CN104934084B - A kind of fuel for nuclear power plant cladding damage monitoring method and system - Google Patents
A kind of fuel for nuclear power plant cladding damage monitoring method and system Download PDFInfo
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- CN104934084B CN104934084B CN201510204682.2A CN201510204682A CN104934084B CN 104934084 B CN104934084 B CN 104934084B CN 201510204682 A CN201510204682 A CN 201510204682A CN 104934084 B CN104934084 B CN 104934084B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
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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
Abstract
The invention discloses a kind of fuel for nuclear power plant cladding damage monitoring method and systems, solve and are unable to on-line continuous monitoring in the prior art, or the technical issues of the defects of be unable to Accurate Diagnosis fuel element cladding breakage shape, and the monitoring method includes step：S1, on-line monitoring obtain the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops coolant；S2, the empirical data for being based on the reactor core running state data and activity concentration data and clad failure carry out n times loop iteration and calculate the practical diagnostic data of N groups for obtaining clad failure；When S3, the convergence coefficient for calculating the 1 group of practical diagnostic data of N obtained in 1 loop iteration of the practical diagnostic data of N groups and N are less than or equal to preset value, determine that 1 group of practical diagnostic data of N is final monitoring, diagnosing result；It realizes on-line continuous monitoring and diagnoses the technique effect of whether damaged fuel element cladding and its damaged character, burnup regional location.
Description
Technical field
The present invention relates to fuel for nuclear power plant cladding Integrity Verification technical field more particularly to a kind of fuel for nuclear power plant
Cladding damage monitoring method and system.
Background technology
Fuel element cladding is responsible for the containing fuel pellet fission product of the task.If fuel element cladding is damaged, split
Becoming product will be discharged into primary Ioops coolant by cut, and potential impact is generated to the safe operation of nuclear power plant.In operation
Timely and accurately judge whether fuel element cladding damaged, break size and damage location to the safe operation of nuclear power plant with
Economical operation has major contribution.
Existing nuclear power plant includes mainly to the method for fuel element cladding breakage monitoring：Total γ (ray) on-line monitorings
Method, the regular sampling method of core sampling system and sipping test system monitoring method.These methods both had its points of course, and there is also certain
Drawback is described as follows：
1) for existing " total γ (ray) monitors method on-line ", γ total radioactive activity surveys are carried out in primary Ioops water
Amount, this is the method that a kind of gross activity of a variety of nucleic in the water to primary Ioops carries out on-line continuous monitoring, if fuel is first
Breakage occurs for part involucrum, and the total γ activity monitored is significantly higher.The advantages of this method is can be cold to primary Ioops
But the radioactive activity of agent is continuously monitored.But this method can not carry out more fuel element cladding breakage
Detailed on-line analysis, can not judge the size and burnup situation of fuel element failure, and be easy to be activated and corrosion product
Interference and report by mistake.
2) for existing " the regular sampling method of core sampling system ", this is a kind of to be periodically sampled to primary Ioops coolant
And to the method for sample progress radioassay.Its advantages of is that the analysis to sample is more careful, accurate.This method lacks
Point is can not to be carried out continuously on-line monitoring, due to sampling and needing the regular hour to the experimental analysis of sample, by sample
The influence of nucleic decay, the judgement that this method is be easy to cause to cut are not prompt enough；The intervention of human factor is increased simultaneously,
Increase the uncertainty of result, and increases nuclear power plant's collective dose and personnel's accident risk of exposure.
3) for existing " sipping test system monitoring method ", this method is during shutdown discharging, and it is online fixed to be divided into
Property analysis and two kinds of offline quantitative analysis.It is to carry out damaged leakage to the fuel assembly after irradiation to visit in linear location sipping test
It surveys, after fuel assembly rises to telescopic sleeve, measure Xe-133 activity by gamma detector is to judge fuel element cladding
It is no to there is breakage.Offline quantitatively sipping test is directed to online qualitative detection and is determined as quantitatively being divided when having damaged fuel assembly
Analysis, this method make fission gas pressure in fuel rod increase using the temperature for improving fuel assembly surrounding fluid, fission gas
(such as Xe-133) will accelerate effusion outward in order to detect.What this method can quantify judges the big of fuel element cladding cut
It is small.But this method is not really monitored on-line, it is necessary to which shutdown could carry out after uncapping, and extremely take, may
Shutdown time can be extended, the economy to nuclear power plant's operation is very unfavorable.
It is unable to on-line continuous monitoring as it can be seen that existing in the prior art, or is unable to Accurate Diagnosis fuel element cladding breakage shape
The technical issues of the defects of shape.
Invention content
The present invention is unable to on-line continuous monitoring, or be unable to Accurate Diagnosis fuel element packet for existing in the prior art
The technical issues of the defects of shell breakage shape, provides a kind of fuel for nuclear power plant cladding damage monitoring method and system, realizes
During nuclear power station is run, on-line continuous monitoring and the whether damaged and its damaged character of diagnosis fuel element cladding, burnup
Regional location etc. can significantly improve safety and the economy of nuclear power station operation.
On the one hand, an embodiment of the present invention provides a kind of fuel for nuclear power plant cladding damage monitoring methods, in core
When power station fuel element cladding occurs damaged, fuel element cladding breakage radical, damaged size and breakage component are monitored and diagnosed
Burnup region, the monitoring method include step：
The radioactive activity that S1, on-line monitoring obtain characteristic nuclide in reactor core running state data and primary Ioops coolant is dense
Degrees of data；
The activity concentration data of S2, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the empirical data of the clad failure, it carries out n times loop iteration and calculates the practical diagnosis of N groups for obtaining the clad failure
Data；
S3, the practical diagnosis of N-1 groups obtained is calculated in the practical diagnostic data of N groups and the N-1 times loop iteration
When data tend to restrain and convergence coefficient is less than or equal to preset value, determine that the practical diagnostic data of N groups is that final monitoring is examined
Disconnected result；
Wherein, N is the integer more than or equal to 1, and the empirical data is specially to carry out shutdown inspection to the clad failure
The empirical value of the clad failure radical and damaged size that are obtained when looking into.
Optionally, first time loop iteration includes sub-step in the step S2：
The activity concentration data of S21, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the empirical value of the clad failure radical in the empirical data of the clad failure and damaged size, it carries out cycle for the first time and changes
In generation, calculates the first value for obtaining clad failure component burnup region；
The activity concentration data of S22, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And empirical value and the clad failure component burnup region of the clad failure size in the empirical data of the clad failure
The first value, carry out first time loop iteration calculate obtain clad failure radical the first value；
The activity concentration data of S23, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the first value of first value and the clad failure radical in the clad failure component burnup region, carry out first time cycle
Iterative calculation obtains the first value of clad failure size；
Wherein, first value in the clad failure component burnup region, the first value of the clad failure radical and described
First value of clad failure size constitutes first group of practical diagnostic data.
Optionally, the practical diagnostic data of N-1 groups obtained after carrying out the N-1 times loop iteration and calculating, including
N-1 values, the N-1 values of the clad failure radical and the clad failure size in the clad failure component burnup region
N-1 values；N-th loop iteration includes sub-step in the step S2：
The activity concentration data of S24, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the N-1 values of the clad failure radical in the practical diagnostic data of N-1 groups and damaged size, carry out n-th cycle
Iterative calculation obtains the N values in clad failure component burnup region；
The activity concentration data of S25, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And N-1 values and the clad failure component burnup area of the clad failure size in the practical diagnostic data of N-1 groups
The N values in domain carry out n-th loop iteration and calculate the N values for obtaining clad failure radical；
The activity concentration data of S26, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the N values of the N values and the clad failure radical in the clad failure component burnup region, it carries out n-th cycle and changes
In generation, calculates the N values for obtaining clad failure size；
Wherein, the N values, the N values of the clad failure radical in the clad failure component burnup region and the packet
The N values of shell breakage size constitute the practical diagnostic data of N groups.
Optionally, the characteristic nuclide includes the isotope of the isotope and the second caesium of the first caesium, and the step S24 is specific
For：
The isotope of first caesium and institute described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
Stating the isotope of the second caesium, the ratio of the activity concentration in primary Ioops coolant and the N-1 groups are real respectively
It is broken to carry out n-th loop iteration calculating acquisition involucrum for the N-1 values of clad failure radical and damaged size in the diagnostic data of border
Damage the N values in component burnup region.
Optionally, the characteristic nuclide includes the isotope of the first inert gas and the first iodine, and the step S25 is specific
For：
Based on the reactor core running state data that on-line monitoring obtains, the physics of the isotope of the first inert gas and the first iodine
The N-1 of chemical property and the burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups
The N values of value and the clad failure component burnup region carry out n-th loop iteration and calculate to obtain the of clad failure radical
N values.
Optionally, the characteristic nuclide includes the isotope of the second inert gas and the second iodine, and the step S26 is specific
For：
Based on the reactor core running state data that on-line monitoring obtains, the isotope of the second inert gas and the second iodine is in reactor core
Leakage coefficient, the N values and the packet in the half-life period of the isotope of the second iodine and the clad failure component burnup region
The N values of shell breakage radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size.
On the other hand, the embodiment of the present invention additionally provides a kind of fuel for nuclear power plant cladding damage monitoring system, is used for
When fuel for nuclear power plant cladding occurs damaged, fuel element cladding breakage radical, damaged size and breakage are monitored and diagnosed
Component burnup region, the monitoring system include：
Data acquisition module obtains characteristic nuclide in reactor core running state data and primary Ioops coolant for monitoring on-line
Activity concentration data；
Practical diagnostic data computing module, the reactor core running state data for being obtained based on on-line monitoring and characteristic nuclide
Activity concentration data and the clad failure empirical data, carry out n times loop iteration and calculate to obtain the packet
The practical diagnostic data of N groups of shell breakage；
Monitoring, diagnosing result determining module, for being calculated in the practical diagnostic data of N groups and the N-1 times loop iteration
When the practical diagnostic data of N-1 groups obtained tends to restrain and convergence coefficient is less than or equal to preset value, determine that the N groups are practical
Diagnostic data is final monitoring, diagnosing result；
Wherein, N is the integer more than or equal to 1, and the empirical data is specially to carry out shutdown inspection to the clad failure
The empirical value of the clad failure radical and damaged size that are obtained when looking into.
Optionally, the practical diagnostic data computing module includes：
First clad failure component burnup region calculated with actual values unit, the reactor core operation for being obtained based on on-line monitoring
Clad failure in the empirical data of the activity concentration data and the clad failure of status data and characteristic nuclide
The empirical value of radical and damaged size carries out first time loop iteration calculates acquisition clad failure component burnup region first
Value；
First clad failure radical calculated with actual values unit, the reactor core running state data for being obtained based on on-line monitoring
With the warp of the clad failure size in the activity concentration data of characteristic nuclide and the empirical data of the clad failure
The first value of value and the clad failure component burnup region is tested, first time loop iteration is carried out and calculates acquisition clad failure radical
The first value；
First clad failure size calculated with actual values unit, the reactor core running state data for being obtained based on on-line monitoring
With the activity concentration data of characteristic nuclide and the first value and the involucrum in the clad failure component burnup region
First value of damaged radical calculates the first value for obtaining clad failure size；
Wherein, first value in the clad failure component burnup region, the first value of the clad failure radical and described
First value of clad failure size constitutes first group of practical diagnostic data.
Optionally, the practical diagnostic data of N-1 groups obtained after carrying out the N-1 times loop iteration and calculating, including
N-1 values, the N-1 values of the clad failure radical and the clad failure size in the clad failure component burnup region
N-1 values；The practical diagnostic data computing module further includes：
N clad failure component burnups region calculated with actual values unit, the reactor core operation for being obtained based on on-line monitoring
The activity concentration data and the involucrum in the practical diagnostic data of N-1 groups of status data and characteristic nuclide are broken
The N-1 values for damaging radical and damaged size carry out n-th loop iteration and calculate the N for obtaining clad failure component burnup region
Value；
N clad failure radical calculated with actual values units, the reactor core running state data for being obtained based on on-line monitoring
With the clad failure size in the activity concentration data of characteristic nuclide and the practical diagnostic data of N-1 groups
The N values of N-1 values and the clad failure component burnup region carry out n-th loop iteration and calculate acquisition clad failure root
Several N values；
N clad failure size calculated with actual values units, the reactor core running state data for being obtained based on on-line monitoring
With the activity concentration data of characteristic nuclide and N values and the involucrum in the clad failure component burnup region
The N values of damaged radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size；
Wherein, the N values, the N values of the clad failure radical in the clad failure component burnup region and the packet
The N values of shell breakage size constitute the practical diagnostic data of N groups.
Optionally, the characteristic nuclide includes the isotope of the isotope and the second caesium of the first caesium, the N clad failures
Component burnup region calculated with actual values unit, is specifically used for：
The isotope of first caesium and institute described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
Stating the isotope of the second caesium, the ratio of the activity concentration in primary Ioops coolant and the N-1 groups are real respectively
It is broken to carry out n-th loop iteration calculating acquisition involucrum for the N-1 values of clad failure radical and damaged size in the diagnostic data of border
Damage the N values in component burnup region.
Optionally, the characteristic nuclide includes the isotope of the first inert gas and the first iodine, the N clad failure roots
Number calculated with actual values unit, is specifically used for：
Based on the reactor core running state data that on-line monitoring obtains, the physics of the isotope of the first inert gas and the first iodine
The N-1 of chemical property and the burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups
The N values of value and the clad failure component burnup region carry out n-th loop iteration and calculate to obtain the of clad failure radical
N values.
Optionally, the characteristic nuclide includes the isotope of the second inert gas and the second iodine, the N clad failure rulers
Very little calculated with actual values unit, is specifically used for：
Based on the reactor core running state data that on-line monitoring obtains, the isotope of the second inert gas and the second iodine is in reactor core
Leakage coefficient, the N values and the packet in the half-life period of the isotope of the second iodine and the clad failure component burnup region
The N values of shell breakage radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size.
One or more technical solution provided in an embodiment of the present invention, has at least the following technical effects or advantages：
Due in embodiments of the present invention, when carrying out the diagnosis of fuel for nuclear power plant cladding breakage monitoring, by online
(i.e. during nuclear power station is run) obtains the radioactive activity of characteristic nuclide in reactor core running state data and primary Ioops coolant
Concentration data, and the activity concentration data of the reactor core running state data and characteristic nuclide obtained based on on-line monitoring,
And the empirical data of the clad failure is (specifically, the involucrum of acquisition is broken when carrying out inspection shutdown to the clad failure
Damage the empirical value of radical and damaged size), it carries out n times loop iteration and calculates the practical diagnosis of N groups for obtaining the clad failure
Data calculate the practical diagnostic data of N-1 groups obtained with the N-1 times loop iteration in the practical diagnostic data of N groups and become
When restraining and convergence coefficient is less than or equal to preset value, determine that the practical diagnostic data of N groups is final monitoring, diagnosing result；
It efficiently solves and is unable to on-line continuous monitoring in the prior art, or be unable to Accurate Diagnosis fuel element cladding breakage shape etc. and lack
Sunken technical problem realizes during nuclear power station is run, on-line continuous monitoring and diagnosis fuel element cladding it is whether damaged and
The technique effect of its damaged character, burnup regional location etc. is conducive to the safety and the economy that significantly improve nuclear power station operation
Property.
Description of the drawings
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below
There is attached drawing needed in technology description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
The embodiment of invention for those of ordinary skill in the art without creative efforts, can also basis
The attached drawing of offer obtains other attached drawings.
Fig. 1 is a kind of fuel for nuclear power plant cladding damage monitoring method flow chart provided in an embodiment of the present invention；
Fig. 2 is the first fuel for nuclear power plant cladding damage monitoring system structure diagram provided in an embodiment of the present invention；
Fig. 3 is second of fuel for nuclear power plant cladding damage monitoring system structure diagram provided in an embodiment of the present invention；
Fig. 4 is the third fuel for nuclear power plant cladding damage monitoring system structure diagram provided in an embodiment of the present invention.
Specific implementation mode
The embodiment of the present invention solves the prior art by providing a kind of fuel for nuclear power plant cladding damage monitoring method
Present in be unable to on-line continuous monitoring, or the technical issues of the defects of be unable to Accurate Diagnosis fuel element cladding breakage shape,
It realizes during nuclear power station is run, the on-line continuous monitoring character whether damaged and its damaged with diagnosis fuel element cladding,
The technique effect of burnup regional location etc..
The technical solution of the embodiment of the present invention is in order to solve the above technical problems, general thought is as follows：
An embodiment of the present invention provides a kind of fuel for nuclear power plant cladding damage monitoring methods, in fuel for nuclear power plant
When cladding occurs damaged, fuel element cladding breakage radical, damaged size and breakage component burnup region are monitored and diagnose,
The monitoring method includes step：S1, on-line monitoring obtain characteristic nuclide in reactor core running state data and primary Ioops coolant
Activity concentration data；The radioactivity of S2, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring
The empirical data of activity concentration data and the clad failure carries out n times loop iteration and calculates the acquisition clad failure
The practical diagnostic data of N groups；S3, the N-1 obtained is calculated in the practical diagnostic data of N groups and the N-1 times loop iteration
When the practical diagnostic data of group tends to restrain and convergence coefficient is less than or equal to preset value, determine that the practical diagnostic data is final prison
Survey diagnostic result；Wherein, N is the integer more than or equal to 1, and the empirical data is specially to carry out shutdown to the clad failure
The empirical value of the clad failure radical and damaged size that are obtained when inspection.
As it can be seen that in embodiments of the present invention, with the fission reaction theory and fission product of nuclear fuel in pressurized water reactor core
The mechanism of release, migration, deposition in power plant's primary Ioops coolant is theoretical foundation, is established based on feature in primary Ioops coolant
The mathematical model of the fuel element cladding breakage diagnosis of nucleic activity analysis, specifically, after breakage occurs in fuel element cladding,
It is different according to the size of involucrum cut, position, and because of the physicochemical properties of each nucleic difference, the feature core released from cut
The amount of element is also different, and this programme utilizes a large amount of theoretical calculation and the operating experience data of combination nuclear power station, it is established that Yi Taoguan
The monitoring, diagnosing method of characteristic nuclide radioactive activity, effectively solves in clad failure character, position and primary Ioops coolant
The technology for the defects of having determined and be unable to on-line continuous monitoring in the prior art, or being unable to Accurate Diagnosis fuel element cladding breakage shape
Problem realizes during nuclear power station is run, and whether on-line continuous monitoring and diagnosis fuel element cladding are damaged and its breakage
The technique effect of character, burnup regional location etc. is conducive to the safety and the economy that significantly improve nuclear power station operation.
In order to better understand the above technical scheme, in conjunction with appended figures and specific embodiments to upper
It states technical solution to be described in detail, it should be understood that the specific features in the embodiment of the present invention and embodiment are to the application
The detailed description of technical solution, rather than to the restriction of technical scheme, in the absence of conflict, the present invention is implemented
Technical characteristic in example and embodiment can be combined with each other.
Embodiment one
During nuclear power station (such as pressurized-water reactor nuclear power plant) is run, when fuel for nuclear power plant cladding occurs damaged, core combustion
The characteristic nuclide that material fission generates, such as iodine (I), xenon (Xe) nucleic, release, migration and deposition in primary Ioops coolant, and
And it is different according to the size of involucrum cut, position, and because of the physicochemical properties of each nucleic difference, the feature released from cut
The amount of nucleic is also different.
Referring to FIG. 1, the embodiment of the present application provides a kind of fuel for nuclear power plant cladding damage monitoring method, it is used for
When fuel for nuclear power plant cladding occurs damaged, fuel element cladding breakage radical, damaged size and damaged group are monitored and diagnosed
Part burnup region, the monitoring method include step：
S1, online (i.e. during nuclear power station is run) monitoring obtain special in reactor core running state data and primary Ioops coolant
Levy the activity concentration data of nucleic；
The activity concentration data of S2, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the empirical data of the clad failure, it carries out n times loop iteration and calculates the practical diagnosis of N groups for obtaining the clad failure
Data；Wherein, the empirical data is specially in nuclear power station (being specifically as follows pressurized-water reactor nuclear power plant) operational process to described
Clad failure carries out the empirical value of the clad failure radical obtained when inspection shutdown (discontinuous) and damaged size, the usual warp
Test the empirical value that data further include breakage component burnup region；
S3, the practical diagnosis of N-1 groups obtained is calculated in the practical diagnostic data of N groups and the N-1 times loop iteration
When data tend to restrain and convergence coefficient is less than or equal to preset value (such as 0.5%, 5%), the practical diagnosis number of the N groups is determined
According to for final monitoring, diagnosing result；Wherein, the practical diagnostic data of N groups specifically by the present invention program to the involucrum
Breakage, which is monitored, diagnoses the clad failure radical obtained, the N group actual values of damaged size and breakage component burnup region.
Specifically, in step S1, the activity concentration data of characteristic nuclide pass through spy in the primary Ioops coolant
It surveys instrument detection primary Ioops system pipeline to obtain, the reactor core running state data includes reactor design parameter, fuel design
Parameter and other design parameters, respectively as shown in table 1-3：
1 reactor design parameter of table
2 fuel design parameter of table
3 other design parameters of table
Further, the loop iteration times N that the practical diagnostic data of N groups is obtained for executing step S2, depends mainly on
The proper so required loop iteration number of the selection of the empirical data of the clad failure, i.e. empirical data selection is few, choosing
Take improper so required loop iteration often.
The obtaining step of first group of practical diagnostic data is introduced first below, specifically, being followed for the first time in the step S2
Ring iterative includes sub-step：
The activity concentration data of S21, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the empirical value of the clad failure radical in the empirical data of the clad failure and damaged size, it carries out cycle for the first time and changes
In generation, calculates the first value for obtaining clad failure component burnup region；
The activity concentration data of S22, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And empirical value and the clad failure component burnup region of the clad failure size in the empirical data of the clad failure
The first value, carry out first time loop iteration calculate obtain clad failure radical the first value；
The activity concentration data of S23, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the first value of first value and the clad failure radical in the clad failure component burnup region, carry out first time cycle
Iterative calculation obtains the first value of clad failure size；
Wherein, first value in the clad failure component burnup region, the first value of the clad failure radical and described
First value of clad failure size constitutes first group of practical diagnostic data.
In specific implementation process, although being not excluded for when the selection of the empirical data is proper and only needs once to calculate just
The possibility for the practical diagnostic data that can be met the requirements, but this possibility is minimum, according to practical experience it is found that logical
In the case of often, when the preset value is set to 0.5%, the value of N can be more than 500, i.e., in practical applications, multiple loop iteration is
It is essential." loop iteration " mentioned here refers to：It is diagnosed when executing first group of reality that first time loop iteration obtains
When data and the empirical data of the clad failure do not restrain or convergence coefficient is more than the preset value, obtained based on on-line monitoring
Reactor core running state data and characteristic nuclide activity concentration data and first group of practical diagnostic data,
It carries out second of loop iteration and calculates second group of practical diagnostic data for obtaining the clad failure, and judge second group of reality
Whether border diagnostic data restrains with first group of practical diagnostic data and whether convergence coefficient is less than or equal to the preset value, according to
Such propulsion row n times loop iteration calculates, until the final practical diagnostic data of N groups that finds out is calculated with the N-1 times loop iteration
When the practical diagnostic data of N-1 groups obtained tends to restrain and convergence coefficient is less than or equal to preset value, determine that the N groups are practical
Diagnostic data is final monitoring, diagnosing result.
Specifically, the practical diagnostic data of N-1 groups obtained after carrying out the N-1 times loop iteration and calculating, including
N-1 values, the N-1 values of the clad failure radical and the clad failure size in the clad failure component burnup region
N-1 values；N-th loop iteration includes sub-step in the step S2：
The activity concentration data of S24, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the N-1 values of the clad failure radical in the practical diagnostic data of N-1 groups and damaged size, carry out n-th cycle
Iterative calculation obtains the N values in clad failure component burnup region；
The activity concentration data of S25, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And N-1 values and the clad failure component burnup area of the clad failure size in the practical diagnostic data of N-1 groups
The N values in domain carry out n-th loop iteration and calculate the N values for obtaining clad failure radical；
The activity concentration data of S26, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring,
And the N values of the N values and the clad failure radical in the clad failure component burnup region, it carries out n-th cycle and changes
In generation, calculates the N values for obtaining clad failure size；
Wherein, the N values, the N values of the clad failure radical in the clad failure component burnup region and the packet
The N values of shell breakage size constitute the practical diagnostic data of N groups.
Further, according in practical application when the breakage of nuclear power station Reactor fuel element cladding, the feature in primary Ioops coolant
Above-mentioned steps S24~S26 is specifically introduced in nucleic situation：
1) characteristic nuclide includes isotope (such as Cs- of the isotope (such as Cs-134) and the second caesium of the first caesium of caesium
137), the step S24 is specially：First described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
The ratio of the isotope of the isotope of caesium and second caesium activity concentration in primary Ioops coolant respectively, and
The N-1 values of clad failure radical and damaged size in the practical diagnostic data of N-1 groups, carry out n-th loop iteration
Calculate the N values for obtaining clad failure component burnup region.
Specifically, the calculating of the actual value for clad failure component burnup region, caesium same position when reactor core operation is utilized
The following features of element：1. the leadage coefficient that Cs-134 and Cs-137 is discharged into primary Ioops coolant is identical, therefore Cs-134 and Cs-
The ratio A of activity concentration of 137 two kinds of nucleic in coolantCs-134,m/ACs-137,mWith its nucleic burden in fuel rod
Ratio ACs-134,f/ACs-137,fIt is identical；2. ratio ACs-134,f/ACs-137,fIncrease with the intensification of fuel burn-up.Based on above two
Point, burdens of the Cs-134 and Cs-137 under the conditions of different burnups in fuel rod when can solve to obtain reactor core steady-state operation；
And reactor core carries out region loading, the basic phase of fuel burn-up in same area in the fuel management of nuclear power station nuclear power generating sets design
Closely.By the above-mentioned burnup being calculated and ACs-134,f/ACs-137,fIn the primary Ioops coolant that relation curve is obtained with measurement
ACs-134,m/ACs-137,mIt compares, the burnup value that burst slug stick occurs can be calculated by interpolation analysis, to obtain its institute
In the location information of subregion.
2) characteristic nuclide includes the isotope of the first inert gas and the first iodine, and the step S25 is specially：It is based on
Monitor the reactor core running state data obtained on-line, the physicochemical properties of the isotope of the first inert gas and the first iodine and
The N-1 values and the involucrum of burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups
The N values in breakage component burnup region carry out n-th loop iteration and calculate the N values for obtaining clad failure radical.Wherein, institute
It states the first inert gas and refers specifically to inert gas Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, the same position of first iodine
Element refers specifically to I-131, I-133.
Specifically, on the basis of considering to stain the influence of uranium, it is known that wrapped when reactor core steady-state operation reaches equilibrium state
The instantaneous value of shell breakage radical, further, in conjunction with the isotope for leaking into the first inert gas and first iodine in coolant
In the difference of the different and each nucleic physicochemical properties of the burden of reactor core, the first inertia leaked into coolant can be found out
The atomicity of the isotope of gas and first iodine, then, obtain measure obtained coolant in the first inert gas and
When the activity concentration data of the isotope of first iodine, usable least square method will pass through above-mentioned different fission product (Kr-
85m, Kr-87, Kr-88, Xe-133, Xe-135, I-131 and I-133) the clad failure radical that is calculated is fitted, into
And find out the actual value of clad failure radical.
3) characteristic nuclide includes the isotope of the second inert gas and the second iodine, and the step S26 is specially：It is based on
Monitor the reactor core running state data obtained on-line, the isotope of the second inert gas and the second iodine reactor core leakage coefficient,
The N values and the clad failure radical in the half-life period of the isotope of the second iodine and the clad failure component burnup region
N values, carry out n-th loop iteration calculate obtain clad failure size N values.Wherein, the second inert gas tool
Body refers to Xe-133, and the isotope of second iodine refers specifically to I-131 and I-133, according to nucleic such as Xe-133, I-131, I-133
Yield, physical property, the difference of half-life period, and judge that fuel rod clad is damaged using mutual ratio relation between them
Size.
Specifically, diagnosis fuel rod breakage size, is utilized each fission product atom under different clad failure dimensional conditions
It is discharged into the difference of the leadage coefficient of primary coolant loop, is based primarily upon following two points：1. second inert gas with it is described
The difference of the isotope of second iodine leadage coefficient under the conditions of identical involucrum break size：Second inert gas (such as Xe-133) exists
Leadage coefficient is bigger in the case that clad failure size is smaller, and the release process of iodine is slower, and the isotope of many iodine exists
It is entered before primary Ioops coolant by cut and has just been decayed；2. when iodine lodges in involucrum gap, different isotopes
It is had differences between half-life period：Short-life I-133 in small packet shell cut, identical burden will be than the long-life
I-131 decays are more, to reduce the amount that I-133 is discharged into primary Ioops coolant.According to above-mentioned 2 points, calculating can be passed through
Fit the release share ratio A of clad failure size h and two kinds of nucleic (Xe-133 and I-131) in coolantXe-133,c/
AI-131,cBetween release share ratio in coolant of ratio and break size h and two kinds of nucleic (I-131 and I-133)
AI-131,c/AI-133,cBetween ratio relation curve, substitute into two kinds of nucleic (Xe- in the primary Ioops coolant that actually measures
133 and I-131) activity concentration in coolant ratio AXe-133,m/AI-131,mExist with two kinds of nucleic (I-131 and I-133)
The ratio A of activity concentration in coolantI-131,m/AI-133,m, the actual value of clad failure size is obtained by interpolation calculation.
To sum up, after the present invention program is based on fuel element cladding appearance breakage, according to the size of involucrum cut, position
Difference, and because of the physicochemical properties of each nucleic difference, the amount of the characteristic nuclide released from cut is also different, using a large amount of
Theoretical calculation and the operating experience data for combining nuclear power station establish a set of utilization primary Ioops coolant characteristic nuclide radioactivity and live
The diagnostic model of degree analysis involucrum destructive shape, damaged burnup regional location, can be during nuclear power station be run, on-line continuous prison
Fuel element cladding whether damaged and damaged character, burnup regional location etc. are surveyed and diagnosed, existing monitoring method can be made up
Deficiency, and can significantly improve nuclear power station operation safety and economy.
Embodiment two
Based on same inventive concept, referring to FIG. 2, the embodiment of the present invention additionally provides a kind of fuel for nuclear power plant cladding
Damage monitoring system, for when fuel for nuclear power plant cladding occurs damaged, monitoring and diagnosing fuel element cladding breakage root
Number, damaged size and breakage component burnup region, when fuel for nuclear power plant cladding occurs damaged, what fuel fission generated
Characteristic nuclide is discharged in primary Ioops coolant, migrates and is deposited, and the monitoring system includes：
Data acquisition module 10 obtains feature core in reactor core running state data and primary Ioops coolant for monitoring on-line
The activity concentration data of element；
Practical diagnostic data computing module 20, the reactor core running state data for being obtained based on on-line monitoring and feature core
The activity concentration data of element and the empirical data of the clad failure carry out n times loop iteration and calculate described in acquisition
The practical diagnostic data of N groups of clad failure；
Monitoring, diagnosing result determining module 30, based in the practical diagnostic data of N groups with the N-1 times loop iteration
When the practical diagnostic data of N-1 groups for calculating acquisition tends to restrain and convergence coefficient is less than or equal to preset value, determine that the N groups are real
Border diagnostic data is final monitoring, diagnosing result；
Wherein, N is the integer more than or equal to 1, and the empirical data is specially to examine being monitored in the clad failure
The empirical value of the disconnected clad failure radical obtained and damaged size；The usual empirical data further includes breakage component burnup region
Empirical value.
In specific implementation process, referring to FIG. 3, practical diagnostic data computing module 20 includes：
First clad failure component burnup region calculated with actual values unit 201-1, the heap for being obtained based on on-line monitoring
Packet in the empirical data of the activity concentration data and the clad failure of core running state data and characteristic nuclide
The empirical value of shell breakage radical and damaged size carries out first time loop iteration and calculates acquisition clad failure component burnup region
First value；
First clad failure radical calculated with actual values unit 202-1, the reactor core for being obtained based on on-line monitoring run shape
Clad failure ruler in the empirical data of the activity concentration data and the clad failure of state data and characteristic nuclide
It is broken to carry out first time loop iteration calculating acquisition involucrum for first value of very little empirical value and the clad failure component burnup region
Damage the first value of radical；
First clad failure size calculated with actual values unit 203-1, the reactor core for being obtained based on on-line monitoring run shape
The first value and the institute of the activity concentration data and the clad failure component burnup region of state data and characteristic nuclide
The first value of clad failure radical is stated, the first value for obtaining clad failure size is calculated；
Wherein, first value in the clad failure component burnup region, the first value of the clad failure radical and described
First value of clad failure size constitutes first group of practical diagnostic data.
Further, referring still to Fig. 3, the N-1 groups that are obtained after carrying out the N-1 time loop iteration calculating are practical to examine
Disconnected data, including the N-1 values in the clad failure component burnup region, N-1 values of the clad failure radical and described
The N-1 values of clad failure size；Practical diagnostic data computing module 20 further includes：
N clad failure component burnups region calculated with actual values unit 201-N, the reactor core for being obtained based on on-line monitoring
The activity concentration data and the packet in the practical diagnostic data of N-1 groups of running state data and characteristic nuclide
The N-1 values of shell breakage radical and damaged size carry out n-th loop iteration and calculate acquisition clad failure component burnup region
N values；
N clad failure radical calculated with actual values unit 202-N, the reactor core operating status for being obtained based on on-line monitoring
The activity concentration data and the clad failure ruler in the practical diagnostic data of N-1 groups of data and characteristic nuclide
It is broken to carry out n-th loop iteration calculating acquisition involucrum for the N values of very little N-1 values and the clad failure component burnup region
Damage the N values of radical；
N clad failure size calculated with actual values unit 203-N, the reactor core operating status for being obtained based on on-line monitoring
N values of the activity concentration data and the clad failure component burnup region of data and characteristic nuclide and described
The N values of clad failure radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size；
Wherein, the N values, the N values of the clad failure radical in the clad failure component burnup region and the packet
The N values of shell breakage size constitute the practical diagnostic data of N groups.
Further, according in practical application when the breakage of nuclear power station Reactor fuel element cladding, the feature in primary Ioops coolant
Nucleic situation is practical to above-mentioned N clad failures component burnup region calculated with actual values unit 201-N, N clad failures radical
Value computing unit 202-N and N clad failure size calculated with actual values unit 203-N is specifically introduced：
1) characteristic nuclide includes isotope (such as Cs- of the isotope (such as Cs-134) and the second caesium of the first caesium of caesium
137), clad failure component burnup region calculated with actual values unit 201-N, is specifically used for：
The isotope of first caesium and institute described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
Stating the isotope of the second caesium, the ratio of the activity concentration in primary Ioops coolant and the N-1 groups are real respectively
It is broken to carry out n-th loop iteration calculating acquisition involucrum for the N-1 values of clad failure radical and damaged size in the diagnostic data of border
Damage the N values in component burnup region.
2) characteristic nuclide includes the isotope of the first inert gas and the first iodine, clad failure radical calculated with actual values
Unit 202-N, is specifically used for：
Based on the reactor core running state data that on-line monitoring obtains, the physics of the isotope of the first inert gas and the first iodine
The N-1 of chemical property and the burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups
The N values of value and the clad failure component burnup region carry out n-th loop iteration and calculate to obtain the of clad failure radical
N values.Wherein, first inert gas refers specifically to inert gas Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, described
The isotope of first iodine refers specifically to I-131, I-133.3) characteristic nuclide includes the same position of the second inert gas and the second iodine
Element, clad failure size calculated with actual values unit 203-N, is specifically used for：
Based on the reactor core running state data that on-line monitoring obtains, the isotope of the second inert gas and the second iodine is in reactor core
Leakage coefficient, the N values and the packet in the half-life period of the isotope of the second iodine and the clad failure component burnup region
The N values of shell breakage radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size.Wherein, described second
Inert gas refers specifically to Xe-133, and the isotope of second iodine refers specifically to I-131 and I-133, according to Xe-133, I-131, I-
The yield of 133 equal nucleic, physical property, the difference of half-life period, and judge fuel using ratio relation mutual between them
The size of stick clad failure.
As described above, above-mentioned fuel for nuclear power plant cladding damage monitoring system is for implementing above-mentioned nuclear power station combustion
Expect cladding damage monitoring method, so, one or more embodiments of the system are consistent with the implementation process of this method,
This is just no longer repeated one by one.
Embodiment three
Referring to FIG. 4, according to as described in embodiment one fuel sheath failure diagnostic model and the cooling of nuclear power plant primary Ioops
The property of radionuclide in agent, the embodiment of the present invention also proposed another fuel for nuclear power plant cladding breakage monitoring system
System, including：For being detected to the radionuclide in cvcs (RCV) pipeline in primary Ioops coolant
Data acquisition module 41, and the data processing module 42 that is connected with data acquisition module 41.Data acquisition module 41 is by detecting
Component unit 411 (the coaxial HPGe detectors of such as GEM p-types), gamma ray spectrometer 412, probe cooler 413 and 4 π lead screens bodies (figure
In be not drawn into) composition.Specifically, exploring block unit 411 includes detection pipeline and γ spectrum probes (being not drawn into figure), drop is considered
Interference of the low ambient enviroment to detection, detects pipeline and γ spectrum probes may be contained in 4 π lead screen bodies；The probe cooler
413 be specially Dewar bottle, in detection process, being cooled down to γ spectrum probes.41 specific work of data acquisition module
It is as principle：It is detected by exploring block unit 411 and obtains the gamma decay energy spectrum number that radionuclide is sent out in RCV pipelines
According to, and the gamma decay energy spectra data that the radionuclide is sent out, be sent in gamma ray spectrometer 412 (such as multiple tracks spectrum analysis instrument) into
The gamma decay energy spectra data is converted to the activity concentration of each characteristic nuclide by row spectrum unscrambling.
In specific implementation process, data processing module 42 is specifically as follows industrial computer, may be provided at separate put
Other regions of penetrating property nucleic search coverage, to reduce the risk of exposure of staff.Data processing module 42 includes：Interface and
Control unit, and the fuel element failure analytic unit that is connected with the interface and control unit, the fuel element failure
The concrete function of analytic unit determines mould with practical diagnostic data computing module 20 and monitoring, diagnosing result in above-described embodiment two
Block 30.Wherein, the interface and control unit are received by network measures obtained each spy from front end data acquisition module 41
The activity concentration of nucleic is levied, and is transmitted to the fuel element failure analytic unit of rear end, to analyze fuel
At the same time the damaged character of cladding provides a variety of type of alarms, including window display alarm, broadcasting audible alarm, shifting
Dynamic terminal alarms etc., can also synchronize and realize data transmission and printing, remind NPP Operations Personnel in time.The fuel element is broken
Analytic unit is damaged after receiving the activity concentration data of each characteristic nuclide, is incorporated into the reactor core fortune that line monitoring obtains
The empirical data of row status data and the clad failure (is pre-stored within the memory of the fuel element failure analytic unit
In) the damaged character of analysis fuel element, Synchronization Analysis fuel rod breakage ratio, cut size and the burnup area at place etc. immediately
Important information, and diagnostic result is output to man-machine terminal, while control is sent out by the interface and control unit if necessary
System/alarm signal reminds nuclear power plant to operate operations staff in time.
It should be understood by those skilled in the art that, the embodiment of the present invention can be provided as method, system or computer program
Product.Therefore, complete hardware embodiment, complete software embodiment or reality combining software and hardware aspects can be used in the present invention
Apply the form of example.Moreover, the present invention can be used in one or more wherein include computer usable program code computer
The computer program production implemented in usable storage medium (including but not limited to magnetic disk storage, CD-ROM, optical memory etc.)
The form of product.
These computer program instructions also can be loaded onto a computer or other programmable data processing device so that count
Series of operation steps are executed on calculation machine or other programmable devices to generate computer implemented processing, in computer or
The instruction executed on other programmable devices is provided for realizing in one flow of flow chart or multiple flows and/or block diagram one
The step of function of being specified in a box or multiple boxes.
Although preferred embodiments of the present invention have been described, it is created once a person skilled in the art knows basic
Property concept, then additional changes and modifications can be made to these embodiments.So it includes excellent that the following claims are intended to be interpreted as
It selects embodiment and falls into all change and modification of the scope of the invention.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and range.In this way, if these modifications and changes of the present invention belongs to the range of the claims in the present invention and its equivalent technologies
Within, then the present invention is also intended to include these modifications and variations.
Claims (12)
1. a kind of fuel for nuclear power plant cladding damage monitoring method is used for when fuel for nuclear power plant cladding occurs damaged,
Monitor and diagnose fuel element cladding breakage radical, damaged size and breakage component burnup region, which is characterized in that the monitoring
Method includes step：
S1, on-line monitoring obtain the activity concentration number of characteristic nuclide in reactor core running state data and primary Ioops coolant
According to the reactor core running state data includes reactor design parameter, fuel design parameter and other design parameters；
The activity concentration data of S2, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The empirical data of the clad failure carries out loop iteration calculating, executes first time loop iteration and obtains first group of practical diagnosis
Data, first value in the clad failure component burnup region, the first value of the clad failure radical and the clad failure
First value of size constitutes first group of practical diagnostic data；
N times loop iteration calculating is carried out, the practical diagnostic data of N groups of the clad failure, the clad failure component are obtained
The N values of the N values in burnup region, the N values of the clad failure radical and the clad failure size constitute the N groups
Practical diagnostic data；
S3, the practical diagnostic data of N groups tend to convergence and convergence coefficient be less than or equal to preset value when, determine the N
The practical diagnostic data of group is final monitoring, diagnosing as a result, the practical diagnostic data of N groups is fired specifically by the nuclear power station
Material cladding damage monitoring method the clad failure is monitored the clad failure radical that diagnosis obtains, damaged size and
The N group actual values in breakage component burnup region；
Wherein, N is the integer more than or equal to 1, and the empirical data is specially when carrying out inspection shutdown to the clad failure
The empirical value of the clad failure radical of acquisition and damaged size, the empirical data further includes the experience in breakage component burnup region
Value.
2. fuel for nuclear power plant cladding damage monitoring method as described in claim 1, which is characterized in that in the step S2
First time loop iteration includes sub-step：
The activity concentration data of S21, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The empirical value of clad failure radical and damaged size in the empirical data of the clad failure, carries out first time loop iteration meter
Calculate the first value for obtaining clad failure component burnup region；
The activity concentration data of S22, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The of the empirical value of clad failure size in the empirical data of the clad failure and the clad failure component burnup region
One value carries out first time loop iteration and calculates the first value for obtaining clad failure radical；
The activity concentration data of S23, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
First value of first value and the clad failure radical in the clad failure component burnup region carries out first time loop iteration
Calculate the first value for obtaining clad failure size.
3. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 2, which is characterized in that carrying out N-1
The practical diagnostic data of N-1 groups that the secondary loop iteration obtains after calculating, including the clad failure component burnup region
The N-1 values of N-1 values, the N-1 values and the clad failure size of the clad failure radical；N in the step S2
Secondary loop iteration includes sub-step：
The activity concentration data of S24, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The N-1 values of clad failure radical and damaged size in the practical diagnostic data of N-1 groups, carry out n-th loop iteration
Calculate the N values for obtaining clad failure component burnup region；
The activity concentration data of S25, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The N-1 values of clad failure size in the practical diagnostic data of N-1 groups and the clad failure component burnup region
N values carry out n-th loop iteration and calculate the N values for obtaining clad failure radical；
The activity concentration data of S26, the reactor core running state data and characteristic nuclide that are obtained based on on-line monitoring, and
The N values of the N values and the clad failure radical in the clad failure component burnup region carry out n-th loop iteration meter
Calculate the N values for obtaining clad failure size.
4. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, which is characterized in that the characteristic nuclide
Include the isotope of the isotope of the first caesium and the second caesium, the step S24 is specially：
The isotope of first caesium and described the described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
The isotope of the two caesiums ratio of the activity concentration in the primary Ioops coolant and N-1 groups are practical examines respectively
The N-1 values of clad failure radical and damaged size in disconnected data carry out the calculating of n-th loop iteration and obtain clad failure group
The N values in part burnup region.
5. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, which is characterized in that the characteristic nuclide
Include the isotope of the first inert gas and the first iodine, the step S25 is specially：
Based on the reactor core running state data that on-line monitoring obtains, the physical chemistry of the isotope of the first inert gas and the first iodine
The N-1 values of property and the burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups and
The N values in the clad failure component burnup region carry out n-th loop iteration and calculate the N values for obtaining clad failure radical.
6. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, which is characterized in that the characteristic nuclide
Include the isotope of the second inert gas and the second iodine, the step S26 is specially：
Based on the reactor core running state data that on-line monitoring obtains, isotope the letting out in reactor core of the second inert gas and the second iodine
Reveal coefficient, the N values and the involucrum in the half-life period of the isotope of the second iodine and the clad failure component burnup region are broken
The N values of radical are damaged, n-th loop iteration is carried out and calculates the N values for obtaining clad failure size.
7. a kind of fuel for nuclear power plant cladding damage monitoring system is used for when fuel for nuclear power plant cladding occurs damaged,
Monitor and diagnose fuel element cladding breakage radical, damaged size and breakage component burnup region, which is characterized in that the monitoring
System includes：
Data acquisition module obtains putting for characteristic nuclide in reactor core running state data and primary Ioops coolant for monitoring on-line
Penetrating property activity concentration data, the reactor core running state data include reactor design parameter, fuel design parameter and other set
Count parameter；
Practical diagnostic data computing module, for putting based on the reactor core running state data and characteristic nuclide for monitoring acquisition on-line
The empirical data of penetrating property activity concentration data and the clad failure carries out loop iteration calculating, executes cycle for the first time and changes
Generation obtains first group of practical diagnostic data, first value in the clad failure component burnup region, the clad failure radical
First value of the first value and the clad failure size constitutes first group of practical diagnostic data；
N times loop iteration calculating is carried out, the practical diagnostic data of N groups of the clad failure, the clad failure component are obtained
The N values of the N values in burnup region, the N values of the clad failure radical and the clad failure size constitute the N groups
Practical diagnostic data；
Monitoring, diagnosing result determining module, for the practical diagnostic data of N groups tend to convergence and convergence coefficient be less than etc.
When preset value, determine the practical diagnostic data of N groups be final monitoring, diagnosing as a result, the practical diagnostic data of N groups
What diagnosis obtained is monitored to the clad failure specifically by the fuel for nuclear power plant cladding damage monitoring system
The N group actual values of clad failure radical, damaged size and breakage component burnup region；
Wherein, N is the integer more than or equal to 1, and the empirical data is specially when carrying out inspection shutdown to the clad failure
The empirical value of the clad failure radical of acquisition and damaged size, the empirical data further includes the experience in breakage component burnup region
Value.
8. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 7, which is characterized in that the practical diagnosis
Data computation module includes：
First clad failure component burnup region calculated with actual values unit, the reactor core operating status for being obtained based on on-line monitoring
Clad failure radical in the empirical data of the activity concentration data and the clad failure of data and characteristic nuclide
With the empirical value of damaged size, carries out first time loop iteration and calculate the first value for obtaining clad failure component burnup region；
First clad failure radical calculated with actual values unit, the reactor core running state data for being obtained based on on-line monitoring and spy
Levy the empirical value of the activity concentration data of nucleic and the clad failure size in the empirical data of the clad failure
With first value in the clad failure component burnup region, carry out first time loop iteration and calculate to obtain the of clad failure radical
One value；
First clad failure size calculated with actual values unit, the reactor core running state data for being obtained based on on-line monitoring and spy
Levy the activity concentration data of nucleic and the first value and the clad failure in the clad failure component burnup region
First value of radical calculates the first value for obtaining clad failure size.
9. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 8, which is characterized in that carrying out N-1
The practical diagnostic data of N-1 groups that the secondary loop iteration obtains after calculating, including the clad failure component burnup region
The N-1 values of N-1 values, the N-1 values and the clad failure size of the clad failure radical；The practical diagnostic data
Computing module further includes：
N clad failure component burnups region calculated with actual values unit, the reactor core operating status for being obtained based on on-line monitoring
The activity concentration data and the clad failure root in the practical diagnostic data of N-1 groups of data and characteristic nuclide
The N-1 values of number and damaged size carry out n-th loop iteration and calculate the N values for obtaining clad failure component burnup region；
N clad failure radical calculated with actual values units, the reactor core running state data for being obtained based on on-line monitoring and spy
Levy the activity concentration data of nucleic and the N-1 of the clad failure size in the practical diagnostic data of N-1 groups
The N values of value and the clad failure component burnup region carry out n-th loop iteration and calculate to obtain the of clad failure radical
N values；
N clad failure size calculated with actual values units, the reactor core running state data for being obtained based on on-line monitoring and spy
Levy the activity concentration data of nucleic and N values and the clad failure in the clad failure component burnup region
The N values of radical carry out n-th loop iteration and calculate the N values for obtaining clad failure size.
10. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 9, which is characterized in that the feature core
The isotope of isotope and second caesium of the element comprising the first caesium, N clad failures component burnup region calculated with actual values list
Member is specifically used for：
The isotope of first caesium and described the described in when the reactor core running state data and reactor core obtained based on on-line monitoring is run
The isotope of the two caesiums ratio of the activity concentration in the primary Ioops coolant and N-1 groups are practical examines respectively
The N-1 values of clad failure radical and damaged size in disconnected data carry out the calculating of n-th loop iteration and obtain clad failure group
The N values in part burnup region.
11. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 9, which is characterized in that the feature core
Element includes the isotope of the first inert gas and the first iodine, and the N clad failures radical calculated with actual values unit is specific to use
In：
Based on the reactor core running state data that on-line monitoring obtains, the physical chemistry of the isotope of the first inert gas and the first iodine
The N-1 values of property and the burden in reactor core and the clad failure size in the practical diagnostic data of N-1 groups and
The N values in the clad failure component burnup region carry out n-th loop iteration and calculate the N values for obtaining clad failure radical.
12. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 9, which is characterized in that the feature core
Element includes the isotope of the second inert gas and the second iodine, and the N clad failures size calculated with actual values unit is specific to use
In：
Based on the reactor core running state data that on-line monitoring obtains, isotope the letting out in reactor core of the second inert gas and the second iodine
Reveal coefficient, the N values and the involucrum in the half-life period of the isotope of the second iodine and the clad failure component burnup region are broken
The N values of radical are damaged, n-th loop iteration is carried out and calculates the N values for obtaining clad failure size.
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| RU2622107C1 (en) * | 2016-05-26 | 2017-06-13 | Федеральное государственное унитарное предприятие "Научно-исследовательский технологический институт имени А.П. Александрова" | Method of inspection of the fuel collision of the shells of fuels of the worked heat-fuel assembly of transport nuclear energy installations |
| CN106531250A (en) * | 2016-12-15 | 2017-03-22 | 中广核工程有限公司 | Detecting method and system for integrity of nuclear power station fuel element cladding |
| CN109545408A (en) * | 2017-09-19 | 2019-03-29 | 无锡物讯科技有限公司 | Judgement and prediction technique based on artificial intelligence technology to nuclear power plant reactor fuel element cladding breakage |
| CN108053900B (en) * | 2017-12-14 | 2019-10-22 | 深圳中广核工程设计有限公司 | The method, apparatus and system of Radiation monitoring |
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