According to the neutron dynamics equation, assuming that the reactor introduces a reactivity, the neutron flux in the reactor increases exponentially, and the intermediate detector measures the power change to generate a stable period. The change in measured power of the intermediate probe over time is shown in figure 2.
3. The change data of the logarithmic power signals measured by the intermediate detector along with time is acquired through a data acquisition system (DCS) of a power plant, and the logarithmic power signals measured by the intermediate detector along with time are in an inclined straight line before a Doppler heating point appears.
4. Along with the rise of power, Doppler heating effect occurs, the reactor core reactivity is reduced due to fuel temperature feedback, the relation of logarithmic power signals measured by the middle detector along with time also changes, the oblique line deflects, the slope is reduced, and accordingly Doppler heating point power is found. The logarithmic power data curve of the intermediate probe is shown in fig. 3.
Fig. 5 is a schematic diagram of a doppler heat generation point power determination apparatus provided according to another embodiment of the present disclosure. As shown in fig. 5, the doppler heat generation point power determination device 50 includes:
an obtaining module 501, configured to obtain multiple detector measurement powers of reactor leakage neutrons over a period of time;
a processing module 502, configured to perform natural logarithm processing on the multiple probe measured powers to determine a growth rate parameter of the multiple probe measured powers changing with time; and
and the determining module 503 is configured to determine the doppler heating point power of the reactor according to the change condition of the growth rate parameter.
In some embodiments, the processing module 502 includes:
the processing submodule is used for performing natural logarithm processing on the measured power of the plurality of detectors so as to determine a plurality of corresponding measured power logarithm values; and
and the determining submodule is used for determining the growth rate parameter according to the plurality of measured power logarithm values and the corresponding time points of the plurality of detections.
In some embodiments, the determining submodule is specifically configured to:
fitting a target curve based on the plurality of measured power logarithm values and the corresponding time points of the plurality of detections;
the slope of the target curve is used as the growth rate parameter.
In some embodiments, the determining module is specifically configured to:
determining a growth curve with unchanged slope in the target curve;
determining an inflection point at which the slope of the growth curve becomes smaller for the first time; and
and taking the power measured by the detector corresponding to the inflection point as the power of the Doppler heating point.
In the embodiment, the power measured by a plurality of detectors for obtaining the leakage neutrons of the reactor within a period of time; performing natural log processing on the plurality of detector measured powers to determine a rate of increase parameter of the plurality of detector measured powers over time; and determining the power of the Doppler heating point of the reactor according to the change condition of the growth rate parameter, and intuitively and quickly determining the power of the Doppler heating point through the growth rate of the power measured by the detector.
The present disclosure also provides a computer device, a readable storage medium, and a computer program product according to embodiments of the present disclosure.
In order to implement the foregoing embodiments, the present disclosure also proposes a computer program product, which when being executed by an instruction processor in the computer program product, executes the doppler heat generation point power determination method proposed by the foregoing embodiments of the present disclosure.
FIG. 6 illustrates a block diagram of an exemplary computer device suitable for use in implementing embodiments of the present disclosure. The computer device 12 shown in FIG. 6 is only one example and should not impose any limitations on the functionality or scope of use of embodiments of the present disclosure.
As shown in FIG. 6, computer device 12 is in the form of a general purpose computing device. The components of computer device 12 may include, but are not limited to: one or more processors or processing units 16, a system memory 28, and a bus 18 that couples various system components including the system memory 28 and the processing unit 16.
Although not shown in FIG. 6, a disk drive for reading from and writing to a removable, nonvolatile magnetic disk (e.g., a "floppy disk") and an optical disk drive for reading from or writing to a removable, nonvolatile optical disk (e.g., a Compact disk Read Only Memory (CD-ROM), a Digital versatile disk Read Only Memory (DVD-ROM), or other optical media) may be provided. In these cases, each drive may be connected to bus 18 by one or more data media interfaces. Memory 28 may include at least one program product having a set (e.g., at least one) of program modules that are configured to carry out the functions of embodiments of the disclosure.
A program/utility 40 having a set (at least one) of program modules 42 may be stored, for example, in memory 28, such program modules 42 including, but not limited to, an operating system, one or more application programs, other program modules, and program data, each of which examples or some combination thereof may comprise an implementation of a network environment. Program modules 42 generally perform the functions and/or methodologies of the embodiments described in this disclosure.
The processing unit 16 executes various functional applications, such as implementing the doppler heat generation point power determination method mentioned in the foregoing embodiments, by running a program stored in the system memory 28.
Other embodiments of the disclosure will be apparent to those skilled in the art from consideration of the specification and practice of the disclosure disclosed herein. This disclosure is intended to cover any variations, uses, or adaptations of the disclosure following, in general, the principles of the disclosure and including such departures from the present disclosure as come within known or customary practice within the art to which the disclosure pertains. It is intended that the specification and examples be considered as exemplary only, with a true scope and spirit of the disclosure being indicated by the following claims.
It will be understood that the present disclosure is not limited to the precise arrangements described above and shown in the drawings and that various modifications and changes may be made without departing from the scope thereof. The scope of the present disclosure is limited only by the appended claims.
It should be noted that, in the description of the present disclosure, the terms "first", "second", etc. are used for descriptive purposes only and are not to be construed as indicating or implying relative importance. Further, in the description of the present disclosure, "a plurality" means two or more unless otherwise specified.
Any process or method descriptions in flow charts or otherwise described herein may be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps of the process, and the scope of the preferred embodiments of the present disclosure includes other implementations in which functions may be executed out of order from that shown or discussed, including substantially concurrently or in reverse order, depending on the functionality involved, as would be understood by those reasonably skilled in the art of the embodiments of the present disclosure.
It should be understood that portions of the present disclosure may be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, the various steps or methods may be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, any one or combination of the following techniques, which are known in the art, may be used: a discrete logic circuit having a logic gate circuit for implementing a logic function on a data signal, an application specific integrated circuit having an appropriate combinational logic gate circuit, a Programmable Gate Array (PGA), a Field Programmable Gate Array (FPGA), or the like.
It will be understood by those skilled in the art that all or part of the steps carried by the method for implementing the above embodiments may be implemented by hardware related to instructions of a program, which may be stored in a computer readable storage medium, and when the program is executed, the program includes one or a combination of the steps of the method embodiments.
In addition, functional units in the embodiments of the present disclosure may be integrated into one processing module, or each unit may exist alone physically, or two or more units are integrated into one module. The integrated module can be realized in a hardware mode, and can also be realized in a software functional module mode. The integrated module, if implemented in the form of a software functional module and sold or used as a stand-alone product, may also be stored in a computer readable storage medium.
The storage medium mentioned above may be a read-only memory, a magnetic or optical disk, etc.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the present disclosure. In this specification, the schematic representations of the terms used above do not necessarily refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
While embodiments of the present disclosure have been shown and described above, it will be understood that the above embodiments are exemplary and not to be construed as limiting the present disclosure, and that changes, modifications, substitutions and alterations may be made to the above embodiments by those of ordinary skill in the art within the scope of the present disclosure.
Claims (10)
1. A Doppler heat generation point power determination method is characterized by comprising the following steps:
obtaining a plurality of detector measurement powers of reactor leakage neutrons within a period of time;
processing the plurality of probe measured powers to determine a rate of increase parameter of the plurality of probe measured powers over time; and
and determining the Doppler heating point power of the reactor according to the change condition of the growth rate parameter.
2. The method of claim 1, wherein processing the plurality of probe measurement powers to determine a rate of increase parameter of the plurality of probe measurement powers over time comprises:
performing natural logarithm processing on the plurality of detector measured powers to determine a corresponding plurality of measured power logarithm values; and
and determining a growth rate parameter according to the plurality of measured power logarithm values and the corresponding time points of the plurality of detections.
3. The method of claim 2, wherein determining a growth rate parameter based on the plurality of log-measured-power values and corresponding points in time of the plurality of probes comprises:
fitting a target curve based on the plurality of measured power logarithm values and the corresponding time points of the plurality of detections;
and taking the slope of the target curve as the growth rate parameter.
4. The method of claim 3, wherein determining the Doppler heating point power of the reactor based on the change in the growth rate parameter comprises:
determining a slope-invariant growth curve in the target curve;
determining an inflection point at which the slope of the growth curve becomes smaller for the first time; and
and taking the power measured by the detector corresponding to the inflection point as the power of the Doppler heating point.
5. The method of any of claims 1-4, wherein the plurality of detector measured powers are detected by one or more off-stack detectors.
6. A doppler heat generation point power determination device, comprising:
the acquisition module is used for acquiring the measured power of a plurality of detectors of the leakage neutrons of the reactor within a period of time;
a processing module for processing the plurality of probe measured powers to determine a growth rate parameter of the plurality of probe measured powers over time; and
and the determining module is used for determining the Doppler heating point power of the reactor according to the change condition of the growth rate parameter.
7. The apparatus of claim 6, wherein the processing module comprises:
the processing submodule is used for performing natural logarithm processing on the plurality of detector measured powers so as to determine a plurality of corresponding measured power logarithm values; and
and the determining submodule is used for determining the growth rate parameter according to the plurality of measured power log values and the corresponding time points of the plurality of detections.
8. The apparatus of claim 7, wherein the determination submodule is specifically configured to:
fitting a target curve based on the plurality of measured power logarithm values and the corresponding time points of the plurality of detections;
and taking the slope of the target curve as the growth rate parameter.
9. The apparatus of claim 8, wherein the determination module is specifically configured to:
determining a slope-invariant growth curve in the target curve;
determining an inflection point at which the slope of the growth curve becomes smaller for the first time; and
and taking the power measured by the detector corresponding to the inflection point as the power of the Doppler heating point.
10. A non-transitory computer readable storage medium having stored thereon computer instructions for causing the computer to perform the method of any one of claims 1-5.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210347720.XA CN114758802B (en) | 2022-04-01 | 2022-04-01 | Doppler heating point power determination method, device and storage medium |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210347720.XA CN114758802B (en) | 2022-04-01 | 2022-04-01 | Doppler heating point power determination method, device and storage medium |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN114758802A true CN114758802A (en) | 2022-07-15 |
| CN114758802B CN114758802B (en) | 2023-05-16 |
Family
ID=82328979
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210347720.XA Active CN114758802B (en) | 2022-04-01 | 2022-04-01 | Doppler heating point power determination method, device and storage medium |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114758802B (en) |
Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3255084A (en) * | 1963-05-17 | 1966-06-07 | Sulzer Ag | Method and apparatus for control of a nuclear power plant |
| FR2914103A1 (en) * | 2007-03-19 | 2008-09-26 | Areva Np Sas | Core power density distribution determining method for monitoring e.g. critical heat flux ratio, in pressurized water reactor, involves determining new power density distribution by adjusting power density distribution with measurements |
| US20080312534A1 (en) * | 2007-06-07 | 2008-12-18 | Kyriacos Pitsillides | System and method for power management in a telemetric monitoring system |
| CN103345950A (en) * | 2013-07-12 | 2013-10-09 | 中科华核电技术研究院有限公司 | Ex-core nuclear detection system and method for pressurized water reactor |
| US20170003312A1 (en) * | 2015-06-30 | 2017-01-05 | Canon Kabushiki Kaisha | Velocimeter and method of manufacturing article |
| CN107887043A (en) * | 2017-10-10 | 2018-04-06 | 福建福清核电有限公司 | A kind of reactor capability coefficient measuring method |
| CN109273119A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Optimize the method for neutron detector position when measuring big reactivity on critical assembly |
| CN109509562A (en) * | 2018-12-07 | 2019-03-22 | 中国科学院上海应用物理研究所 | Core structure, the fuel management of fused salt pebble bed reactor and fused salt pebble bed reactor and core loading method |
| CN110111917A (en) * | 2019-04-17 | 2019-08-09 | 中广核工程有限公司 | Out-pile neutrons in nuclei flux monitoring method, apparatus and readable storage medium storing program for executing after accident |
| CN113255249A (en) * | 2021-06-07 | 2021-08-13 | 清华大学 | Multi-physical coupling transient calculation method and device for heat pipe solid state stack |
| CN114242280A (en) * | 2021-11-17 | 2022-03-25 | 华能核能技术研究院有限公司 | Reactor reactivity measuring method, device, equipment and storage medium |
-
2022
- 2022-04-01 CN CN202210347720.XA patent/CN114758802B/en active Active
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3255084A (en) * | 1963-05-17 | 1966-06-07 | Sulzer Ag | Method and apparatus for control of a nuclear power plant |
| FR2914103A1 (en) * | 2007-03-19 | 2008-09-26 | Areva Np Sas | Core power density distribution determining method for monitoring e.g. critical heat flux ratio, in pressurized water reactor, involves determining new power density distribution by adjusting power density distribution with measurements |
| US20080312534A1 (en) * | 2007-06-07 | 2008-12-18 | Kyriacos Pitsillides | System and method for power management in a telemetric monitoring system |
| CN103345950A (en) * | 2013-07-12 | 2013-10-09 | 中科华核电技术研究院有限公司 | Ex-core nuclear detection system and method for pressurized water reactor |
| US20170003312A1 (en) * | 2015-06-30 | 2017-01-05 | Canon Kabushiki Kaisha | Velocimeter and method of manufacturing article |
| CN107887043A (en) * | 2017-10-10 | 2018-04-06 | 福建福清核电有限公司 | A kind of reactor capability coefficient measuring method |
| CN109273119A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Optimize the method for neutron detector position when measuring big reactivity on critical assembly |
| CN109509562A (en) * | 2018-12-07 | 2019-03-22 | 中国科学院上海应用物理研究所 | Core structure, the fuel management of fused salt pebble bed reactor and fused salt pebble bed reactor and core loading method |
| CN110111917A (en) * | 2019-04-17 | 2019-08-09 | 中广核工程有限公司 | Out-pile neutrons in nuclei flux monitoring method, apparatus and readable storage medium storing program for executing after accident |
| CN113255249A (en) * | 2021-06-07 | 2021-08-13 | 清华大学 | Multi-physical coupling transient calculation method and device for heat pipe solid state stack |
| CN114242280A (en) * | 2021-11-17 | 2022-03-25 | 华能核能技术研究院有限公司 | Reactor reactivity measuring method, device, equipment and storage medium |
Non-Patent Citations (4)
| Title |
|---|
| 刘臻;杨嗣;王澄瀚;: "秦山第二核电厂寻找多普勒发热点试验方法的优化" * |
| 周旭华;李富;韩松;王登营;颜见秋;: "堆外探测器读数与堆内功率分布的关系研究" * |
| 朱宏亮;刘艳阳;柴晓明;王银丽;张秀万;: "压水堆冷却剂下降段温度对中子探测的影响分析和修正研究" * |
| 谭兴春;: "新堆多普勒发热点有效查找方法探究" * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN114758802B (en) | 2023-05-16 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| RU2491664C2 (en) | Method to measure doppler coefficient of reactivity | |
| EP2801979B1 (en) | Atomic reactor state monitoring device and monitoring method thereof | |
| CN109273119B (en) | Method for optimizing the position of a neutron detector during the measurement of high reactivity on a critical device | |
| KR100991441B1 (en) | Renormalization Method of Excore Neutron Detectors | |
| CN116955027B (en) | MCU chip test system and test method thereof | |
| EP0322541A2 (en) | Apparatus for measuring nuclear reactor power distribution | |
| CN114758802B (en) | Doppler heating point power determination method, device and storage medium | |
| US11280750B2 (en) | Boiling point water activity measurement | |
| CN114420328B (en) | Method and device for monitoring subcritical degree of reactor | |
| JPH1039083A (en) | In-furnace information monitoring apparatus | |
| CN110749919A (en) | Method and device for calibrating nuclear reactor out-of-pile detector | |
| CN114242280B (en) | Reactor reactivity measuring method, device, equipment and storage medium | |
| CN212391150U (en) | Temperature sensor precision test system | |
| JP3556409B2 (en) | Reactor power measurement device | |
| CN117292861A (en) | Method, apparatus, device, storage medium and program product for calibrating detector outside pile | |
| JP2002202395A (en) | Reactor power measurement device | |
| JP2001099980A (en) | Nuclear reactor power measuring device | |
| JP2009150704A (en) | Method and device for cold criticality test | |
| JP2002341083A (en) | In-core nuclear instrumentation detector aggregate and reactor output monitoring device | |
| RU2165109C2 (en) | Method for experimental detection of local dips of multiplication constant in active zone of subcritical pile | |
| CN115798753A (en) | Method and device for measuring void fraction in pressure vessel of pressurized water reactor nuclear power plant | |
| JPH04115193A (en) | Measuring apparatus for average burnup of nuclear fuel assembly | |
| JP3442598B2 (en) | Fixed in-core instrumentation system | |
| CN116844745A (en) | Method for measuring leakage current of vanadium fixed detector in reactor | |
| CN115326276A (en) | Temperature compensation method and equipment for Pirani vacuum gauge and calculation method and equipment for environmental vacuum degree |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| EE01 | Entry into force of recordation of patent licensing contract |
Application publication date: 20220715 Assignee: HUANENG SHANDONG SHIDAOBAY NUCLEAR POWER Co.,Ltd. Assignor: Huaneng Nuclear Energy Technology Research Institute Co.,Ltd. Contract record no.: X2023110000137 Denomination of invention: Method, device, and storage medium for determining Doppler hotspot power Granted publication date: 20230516 License type: Common License Record date: 20231201 |
|
| EE01 | Entry into force of recordation of patent licensing contract |