CN104934084A - Nuclear power plant fuel element cladding failure monitoring method and system - Google Patents
Nuclear power plant fuel element cladding failure monitoring method and system Download PDFInfo
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- CN104934084A CN104934084A CN201510204682.2A CN201510204682A CN104934084A CN 104934084 A CN104934084 A CN 104934084A CN 201510204682 A CN201510204682 A CN 201510204682A CN 104934084 A CN104934084 A CN 104934084A
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Abstract
The invention discloses a monitoring method and a monitoring system of nuclear power plant fuel element cladding failures. With prior arts, online continuous monitoring is not possible, or defects such as fuel element cladding failure shapes cannot be diagnosed accurately. With the method and the system, the technical problems are solved. The monitoring method comprises the following steps: S1, online monitoring is carried out, such that reactor core operation status data and radioactivity concentration data of a characteristic nuclide in a primary coolant are obtained; S2, N times of loop iteration calculations are carried out based on the reactor core operation status data, the radioactivity concentration data and cladding failure empirical data, such that an Nth set of actual diagnosis data of cladding failure is obtained; S3, when the convergence coefficient of the Nth set of actual diagnosis data and an (N-1)th set of actual diagnosis data obtained by the (N-1)th loop iteration calculation is smaller than or equal to a preset value, the (N-1)th set of actual diagnosis data is determined as a final monitoring diagnosis result. Therefore, online continuous monitoring and diagnosis of fuel element cladding failure existence, failure traits and fuel consumption area location are realized.
Description
Technical field
The present invention relates to fuel for nuclear power plant cladding Integrity Verification technical field, particularly relate to a kind of fuel for nuclear power plant cladding damage monitoring method and system.
Background technology
Can is responsible for the task of containing fuel pellet fission product.If can is damaged, fission product will be discharged in primary Ioops cooling medium by cut, produce potential impact to the safe operation of nuclear power plant.Be in operation and judge that whether can is damaged timely and accurately, break size and damage location have major contribution to the safe operation of nuclear power plant and economical operation.
The way of existing nuclear power plant to can breakage monitoring mainly comprises: total γ (ray) on-line monitoring method, the regular sampling method of core sampling system and sipping test system monitoring method.These methods both had its points of course, and also there is certain drawback, were described as follows:
1) for existing " total γ (ray) on-line monitoring method ", it carries out γ gross activity activity measurement in primary Ioops water, this is a kind of method that gross activity to the multiple nucleic in primary Ioops water carries out on-line continuous monitoring, if can occurs damaged, the total γ activity monitored is significantly higher.The advantage of this method can be monitored continuously the radioactivity of primary Ioops cooling medium.But, this method can not to can breakage carry out comparatively detailed on-line analysis, size and the burnup situation of fuel element failure cannot be judged, and easily activated and corrosion product interference and report by mistake.
2) for existing " the regular sampling method of core sampling system ", this kind ofly regularly samples primary Ioops cooling medium and sample carried out to the method for radioanalysis.Its advantage is comparatively careful, accurate to the analysis of sample.The shortcoming of this method cannot carry out on-line monitoring continuously, and owing to sampling and needing the regular hour to the experimental analysis of sample, be subject to the impact of sample Radionuclide decay, this method easily causes the judgement of cut not prompt enough; Add the intervention of human factor simultaneously, increase the uncertainty of result, and add nuclear power plant's collective dose and personnel surprisingly by according to risk.
3) for existing " sipping test system monitoring method ", this method is during shutdown discharging, is divided into online qualitative analysis and off-line quantitative test two kinds.Linear location sipping test be to irradiation after fuel assembly carry out damaged leak detection, after fuel assembly rises to telescopic sleeve, measure Xe-133 activity to judge whether can exists breakage by gamma detector.Off-line quantitative sipping test carries out quantitative test when being defined as damaged fuel assembly for online qualitative detection, this method utilizes the temperature improving fuel assembly surrounding fluid that fission gas pressure in fuel rod is raised, and fission gas (as Xe-133) will speed up outwards effusion so that detection.The method can be quantitative the size judging can cut.But, this method the on-line monitoring of really, must shutdown uncap after just can carry out, and very consuming time, may extend Shutdown time, the economy run nuclear power plant is very unfavorable.
Visible, existing in prior art can not on-line continuous monitoring, or can not the technical matters of the defect such as the damaged shape of Accurate Diagnosis can.
Summary of the invention
The present invention is directed to and to exist in prior art, can not on-line continuous monitor, or can not the technical matters of the defect such as the damaged shape of Accurate Diagnosis can, a kind of fuel for nuclear power plant cladding damage monitoring method and system are provided, achieve at nuclear power station run duration, proterties, burnup regional location etc. that whether on-line continuous detection and diagnosis can is damaged and damaged, can significantly improve security and the economy of nuclear power station operation.
On the one hand, embodiments provide a kind of fuel for nuclear power plant cladding damage monitoring method, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, described monitoring method comprises step:
S1, on-line monitoring obtain the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium;
S2, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical data of described clad failure, carry out the actual diagnostic data of N group that N loop iteration calculates the described clad failure of acquisition;
S3, the actual diagnostic data of described N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result;
Wherein, N be more than or equal to 1 integer, described empirical data is specially the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure.
Optionally, in described step S2, loop iteration comprises sub-step for the first time:
S21, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
S22, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
S23, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, carry out first time loop iteration and calculate the first value of acquisition clad failure size;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
Optionally, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size is comprised; In described step S2, the N time loop iteration comprises sub-step:
S24, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
S25, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
S26, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
Optionally, described characteristic nuclide comprises the isotope of the first caesium and the isotope of the second caesium, and described step S24 is specially:
The ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
Optionally, described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, and described step S25 is specially:
Based on the reactor core running state data that on-line monitoring obtains, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.
Optionally, described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, and described step S26 is specially:
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 at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value 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, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, described monitoring system comprises:
Data acquisition module, obtains the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium for on-line monitoring;
Actual diagnostic data computing module, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical data of described clad failure, carry out N loop iteration and calculate the actual diagnostic data of N group obtaining described clad failure;
Monitoring, diagnosing result determination module, for calculate at the actual diagnostic data of described N group and the N-1 time loop iteration the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result;
Wherein, N be more than or equal to 1 integer, described empirical data is specially the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure.
Optionally, described actual diagnostic data computing module comprises:
First clad failure assembly burnup region calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
First clad failure radical calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
First clad failure size calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, calculate and obtain first of clad failure size and be worth;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
Optionally, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size is comprised; Described actual diagnostic data computing module also comprises:
N clad failure assembly burnup region calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
N clad failure radical calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
N clad failure size calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
Optionally, described characteristic nuclide comprises the isotope of the first caesium and the isotope of the second caesium, described N clad failure assembly burnup region calculated with actual values unit, specifically for:
The ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
Optionally, described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, described N clad failure radical calculated with actual values unit, specifically for:
Based on the reactor core running state data that on-line monitoring obtains, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.
Optionally, described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, described N clad failure size calculated with actual values unit, specifically 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 at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size.
One or more technical schemes that the embodiment of the present invention provides, at least have following technique effect or advantage:
Due in embodiments of the present invention, when carrying out the diagnosis of fuel for nuclear power plant cladding breakage monitoring, the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium are obtained by online (namely at nuclear power station run duration), and based on the reactor core running state data of on-line monitoring acquisition and the activity concentration data of characteristic nuclide, and the empirical data of described clad failure (is specially, the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure), carry out N loop iteration and calculate the actual diagnostic data of N group obtaining described clad failure, the actual diagnostic data of described N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result, efficiently solve in prior art and can not on-line continuous monitor, or can not the technical matters of the defect such as the damaged shape of Accurate Diagnosis can, achieve at nuclear power station run duration, the technique effect of proterties, burnup regional location etc. that whether on-line continuous detection and diagnosis can is damaged and damaged, is conducive to the security and the economy that significantly improve nuclear power station operation.
Accompanying drawing explanation
In order to be illustrated more clearly in the embodiment of the present invention or technical scheme of the prior art, be briefly described to the accompanying drawing used required in embodiment or description of the prior art below, apparently, accompanying drawing in the following describes is only embodiments of the invention, for those of ordinary skill in the art, under the prerequisite not paying creative work, other accompanying drawing can also be obtained according to the accompanying drawing provided.
A kind of fuel for nuclear power plant cladding damage monitoring method process flow diagram that Fig. 1 provides for the embodiment of the present invention;
The first fuel for nuclear power plant cladding damage monitoring system structured flowchart that Fig. 2 provides for the embodiment of the present invention;
The second fuel for nuclear power plant cladding damage monitoring system structured flowchart that Fig. 3 provides for the embodiment of the present invention;
The third fuel for nuclear power plant cladding damage monitoring system structured flowchart that Fig. 4 provides for the embodiment of the present invention.
Embodiment
The embodiment of the present invention is by providing a kind of fuel for nuclear power plant cladding damage monitoring method, solve exist in prior art can not on-line continuous monitoring, or can not the technical matters of the defect such as the damaged shape of Accurate Diagnosis can, achieve at nuclear power station run duration, the technique effect of proterties, burnup regional location etc. that whether on-line continuous detection and diagnosis can is damaged and damaged.
The technical scheme of the embodiment of the present invention is for solving the problems of the technologies described above, and general thought is as follows:
Embodiments provide a kind of fuel for nuclear power plant cladding damage monitoring method, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, described monitoring method comprises step: S1, on-line monitoring obtain the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium; S2, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical data of described clad failure, carry out the actual diagnostic data of N group that N loop iteration calculates the described clad failure of acquisition; S3, the actual diagnostic data of described N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that described actual diagnostic data is final monitoring, diagnosing result; Wherein, N be more than or equal to 1 integer, described empirical data is specially the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure.
Visible, in embodiments of the present invention, theoretical and the release of fission product in PWR Nuclear Power Plant primary Ioops cooling medium with the fission reaction of nuclear fuel, migration, the mechanism of deposition is theoretical foundation, set up the mathematical model of the can breakage diagnosis based on characteristic nuclide activity analysis in primary Ioops cooling medium, concrete, after there is breakage in can, according to the size of involucrum cut, position is different, and because of the physicochemical property of each nucleic different, the amount of the characteristic nuclide discharged from cut is also different, this programme utilizes a large amount of theory calculate and the operating experience data in syncaryon power station, set up a set of about clad failure proterties, the monitoring, diagnosing method of characteristic nuclide radioactivity in position and primary Ioops cooling medium, efficiently solve in prior art and can not on-line continuous monitor, or can not the technical matters of the defect such as the damaged shape of Accurate Diagnosis can, achieve at nuclear power station run duration, the proterties whether on-line continuous detection and diagnosis can is damaged and damaged, the technique effect of burnup regional location etc., be conducive to the security and the economy that significantly improve nuclear power station operation.
In order to better understand technique scheme, below in conjunction with Figure of description and concrete embodiment, technique scheme is described in detail, the specific features being to be understood that in the embodiment of the present invention and embodiment is the detailed description to technical scheme, instead of the restriction to technical scheme, when not conflicting, the technical characteristic in the embodiment of the present invention and embodiment can combine mutually.
Embodiment one
At nuclear power station (as pressurized-water reactor nuclear power plant) run duration, when fuel for nuclear power plant cladding occurs damaged, the characteristic nuclide that fuel fission produces, as nucleic such as iodine (I), xenons (Xe), discharge in primary Ioops cooling medium, move and deposition, and different according to the size of involucrum cut, position, and because of the physicochemical property of each nucleic different, the amount of the characteristic nuclide discharged from cut is also different.
Please refer to Fig. 1, the embodiment of the present application provides a kind of fuel for nuclear power plant cladding damage monitoring method, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, described monitoring method comprises step:
S1, online (namely at nuclear power station run duration) monitoring obtain the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium;
S2, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical data of described clad failure, carry out the actual diagnostic data of N group that N loop iteration calculates the described clad failure of acquisition; Wherein, described empirical data is specially the empirical value of clad failure radical and the damaged size obtained when carrying out inspection shutdown (discontinuous) to described clad failure in nuclear power station (being specifically as follows pressurized-water reactor nuclear power plant) operational process, and usual described empirical data also comprises the empirical value in breakage component burnup region;
S3, the actual diagnostic data of described N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value (as 0.5%, 5% etc.) time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result; Wherein, the actual diagnostic data of described N group carries out the N group actual value in the clad failure radical of monitoring, diagnosing acquisition, damaged size and breakage component burnup region to described clad failure specifically by the present invention program.
Concrete, in step S1, in described primary Ioops cooling medium, the activity concentration data of characteristic nuclide are obtained by detection instrument detection primary Ioops system pipeline, described reactor core running state data comprises reactor design parameter, fuel design parameter and other design parameter, respectively as shown in table 1-3:
Table 1 reactor design parameter
Table 2 fuel design parameter
Other design parameter of table 3
Further, execution step S2 is obtained to the loop iteration times N of the actual diagnostic data of N group, depend mainly on choosing of the empirical data of described clad failure, namely to choose proper so required loop iteration number of times few for empirical data, chooses improper so required loop iteration often.
First introduce the obtaining step of first group of actual diagnostic data below, concrete, in described step S2, loop iteration comprises sub-step for the first time:
S21, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
S22, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
S23, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, carry out first time loop iteration and calculate the first value of acquisition clad failure size;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
In specific implementation process, although do not get rid of choosing proper and only needing once to calculate the possibility of the actual diagnostic data that just can be met requirement when described empirical data, but this possibility is minimum, according to practical experience, under normal conditions, when described preset value is decided to be 0.5%, the value of N can be greater than 500, namely in actual applications, repeatedly loop iteration is absolutely necessary." loop iteration " mentioned here refers to: when perform first time first group of actual diagnostic data obtaining of loop iteration and the empirical data of described clad failure does not restrain or convergence coefficient is greater than described preset value time, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and described first group of actual diagnostic data, carry out second time loop iteration and calculate the second group of actual diagnostic data obtaining described clad failure, and judge described second group of actual diagnostic data and described first group of actual diagnostic data whether is restrained and whether convergence coefficient is less than or equal to described preset value, the rest may be inferred carries out N loop iteration calculating, until finally obtain the actual diagnostic data of N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result.
Concrete, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, comprise the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size; In described step S2, the N time loop iteration comprises sub-step:
S24, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
S25, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
S26, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
Further, time damaged according to nuclear power station Reactor fuel element cladding in practical application, the characteristic nuclide situation in primary Ioops cooling medium, is specifically introduced above-mentioned steps S24 ~ S26:
1) described characteristic nuclide comprises the isotope (as Cs-134) of the first caesium of caesium and the isotope (as Cs-137) of the second caesium, described step S24 is specially: the ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
Concrete, for the calculating of the actual value in clad failure assembly burnup region, make use of the following features of cesium isotope when reactor core runs: 1. the leadage coefficient that is discharged in primary Ioops cooling medium of Cs-134 with Cs-137 is identical, therefore the ratio A of the activity concentration of Cs-134 and Cs-137 two kinds of nucleic in cooling medium
cs-134, m/ A
cs-137, mwith its nucleic burden ratio A in fuel rod
cs-134, f/ A
cs-137, fidentical; 2. ratio A
cs-134, f/ A
cs-137, fincrease along with the intensification of fuel burn-up.Based on above 2 points, the burden of Cs-134 and Cs-137 under different burnup condition in fuel rod when obtaining reactor core steady-state operation can be solved; And in the fuel management design of Nuclear Power Station group of motors, reactor core carries out region loading, and the fuel burn-up in same district is substantially close.By the above-mentioned burnup that calculates and A
cs-134, f/ A
cs-137, fa in the primary Ioops cooling medium that relation curve and measurement obtain
cs-134, m/ A
cs-137, mcompare, the burnup value that burst slug rod occurs can be calculated by interpolation analysis, thus obtain the positional information of its place subregion.
2) described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, described step S25 is specially: the reactor core running state data obtained based on on-line monitoring, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.Wherein, described first inert gas specifically refers to inert gas Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, and the isotope of described first iodine specifically refers to I-131, I-133.
Concrete, on the basis considering the impact of staiing uranium, the instantaneous value of the known clad failure radical when reactor core steady-state operation reaches equilibrium state, further, in conjunction with the difference of isotope in the burden of reactor core and the difference of each nucleic physicochemical property that leak into the first inert gas and described first iodine in cooling medium, the isotopic atomicity leaking into the first inert gas in cooling medium and described first iodine can be obtained, so, when obtaining the isotopic activity concentration data of the first inert gas and described first iodine in the cooling medium measured and obtain, can use least square method will by 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 calculates carries out matching, and then obtain the actual value of clad failure radical.
3) described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, described step S26 is specially: the reactor core running state data obtained based on on-line monitoring, the isotope of the second inert gas and the second iodine is at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size.Wherein, described second inert gas specifically refers to Xe-133, the isotope of described second iodine specifically refers to I-131 and I-133, according to generation, physical property, the difference of half life period of the nucleic such as Xe-133, I-131, I-133, and ratio relation mutual between them is utilized to judge the size of fuel rod clad breakage.
Concrete, the damaged size of diagnosis fuel rod, under make use of different clad failure dimensional conditions, each fission product atom is discharged into the difference of the leadage coefficient of primary coolant loop, mainly based on following 2 points: the 1. difference of described second inert gas and isotope leadage coefficient under identical involucrum break size condition of described second iodine: the second inert gas (as Xe-133) leadage coefficient when clad failure size is less is larger, and the dispose procedure of iodine is comparatively slow, the isotope of much iodine just decays before entering into primary Ioops cooling medium by cut; 2. when iodine lodges in involucrum gap, there are differences between different half-life isotopes: in less involucrum cut situation, short-life I-133 of identical burden will be more than long-life I-131 decay, thus decrease I-133 and be discharged into amount in primary Ioops cooling medium.According to above-mentioned 2 points, go out the release share of clad failure size h and two kind of nucleic (Xe-133 and I-131) in cooling medium by digital simulation and compare A
xe-133, c/ A
i-131, cbetween ratio, and the release share of break size h and two kind of nucleic (I-131 and I-133) in cooling medium compares A
i-131, c/ A
i-133, cbetween the relation curve of ratio, substitute into actual measurement to primary Ioops cooling medium in the ratio A of the activity concentration of two kinds of nucleic (Xe-133 and I-131) in cooling medium
xe-133, m/ A
i-131, mwith the ratio A of the activity concentration of two kinds of nucleic (I-131 and I-133) in cooling medium
i-131, m/ A
i-133, m, the actual value of clad failure size is obtained by interpolation calculation.
Generally speaking, after there is breakage based on can in the present invention program, according to the size of involucrum cut, position is different, and because of the physicochemical property of each nucleic different, the amount of the characteristic nuclide discharged from cut is also different, utilize a large amount of theory calculate and the operating experience data in syncaryon power station, establish a set of primary Ioops cooling medium characteristic nuclide radioactivity that utilizes and analyze involucrum destructive shape, the diagnostic model of damaged burnup regional location, can at nuclear power station run duration, the proterties whether on-line continuous detection and diagnosis can is damaged and damaged, burnup regional location etc., the deficiency of existing monitoring method can be made up, and security and the economy of nuclear power station operation can be significantly improved.
Embodiment two
Based on same inventive concept, please refer 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, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, when fuel for nuclear power plant cladding occurs damaged, the characteristic nuclide that fuel fission produces discharges, moves and deposits in primary Ioops cooling medium, and described monitoring system comprises:
Data acquisition module 10, obtains the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium for on-line monitoring;
Actual diagnostic data computing module 20, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical data of described clad failure, carry out N loop iteration and calculate the actual diagnostic data of N group obtaining described clad failure;
Monitoring, diagnosing result determination module 30, for calculate at the actual diagnostic data of described N group and the N-1 time loop iteration the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result;
Wherein, N be more than or equal to 1 integer, described empirical data is specially carrying out the clad failure radical of monitoring, diagnosing acquisition and the empirical value of damaged size at described clad failure; Usual described empirical data also comprises the empirical value in breakage component burnup region.
In specific implementation process, please refer to Fig. 3, actual diagnostic data computing module 20 comprises:
First clad failure assembly burnup region calculated with actual values unit 201-1, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
First clad failure radical calculated with actual values unit 202-1, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
First clad failure size calculated with actual values unit 203-1, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, calculate and obtain first of clad failure size and be worth;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
Further, still please refer to Fig. 3, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, comprise the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size; Actual diagnostic data computing module 20 also comprises:
N clad failure assembly burnup region calculated with actual values unit 201-N, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
N clad failure radical calculated with actual values unit 202-N, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
N clad failure size calculated with actual values unit 203-N, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
Further, time damaged according to nuclear power station Reactor fuel element cladding in practical application, characteristic nuclide situation in primary Ioops cooling medium, is specifically introduced above-mentioned N clad failure assembly burnup region calculated with actual values unit 201-N, N clad failure radical calculated with actual values unit 202-N and N clad failure size calculated with actual values unit 203-N:
1) described characteristic nuclide comprises the isotope (as Cs-134) of the first caesium of caesium and the isotope (as Cs-137) of the second caesium, clad failure assembly burnup region calculated with actual values unit 201-N, specifically for:
The ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
2) described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, clad failure radical calculated with actual values unit 202-N, specifically for:
Based on the reactor core running state data that on-line monitoring obtains, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.Wherein, described first inert gas specifically refers to inert gas Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, and the isotope of described first iodine specifically refers to I-131, I-133.3) described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, clad failure size calculated with actual values unit 203-N, specifically 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 at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size.Wherein, described second inert gas specifically refers to Xe-133, the isotope of described second iodine specifically refers to I-131 and I-133, according to generation, physical property, the difference of half life period of the nucleic such as Xe-133, I-131, I-133, and ratio relation mutual between them is utilized to judge the size of fuel rod clad breakage.
According to description above, above-mentioned fuel for nuclear power plant cladding damage monitoring system is for implementing above-mentioned fuel for nuclear power plant cladding damage monitoring method, so one or more embodiment of this system is consistent with the implementation process of the method, just repeat no longer one by one at this.
Embodiment three
Please refer to Fig. 4, according to the character of radioactive nuclide in the fuel sheath failure diagnostic model as described in embodiment one and nuclear power plant's primary Ioops cooling medium, the embodiment of the present invention also proposed another kind of fuel for nuclear power plant cladding damage monitoring system, comprise: for the data acquisition module 41 detected cvcs (RCV) ducted radioactive nuclide in primary Ioops cooling medium, and the data processing module 42 be connected with data acquisition module 41.Data acquisition module 41 is made up of exploring block unit 411 (as GEM P type coaxial HPGe detector), gamma ray spectrometer 412, probe refrigeratory 413 and 4 π lead shield body (not shown in FIG.).Concrete, exploring block unit 411 comprises pipelines and γ spectrum probe (not shown in FIG.), considers to reduce the interference of surrounding environment to detection, and pipelines and γ spectrum probe are all arranged in 4 π lead shield bodies; Described probe refrigeratory 413 is specially Dewar flask, in detection process, composes probe cool described γ.Data acquisition module 41 specific works principle is: detected by exploring block unit 411 and obtain the gamma decay energy spectra data that in RCV pipeline, radioactive nuclide sends, and the gamma decay energy spectra data that described radioactive nuclide is sent, be sent in gamma ray spectrometer 412 (as multiple tracks spectrometer) and carry out spectrum unscrambling, described gamma decay energy spectra data to be converted to the activity concentration of each characteristic nuclide.
In specific implementation process, data processing module 42 is specifically as follows industrial computer, can be arranged on other region away from radioactive nuclide search coverage, with being subject to according to risk of reducing a staff.Data processing module 42 comprises: interface and control module, and the fuel element failure analytic unit to be connected with control module with described interface, the concrete function of described fuel element failure analytic unit is with diagnostic data computing module 20 actual in above-described embodiment two and monitoring, diagnosing result determination module 30.Wherein, described interface and control module measure the activity concentration of each characteristic nuclide obtained from front end data acquisition module 41 by network reception, and be transferred to the described fuel element failure analytic unit of rear end, to analyze the damaged proterties of can, multiple type of alarm is meanwhile provided, comprise window display alarm, play sound warning, mobile terminal warning etc., also synchronously can realize data transmission and print, reminding NPP Operations Personnel in time.Described fuel element failure analytic unit is after receiving the activity concentration data of each characteristic nuclide, the empirical data (being pre-stored within the storer of described fuel element failure analytic unit) of the reactor core running state data obtained in conjunction with on-line monitoring and described clad failure is analyzed the damaged proterties of fuel element, the damaged ratio of Synchronization Analysis fuel rod immediately, the important informations such as the burnup district at cut size and place, and diagnostic result is outputted to man-machine terminal, send control/alerting signal by described interface and control module where necessary simultaneously, timely prompting nuclear power plant operation operations staff.
Those skilled in the art should understand, embodiments of the invention can be provided as method, system or computer program.Therefore, the present invention can adopt the form of complete hardware embodiment, completely software implementation or the embodiment in conjunction with software and hardware aspect.And the present invention can adopt in one or more form wherein including the upper computer program implemented of computer-usable storage medium (including but not limited to magnetic disk memory, CD-ROM, optical memory etc.) of computer usable program code.
These computer program instructions also can be loaded in computing machine or other programmable data processing device, make on computing machine or other programmable devices, to perform sequence of operations step to produce computer implemented process, thus the instruction performed on computing machine or other programmable devices is provided for the step realizing the function of specifying in process flow diagram flow process or multiple flow process and/or block scheme square frame or multiple square frame.
Although describe the preferred embodiments of the present invention, those skilled in the art once obtain the basic creative concept of cicada, then can make other change and amendment to these embodiments.So claims are intended to be interpreted as comprising preferred embodiment and falling into all changes and the amendment of the scope of the invention.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technologies thereof, then the present invention is also intended to comprise these change and modification.
Claims (12)
1. a fuel for nuclear power plant cladding damage monitoring method, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, it is characterized in that, described monitoring method comprises step:
S1, on-line monitoring obtain the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium;
S2, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical data of described clad failure, carry out the actual diagnostic data of N group that N loop iteration calculates the described clad failure of acquisition;
S3, the actual diagnostic data of described N group and the N-1 time loop iteration calculate the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result;
Wherein, N be more than or equal to 1 integer, described empirical data is specially the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure.
2. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 1, is characterized in that, in described step S2, loop iteration comprises sub-step for the first time:
S21, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
S22, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
S23, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, carry out first time loop iteration and calculate the first value of acquisition clad failure size;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
3. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 2, it is characterized in that, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, comprise the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size; In described step S2, the N time loop iteration comprises sub-step:
S24, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
S25, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
S26, the reactor core running state data obtained based on on-line monitoring and the activity concentration data of characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
4. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, it is characterized in that, described characteristic nuclide comprises the isotope of the first caesium and the isotope of the second caesium, and described step S24 is specially:
The ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
5. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, it is characterized in that, described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, and described step S25 is specially:
Based on the reactor core running state data that on-line monitoring obtains, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.
6. fuel for nuclear power plant cladding damage monitoring method as claimed in claim 3, it is characterized in that, described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, and described step S26 is specially:
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 at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size.
7. a fuel for nuclear power plant cladding damage monitoring system, for when fuel for nuclear power plant cladding occurs damaged, monitor and diagnose the damaged radical of can, damaged size and breakage component burnup region, it is characterized in that, described monitoring system comprises:
Data acquisition module, obtains the activity concentration data of characteristic nuclide in reactor core running state data and primary Ioops cooling medium for on-line monitoring;
Actual diagnostic data computing module, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical data of described clad failure, carry out N loop iteration and calculate the actual diagnostic data of N group obtaining described clad failure;
Monitoring, diagnosing result determination module, for calculate at the actual diagnostic data of described N group and the N-1 time loop iteration the actual diagnostic data of N-1 group obtained be tending towards restraining and convergence coefficient is less than or equal to preset value time, determine that the actual diagnostic data of described N group is final monitoring, diagnosing result;
Wherein, N be more than or equal to 1 integer, described empirical data is specially the clad failure radical of acquisition and the empirical value of damaged size when carrying out inspection shutdown to described clad failure.
8. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 7, it is characterized in that, described actual diagnostic data computing module comprises:
First clad failure assembly burnup region calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the empirical value of clad failure radical in the empirical data of described clad failure and damaged size, carry out first time loop iteration and calculate the first value obtaining clad failure assembly burnup region;
First clad failure radical calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in the empirical value of clad failure size in the empirical data of described clad failure and described clad failure assembly burnup region, carry out first time loop iteration and calculate the first value obtaining clad failure radical;
First clad failure size calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and first value in described clad failure assembly burnup region and the first value of described clad failure radical, calculate and obtain first of clad failure size and be worth;
Wherein, the first value formation first group of actual diagnostic data of first value in described clad failure assembly burnup region, the first value of described clad failure radical and described clad failure size.
9. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 8, it is characterized in that, at the actual diagnostic data of N-1 group carrying out obtaining after the N-1 time described loop iteration calculates, comprise the N-1 value in described clad failure assembly burnup region, the N-1 value of described clad failure radical and the N-1 value of described clad failure size; Described actual diagnostic data computing module also comprises:
N clad failure assembly burnup region calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region;
N clad failure radical calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical;
N clad failure size calculated with actual values unit, for the activity concentration data of the reactor core running state data that obtains based on on-line monitoring and characteristic nuclide, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size;
Wherein, the N value of the described N value in clad failure assembly burnup region, the N value of described clad failure radical and described clad failure size forms the actual diagnostic data of described N group.
10. fuel for nuclear power plant cladding damage monitoring system as claimed in claim 9, it is characterized in that, described characteristic nuclide comprises the isotope of the first caesium and the isotope of the second caesium, described N clad failure assembly burnup region calculated with actual values unit, specifically for:
The ratio of the isotope of the first caesium and the activity concentration of isotope respectively in primary Ioops cooling medium of described second caesium described in when the reactor core running state data obtained based on on-line monitoring and reactor core run, and the N-1 value of clad failure radical in the actual diagnostic data of described N-1 group and damaged size, carry out the N time loop iteration and calculate the N value obtaining clad failure assembly burnup region.
11. fuel for nuclear power plant cladding damage monitoring systems as claimed in claim 9, it is characterized in that, described characteristic nuclide comprises the isotope of the first inert gas and the first iodine, described N clad failure radical calculated with actual values unit, specifically for:
Based on the reactor core running state data that on-line monitoring obtains, the isotopic physicochemical property of the first inert gas and the first iodine and the burden in reactor core, and the N-1 value of clad failure size in the actual diagnostic data of described N-1 group and the N value in described clad failure assembly burnup region, carry out the N time loop iteration and calculate the N value obtaining clad failure radical.
12. fuel for nuclear power plant cladding damage monitoring systems as claimed in claim 9, it is characterized in that, described characteristic nuclide comprises the isotope of the second inert gas and the second iodine, described N clad failure size calculated with actual values unit, specifically 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 at the leakage coefficient of reactor core, the isotopic half life period of the second iodine, and the described N value in clad failure assembly burnup region and the N value of described clad failure radical, carry out the N time loop iteration and calculate the N value obtaining clad failure size.
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