CN114267465A - Method for judging output abnormity of pressurized water reactor nuclear power unit - Google Patents
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Abstract
The invention discloses a method for judging the output abnormity of a nuclear power unit of a pressurized water reactor, which comprises the following steps: acquiring output tracking data of a nuclear power unit in a current fuel cycle period and output tracking data of a nuclear power unit in a historical fuel cycle period; calculating equivalent steam flow of the steam turbine, converting the equivalent steam flow into electric power under rated thermal power and converting the equivalent steam flow into electric power under 104% steam flow based on the output tracking data; according to output tracking data of the current fuel cycle period and the historical fuel cycle period, respectively taking the seawater temperature and steam parameters of a condenser as an X axis, respectively taking electric power converted to rated thermal power and electric power converted to 104% steam flow as a Y axis, and making four scatter diagrams; according to the four scatter diagrams, the time is taken as the third dimension, and the longitudinal comparison is carried out independently or jointly, so that whether the unit output is abnormal or not can be judged, and the abnormal section can be judged.
Description
Technical Field
The invention relates to the field of nuclear power engineering, in particular to a method for judging output abnormity of a nuclear power unit of a pressurized water reactor.
Background
During the daily operation of the pressurized water reactor unit, even if the operation performance of a thermodynamic system and equipment is all normal, the electric power is often changed under the influence of the change of parameters such as seawater temperature, ocean tide, core thermal power, evaporator pollution discharge flow, plant steam consumption and the like. Therefore, after the unit is subjected to refueling and overhaul or in the daily production management process, the output of the unit needs to be supervised, namely the output of the unit is tracked, whether the change of electric power is normal or not is identified, and attention is paid if the change is caused by uncontrollable factors outside the boundary of a thermodynamic system; if the output force changes caused by controllable factors outside or inside the boundary of the thermodynamic system, the reasons should be found out in time and eliminated, so that the unit operates in a healthy state to exert the generating capacity of the unit to the maximum extent.
Generally, the unit output tracking method adopted by nuclear power plant technicians is as follows: and (3) carrying out correction calculation on the actually measured electric power by using a design curve or a formula provided by a device manufacturer according to the electric power variation caused by the boundary factor deviating from the design condition to obtain the electric power corrected to the design condition (the corrected electric power for short), comparing the electric power with the design value, and if the corrected electric power is greater than the design value, considering that the unit output is normal, and if the corrected electric power is less than the design value, considering that the unit output is abnormal. However, there is a certain deviation between the design curve or formula and the actual thermal characteristics, and the correction calculation cannot accurately reflect the electric power variation caused by the deviation of the external exclusion boundary factors from the design conditions, so that the deviation between the corrected electric power and the design value cannot represent the real performance difference, thereby affecting the identification of whether the unit output variation is normal or not.
Disclosure of Invention
The invention aims to provide a method for judging the output abnormity of a nuclear power unit of a pressurized water reactor, which abandons the conventional method for correcting and calculating the actually measured electric power and provides a method for longitudinally comparing the actual thermodynamic characteristics based on the previous fuel cycle so as to accurately and efficiently distinguish the output abnormity of the nuclear power unit.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method for judging the output abnormity of a nuclear power unit of a pressurized water reactor is characterized by identifying the output abnormity condition of the nuclear power unit through the following steps:
acquiring output tracking data of a nuclear power unit in a current fuel cycle period and output tracking data of a nuclear power unit in a historical fuel cycle period;
acquiring current relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a historical fuel cycle period;
and if the electric power converted to the rated thermal power corresponding to the seawater temperature in the current relation data is smaller than the electric power converted to the rated thermal power corresponding to the same seawater temperature in the historical relation data, judging that the output of the nuclear power unit is abnormal.
Further, the output tracking data of the current fuel cycle period and the output tracking data of the historical fuel cycle period are obtained by tracking in a full-power operation state of the nuclear power unit, and the output tracking data is obtained by screening the data obtained by tracking according to one or more of the following conditions:
the thermal power of the secondary side of the steam generator and the thermal balance test system thereof is in the range of 98.5 percent FP-100 percent FP; and/or
The blowdown flow of a blowdown system of the steam generator is about 70t/h, the APG002RF cooling water flow is greater than or equal to 80t/h, and the temperature of an outlet at the cooling water side of APG002RF is higher than or equal to 170 ℃; and/or
The opening of the regulating valve of the steam trap is less than or equal to 10%.
Further, under the premise that the thermal power circulation of the pressurized water reactor nuclear power unit is decomposed into a hot end, a middle section and a cold end, the contribution of the output improvement of the cold end is calculated according to the following steps:
according to the relation data of the electric power converted to the rated thermal power and the seawater temperature, calculating the difference between the electric power currently converted to the rated thermal power and the electric power historically converted to the rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the electric power corresponding to the same steam parameter of the condenser and the electric power corresponding to the same condenser, which is converted to the rated thermal power currently, and the electric power converted to the rated thermal power historically to obtain a second converted electric power difference;
and calculating a difference value between the first and second calculated electric power difference values to serve as the contribution of output promotion of the cold end, and if the first calculated electric power difference value is smaller than the second calculated electric power difference value, judging that the output of the cold end of the nuclear power unit is abnormal.
Further, under the premise that the thermal power circulation of the pressurized water reactor nuclear power unit is decomposed into a hot end, a middle section and a cold end, the contribution of the output improvement of the hot end is calculated according to the following steps:
according to the relation data of the electric power converted to the rated thermal power and the seawater temperature, calculating the difference between the electric power currently converted to the rated thermal power and the electric power historically converted to the rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference value between the electric power corresponding to the same seawater temperature and currently converted to 104% of steam flow and the electric power converted to 104% of steam flow historically to obtain a third converted electric power difference value;
and calculating a difference value between the first and third calculated electric power difference values to serve as the contribution of output improvement of the hot end, and if the first calculated electric power difference value is smaller than the third calculated electric power difference value, judging that the output of the hot end of the nuclear power unit is abnormal.
Further, under the premise that the thermal power circulation of the pressurized water reactor nuclear power unit is decomposed into a hot end, a middle section and a cold end, the contribution of output improvement of the middle section is calculated according to the following steps:
acquiring current relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; counting the difference value between the electric power corresponding to the same condenser steam parameter and currently converted to 104% of the steam flow and the electric power corresponding to the same condenser steam parameter and historically converted to 104% of the steam flow to obtain a fourth converted electric power difference value;
and taking the fourth converted electric power difference as the contribution of output improvement of the middle section, and if the fourth converted electric power difference is smaller than 0, judging that the output of the middle section of the nuclear power unit is abnormal.
Further, the step of counting the difference between the current electric power converted to the rated thermal power and the historical electric power converted to the rated thermal power corresponding to the same seawater temperature comprises the following steps:
and calculating the average value of the difference between the current scattering point value and the historical scattering point value to obtain the statistical result of the difference between the current electric power converted to the rated thermal power and the electric power converted to the rated thermal power at the same seawater temperature.
Further, the steam parameter of the condenser is the steam temperature of the condenser or the steam pressure of the condenser.
Furthermore, the output tracking data of the historical fuel cycle period is output tracking data of a plurality of cycle periods, and the historical relation data of the electric power converted to the rated thermal power and the seawater temperature are a plurality of groups;
and if the electric power converted to the rated thermal power corresponding to the seawater temperature in the current relation data is smaller than the electric power converted to the rated thermal power corresponding to the same seawater temperature in any group of historical relation data, judging that the output of the nuclear power unit is abnormal.
On the other hand, the invention also provides a method for judging the output abnormity of the nuclear power unit of the pressurized water reactor, which is characterized in that on the premise that the thermal cycle of the nuclear power unit of the pressurized water reactor is decomposed into a hot end, a middle section and a cold end, one or more of the following four converted electric power difference values are obtained to identify the output abnormity condition of the nuclear power unit:
acquiring current relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the current electric power converted to rated thermal power and the historical electric power converted to rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the electric power corresponding to the same steam parameter of the condenser and the electric power corresponding to the same condenser, which is converted to the rated thermal power currently, and the electric power converted to the rated thermal power historically to obtain a second converted electric power difference;
acquiring current relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference value between the electric power corresponding to the same seawater temperature and currently converted to 104% of steam flow and the electric power converted to 104% of steam flow historically to obtain a third converted electric power difference value;
acquiring current relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; and counting the difference value between the electric power corresponding to the same condenser steam parameter and currently converted to 104% of the steam flow and the electric power converted to 104% of the steam flow historically to obtain a fourth converted electric power difference value.
Further, the abnormal output condition of the nuclear power unit is identified through the following conditions:
if the first calculated electric power difference value is smaller than 0, judging that the output of the nuclear power unit is abnormal; or,
if the second calculated electric power difference value is smaller than 0, judging that the output of the middle section and/or the hot end of the nuclear power unit is abnormal; or,
if the third calculated electric power difference is smaller than 0, judging that the output of the middle section and/or the cold end of the nuclear power unit is abnormal; or,
if the fourth converted electric power difference is smaller than 0, judging that the output of the middle section of the nuclear power unit is abnormal; or,
calculating respective output lifting contributions of the hot end, the middle section and the cold end according to at least three of the four converted electric power difference values, wherein if the output lifting contribution of the hot end is a negative value, the output of the hot end of the nuclear power unit is abnormal; if the output promotion contribution of the middle section is a negative value, the output of the middle section of the nuclear power unit is abnormal; and if the contribution of the output promotion of the cold end is a negative value, the output of the cold end of the nuclear power unit is abnormal.
The technical scheme provided by the invention has the following beneficial effects:
a. by means of the historical fuel circulation statistical data of the nuclear power unit, a scatter diagram can be made only after electric power conversion is carried out, and abnormal output can be identified and abnormal parts can be located through longitudinal comparison of the characteristic trends of the historical fuel circulation;
b. and a correction calculation method is not needed, so that misjudgment or missing judgment of unit output abnormity caused by deviation of a design curve or formula and the real thermal characteristics of the unit is avoided.
Drawings
In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings needed to be used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments described in the present application, and other drawings can be obtained by those skilled in the art without creative efforts.
FIG. 1 is a schematic view of scatter distribution of electric power VS seawater temperature converted to rated thermal power from historical fuel cycle statistical data of a nuclear power unit provided by an embodiment of the invention;
FIG. 2 is a schematic view of the scatter point distribution of the steam temperature of the electric power VS condenser converted from the historical fuel cycle statistical data of the nuclear power unit to the rated thermal power, provided by the embodiment of the invention;
FIG. 3 is a schematic diagram of scatter distribution of electrical power VS seawater temperature converted to 104% steam flow from historical fuel cycle statistical data of a nuclear power unit provided by an embodiment of the present invention;
FIG. 4 is a schematic view of the scatter point distribution of the steam temperature of the electric power VS condenser when the historical fuel cycle statistical data of the nuclear power unit provided by the embodiment of the invention is converted to 104% steam flow;
fig. 5 is a logic schematic diagram of a method for determining an output abnormality of a nuclear power generating unit of a pressurized water reactor according to an embodiment of the present invention.
Detailed Description
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
It should be noted that the terms "first," "second," and the like in the description and claims of the present invention and in the drawings described above are used for distinguishing between similar elements and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used is interchangeable under appropriate circumstances such that the embodiments of the invention described herein are capable of operation in sequences other than those illustrated or described herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, apparatus, article, or device that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed, but may include other steps or elements not expressly listed or inherent to such process, method, article, or device.
The conventional method for judging the output abnormity of the unit needs to use a design curve or formula, and the design curve or formula often has a certain deviation from the real thermal characteristics of the unit, so that the output abnormity of the unit is judged wrongly or not judged. The invention abandons the conventional correction calculation method and provides a method for longitudinally comparing the actual thermodynamic characteristics based on the previous fuel circulation, applies the steam turbine principle and the thermodynamic correlation theory, combines the characteristics of a nuclear power unit, exerts the linking action of three parameters, namely the thermal power of a reactor, the first-stage front steam pressure of a high-pressure cylinder and the steam parameter of a condenser, decomposes a two-loop thermodynamic system into three sections, tracks and counts data according to the output of a daily unit, performs simple electric power conversion, classifies according to the fuel circulation to manufacture a scatter diagram, and can accurately and efficiently distinguish the output abnormality of the nuclear power unit and position an abnormal section by longitudinally comparing the characteristic trends of the previous fuel circulation.
In one embodiment of the invention, a method for judging the output abnormity of a nuclear power unit of a pressurized water reactor is provided, which decomposes the thermodynamic cycle of the nuclear power pressurized water reactor unit into a hot end part, a middle section and a cold end part. The hot end comprises a system and equipment for flowing new steam, wherein the system and equipment for flowing new steam refers to a secondary side of a steam generator and a heat balance test system (KME) thereof, a steam-driven auxiliary feed water pump steam extraction pipeline (ASG), a main steam pipeline and drain pipe (VVP), a main steam bypass discharge system (GCT), a new steam extraction pipeline of a steam-water separation reheating system (GSS), a high-pressure main steam valve and regulating valve (TV & GV) of a steam turbine and a steam pipeline (commonly known as a steam guide pipe) connected with a high-pressure cylinder; the cold end comprises a condenser, a circulating water system, a vacuumizing system and a vacuum boundary; the interlude includes steam turbine body and is hydrophobic, steam-water separation reheating system and backheat heating system. After the three-section division is completed, firstly, a scatter diagram of the nuclear power unit in the past fuel circulation is made according to the combination rule of three-section-in-one (hot end + middle section + cold end), two-section-in-one (hot end + middle section, middle section + cold end) and single-section-only (middle section) by utilizing the connection effect of three parameters of the thermal power of the reactor, the first-stage front steam pressure of the high-pressure cylinder and the steam parameter of the condenser, then the scatter diagrams are longitudinally compared, and whether the output is normal or not is judged by combining one or more scatter diagrams, and the section with the abnormal output can be deduced. The relationship curves corresponding to the above-mentioned scatter diagrams are respectively a relationship curve of electric power and seawater temperature under the condition of being converted to rated thermal power, a relationship curve of electric power and condenser temperature (or condenser pressure, hereinafter, taking condenser temperature as an example) under the condition of being converted to rated thermal power, a relationship curve of electric power and seawater temperature under the condition of being converted to the same steam flow, and a relationship curve of electric power and condenser temperature (or condenser pressure, hereinafter, taking condenser temperature as an example) under the condition of being converted to the same steam flow.
Taking the F1 unit as an example, the output variation and the variation-causing part of the unit after F104 major repair and F103 major repair are analyzed. Suppose that the F1 unit completes the 4 th refurbishment and repair (abbreviated as F104 overhaul) in 9 months of 2021, and then starts the full power operation of the fifth fuel cycle. The daily output tracking data of the second, third, fourth and fifth fuel circulation periods (F1C 02, F1C03, F1C04 and F1C05) of the F1 unit are screened according to one or more of the following conditions:
1) KME (steam generator secondary side and heat balance test system) thermal power is in the range of 95% -100% FP, more preferably 98.5% -100% FP;
2) the discharge flow of APG (steam generator sewage system) is about 70t/h, the flow of APG002RF cooling water is more than or equal to 80t/h, more preferably not less than 100t/h, the outlet temperature of APG002RF cooling water side is more than or equal to 170 ℃, and more preferably not less than 176 ℃;
3) STR (plant steam shift system) fresh steam regulating valve opening is less than or equal to 10%, further preferably not more than 5%.
Based on the screened data samples, associated trends are made to obtain scatter plots shown in fig. 1 to 4, and fig. 1 to 4 are only examples and do not limit actual values and relative sizes of data.
Referring to fig. 1, the dispersion point of the electric power VS sea water temperature in the condition of conversion to rated thermal power in the F1C02 fuel cycle period, the dispersion point of the electric power VS sea water temperature in the condition of conversion to rated thermal power in the F1C03 fuel cycle period, the dispersion point of the electric power VS sea water temperature in the condition of conversion to rated thermal power in the F1C04 fuel cycle period, the dispersion point of the electric power VS sea water temperature in the condition of conversion to rated thermal power in the F1C05 fuel cycle period (i.e., at present) is denoted by □, respectively; as can be seen from fig. 1, under the conditions of rated thermal power and the same seawater temperature, the electric power of F1C05 is higher by about 13MW than that of F1C04 (at the end of life) (the calculation method is that the X-axis coordinate is determined, the Y-axis coordinates of the trend curves of F1C05 and F1C04 are checked, the two Y-axis coordinates are subtracted to obtain the single-point electric power deviation of F1C05 relative to the fuel cycle of F1C04, and for the case of multiple points, the average value of the multiple single-point electric power deviations is obtained), that is: after the F104 major repair (i.e., F1C05), the output increased by about 13MW compared to before the F104 major repair (i.e., at the end of the F1C04 life). FIG. 1 shows that the combined output of the hot end, the middle section and the cold end of the thermodynamic cycle of the nuclear power pressurized water reactor unit is improved by about 13 MW. Specifically, the electric power converted to the rated thermal power is calculated according to a formula of 'rated thermal power ÷ actually measured thermal power x electric power'.
Referring to FIG. 2, the dissipation point of the electrical power VS condenser steam temperature under the condition of the F1C02 fuel cycle period converted to the rated thermal power is denoted by O, the dissipation point of the F1C03 fuel cycle period converted to the electrical power VS condenser steam temperature under the condition of the rated thermal power is denoted by Δ, the dissipation point of the F1C04 fuel cycle period converted to the electrical power VS condenser steam temperature under the condition of the rated thermal power is denoted by Δ, and the dissipation point of the F1C05 fuel cycle period (i.e., current) converted to the electrical power VS condenser steam temperature under the condition of the rated thermal power is denoted by □, respectively; as can be seen from fig. 2, the F1C05 output is substantially equal to the F1C04 (end of life) output (output increase is 0) under the conditions of rated thermal power and the same condenser steam temperature (or equivalent back pressure). FIG. 2 represents the combined output improvement of the hot end and the middle section of the thermodynamic cycle of the nuclear power pressurized water reactor unit. As can be seen from the combination of fig. 1 and 2, the major contributor to the increase in output after F104 overhaul is the cold end, about 13MW, as compared to before F104 overhaul.
Referring to fig. 3, the dispersion point of the electric power VS sea water temperature in the condition of conversion to 104% steam flow for the F1C02 fuel cycle period, the dispersion point of the electric power VS sea water temperature in the condition of conversion to 104% steam flow for the F1C03 fuel cycle period, the dispersion point of the electric power VS sea water temperature in the condition of conversion to 104% steam flow for the F1C04 fuel cycle period, and the dispersion point of the electric power VS sea water temperature in the condition of conversion to 104% steam flow for the F1C05 fuel cycle period (i.e., present) are denoted by □, respectively; it can be seen from fig. 3 that F1C05 is increased by about 15MW (statistical method is shown above for 13 MW) over F1C04 (end of life) under the same steam flow and same seawater temperature. FIG. 3 represents the combined output improvement of the cold end and the middle section of the thermodynamic cycle of the nuclear power pressurized water reactor unit. As can be seen from fig. 1 and 3, the hot end of the F104 after overhaul brings no benefit, but produces a negative effect, resulting in an electric power loss of 2MW, compared with the hot end before overhaul of the F104. It can be seen from the simultaneous FIG. 2 that the force development in the middle section is 2MW (resulting in a substantially flat force in FIG. 2). Specifically, the equivalent flow of the steam turbine is calculated according to the front steam pressure of the first stage of the high-pressure cylinder and the new steam flow consumed by the steam-water separation reheater, and then the electric power converted to 104% of the steam flow is calculated according to a formula of 104% ÷ equivalent flow of the steam turbine x electric power.
Referring to fig. 4, the take-off point of the electric power VS condenser steam temperature under the condition of conversion to 104% steam flow for the F1C02 fuel cycle is denoted by O, the take-off point of the electric power VS condenser steam temperature under the condition of conversion to 104% steam flow for the F1C03 fuel cycle is denoted by Δ, the take-off point of the electric power VS condenser steam temperature under the condition of conversion to 104% steam flow for the F1C04 fuel cycle is denoted by Δ, and the take-off point of the electric power VS condenser steam temperature under the condition of conversion to 104% steam flow for the F1C05 fuel cycle (i.e., present) is denoted by □, respectively; as can be seen from FIG. 4, under the same steam flow and the same steam temperature (or the same backpressure) of the condenser, the F1C05 is improved by 1-2 MW compared with the F1C04 (at the end of life), or the F104 after overhaul exceeds the F103 after overhaul by 1-2 MW. FIG. 4 represents the improvement in output of a single section of the middle section of a thermodynamic cycle of a nuclear power pressurized water reactor plant.
In summary, the major contribution to the increase in output after F104 overhaul (F1C05 fuel cycle, i.e. current) is from the cold end, about 13MW, compared to after F103 overhaul (F1C04 fuel cycle); the secondary contributor is the middle segment, about 1-2 MW; but the hot end generates negative effect to offset 2 MW; and after the three sections are overlapped, the output force is finally improved by 13 MW.
The above is only the F1C05 fuel cycle compared to the F1C04 fuel cycle, which is the same as the F1C03 fuel cycle, and the F1C02 fuel cycle. As can be seen from fig. 1 to 4, compared with F1C02 and F1C04, F1C03 has a relatively optimal unit operating state, and compared with F1C03, F1C05 has a 7MW electric power at the cold end, a 3MW loss at the hot end, and a 1MW loss at the middle section, and after the three sections are stacked, the total output is increased by 3 MW.
In summary, the method utilizes the linking effect of three parameters, namely the thermal power of the reactor, the first-stage front steam pressure of the high-pressure cylinder and the steam parameter of the condenser, and obtains the output tracking data of the nuclear power unit in the current fuel cycle period and the output tracking data of the nuclear power unit in the historical fuel cycle period by referring to fig. 5; calculating equivalent steam flow of the steam turbine, converting the equivalent steam flow into electric power under rated thermal power and converting the equivalent steam flow into electric power under 104% steam flow based on the output tracking data; according to output tracking data of the current fuel cycle period and the historical fuel cycle period, respectively taking the seawater temperature and steam parameters of a condenser as an X axis, respectively taking electric power converted to rated thermal power and electric power converted to 104% steam flow as a Y axis, and making four scatter diagrams; according to the four scatter diagrams, the time is taken as the third dimension, and the longitudinal comparison is carried out independently or jointly, so that whether the unit output is abnormal or not can be judged, and the abnormal section can be judged. According to the combination rule that three sections are combined (hot end + interlude + cold end), two sections are combined (hot end + interlude, interlude + cold end), single section is only (interlude), with the help of nuclear power unit fuel circulation statistical data all the time, only need do the electric power after converting, can do the scatter diagram, promptly: converting a relation curve of electric power to seawater temperature under the condition of rated thermal power, converting a relation curve of electric power to condenser temperature (or condenser pressure) under the condition of rated thermal power, converting a relation curve of electric power to seawater temperature under the condition of equal steam flow, converting a relation curve of electric power to condenser temperature (or condenser pressure) under the condition of equal steam flow, longitudinally comparing scatter diagrams, judging whether the output is normal or not by applying thermodynamic knowledge according to the four scatter diagrams, and deducing sections with abnormal output, such as:
as shown in fig. 1, obtaining current relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the current electric power converted to rated thermal power and the historical electric power converted to rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
as shown in fig. 2, obtaining current relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the electric power corresponding to the same steam parameter of the condenser and the electric power corresponding to the same condenser, which is converted to the rated thermal power currently, and the electric power converted to the rated thermal power historically to obtain a second converted electric power difference;
as shown in fig. 3, according to the output tracking data of the nuclear power unit in the current fuel cycle period, obtaining the current relation data of the electric power converted to 104% steam flow and the seawater temperature; acquiring historical relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference value between the electric power corresponding to the same seawater temperature and currently converted to 104% of steam flow and the electric power converted to 104% of steam flow historically to obtain a third converted electric power difference value;
as shown in fig. 4, obtaining current relation data of electric power converted to steam flow of 104% and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; counting the difference value between the electric power corresponding to the same condenser steam parameter and currently converted to 104% of the steam flow and the electric power corresponding to the same condenser steam parameter and historically converted to 104% of the steam flow to obtain a fourth converted electric power difference value;
the abnormal output condition of the nuclear power unit is identified through the following conditions:
if the first calculated electric power difference value is smaller than 0, judging that the output of the nuclear power unit is abnormal; or,
if the second calculated electric power difference value is smaller than 0, judging that the output of the middle section and/or the hot end of the nuclear power unit is abnormal; or,
if the third calculated electric power difference is smaller than 0, judging that the output of the middle section and/or the cold end of the nuclear power unit is abnormal; or,
if the fourth converted electric power difference is smaller than 0, judging that the output of the middle section of the nuclear power unit is abnormal; or,
calculating respective output lifting contributions of the hot end, the middle section and the cold end according to at least three of the four converted electric power difference values, wherein if the output lifting contribution of the hot end is a negative value, the output of the hot end of the nuclear power unit is abnormal; if the output promotion contribution of the middle section is a negative value, the output of the middle section of the nuclear power unit is abnormal; and if the contribution of the output promotion of the cold end is a negative value, the output of the cold end of the nuclear power unit is abnormal.
It is noted that, herein, relational terms such as first and second, and the like may be used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Also, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
The foregoing is directed to embodiments of the present application and it is noted that numerous modifications and adaptations may be made by those skilled in the art without departing from the principles of the present application and are intended to be within the scope of the present application.
Claims (10)
1. The method for judging the output abnormity of the nuclear power unit of the pressurized water reactor is characterized by comprising the following steps of:
acquiring output tracking data of a nuclear power unit in a current fuel cycle period and output tracking data of a nuclear power unit in a historical fuel cycle period;
acquiring current relation data of electric power converted to rated thermal power and seawater temperature based on output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a historical fuel cycle period;
and if the electric power converted to the rated thermal power corresponding to the seawater temperature in the current relation data is smaller than the electric power converted to the rated thermal power corresponding to the same seawater temperature in the historical relation data, judging that the output of the nuclear power unit is abnormal.
2. The method for judging the output abnormity of the nuclear power unit of the pressurized water reactor according to claim 1, wherein the output tracking data of the current fuel cycle period and the output tracking data of the historical fuel cycle period are obtained by tracking in a full-power running state of the nuclear power unit, and the output tracking data is obtained by screening the data obtained by tracking according to one or more of the following conditions:
the thermal power of the secondary side of the steam generator and the thermal balance test system thereof is in the range of 98.5 percent FP-100 percent FP; and/or
The blow-down flow of a blow-down system of the steam generator is about 70t/h, the cooling water flow of a blow-down heat energy recovery heat exchanger (APG002RF) is more than or equal to 80t/h, and the outlet temperature of the APG002RF on the cooling water side is more than or equal to 170 ℃; and/or
The opening degree of the new steam regulating valve of the plant steam conversion system is less than or equal to 10 percent.
3. The method for judging the output abnormity of the pressurized water reactor nuclear power unit according to claim 1, wherein the output lifting contribution of the cold end is calculated according to the following steps on the premise that the thermal cycle of the pressurized water reactor nuclear power unit is decomposed into the hot end, the middle section and the cold end:
according to the relation data of the electric power converted to the rated thermal power and the seawater temperature, calculating the difference between the electric power currently converted to the rated thermal power and the electric power historically converted to the rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the electric power corresponding to the same steam parameter of the condenser and the electric power corresponding to the same condenser, which is converted to the rated thermal power currently, and the electric power converted to the rated thermal power historically to obtain a second converted electric power difference;
and calculating a difference value between the first and second calculated electric power difference values to serve as the contribution of output promotion of the cold end, and if the first calculated electric power difference value is smaller than the second calculated electric power difference value, judging that the output of the cold end of the nuclear power unit is abnormal.
4. The method for judging the output abnormity of the pressurized water reactor nuclear power unit according to claim 1, wherein the output lifting contribution of the hot end is calculated according to the following steps on the premise that the pressurized water reactor nuclear power unit is decomposed into the hot end, the middle section and the cold end in a thermal cycle:
according to the relation data of the electric power converted to the rated thermal power and the seawater temperature, calculating the difference between the electric power currently converted to the rated thermal power and the electric power historically converted to the rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference value between the electric power corresponding to the same seawater temperature and currently converted to 104% of steam flow and the electric power converted to 104% of steam flow historically to obtain a third converted electric power difference value;
and calculating a difference value between the first and third calculated electric power difference values to serve as the contribution of output improvement of the hot end, and if the first calculated electric power difference value is smaller than the third calculated electric power difference value, judging that the output of the hot end of the nuclear power unit is abnormal.
5. The method for judging the output abnormity of the pressurized water reactor nuclear power unit according to claim 1, wherein the output lifting contribution of the middle section is calculated according to the following steps on the premise that the pressurized water reactor nuclear power unit is decomposed into the hot end, the middle section and the cold end in a thermal cycle manner:
acquiring current relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; counting the difference value between the electric power corresponding to the same condenser steam parameter and currently converted to 104% of the steam flow and the electric power corresponding to the same condenser steam parameter and historically converted to 104% of the steam flow to obtain a fourth converted electric power difference value;
and taking the fourth converted electric power difference as the contribution of output improvement of the middle section, and if the fourth converted electric power difference is smaller than 0, judging that the output of the middle section of the nuclear power unit is abnormal.
6. The method for judging the output abnormity of the nuclear power generating set of the pressurized water reactor as claimed in claim 3 or 4, wherein the step of counting the difference between the electric power converted to rated thermal power currently and the electric power converted to rated thermal power historically, which correspond to the same seawater temperature, comprises the following steps:
and calculating the average value of the difference between the current scattering point value and the historical scattering point value to obtain the statistical result of the difference between the current electric power converted to the rated thermal power and the electric power converted to the rated thermal power at the same seawater temperature.
7. The method for judging the output abnormity of the pressurized water reactor nuclear power generator according to claim 3 or 5, wherein the steam parameter of the condenser is the steam pressure of the condenser or the steam temperature of the condenser.
8. The method for judging the output abnormity of the nuclear power unit of the pressurized water reactor according to any one of claims 1 to 5, wherein the output tracking data of the historical fuel cycle period are output tracking data of a plurality of cycle periods, and the historical relation data of electric power converted to rated thermal power and seawater temperature are a plurality of groups;
and if the electric power converted to the rated thermal power corresponding to the seawater temperature in the current relation data is smaller than the electric power converted to the rated thermal power corresponding to the same seawater temperature in any group of historical relation data, judging that the output of the nuclear power unit is abnormal.
9. The method for judging the output abnormity of the nuclear power unit of the pressurized water reactor is characterized in that on the premise that the thermal cycle of the nuclear power unit of the pressurized water reactor is decomposed into a hot end, a middle section and a cold end, one or more of the following four converted electric power difference values are obtained to identify the output abnormity condition of the nuclear power unit:
acquiring current relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and seawater temperature according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the current electric power converted to rated thermal power and the historical electric power converted to rated thermal power corresponding to the same seawater temperature to obtain a first converted electric power difference;
acquiring current relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to rated thermal power and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference between the electric power corresponding to the same steam parameter of the condenser and the electric power corresponding to the same condenser, which is converted to the rated thermal power currently, and the electric power converted to the rated thermal power historically to obtain a second converted electric power difference;
acquiring current relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power and seawater temperature converted to 104% steam flow according to output tracking data of a nuclear power unit in a historical fuel cycle period; calculating the difference value between the electric power corresponding to the same seawater temperature and currently converted to 104% of steam flow and the electric power converted to 104% of steam flow historically to obtain a third converted electric power difference value;
acquiring current relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a current fuel cycle period; acquiring historical relation data of electric power converted to 104% steam flow and steam parameters of a condenser according to output tracking data of a nuclear power unit in a historical fuel cycle period; and counting the difference value between the electric power corresponding to the same condenser steam parameter and currently converted to 104% of the steam flow and the electric power converted to 104% of the steam flow historically to obtain a fourth converted electric power difference value.
10. The method for judging the output abnormity of the nuclear power unit of the pressurized water reactor according to claim 9, wherein the output abnormity condition of the nuclear power unit is identified through the following conditions:
if the first calculated electric power difference value is smaller than 0, judging that the output of the nuclear power unit is abnormal; or,
if the second calculated electric power difference value is smaller than 0, judging that the output of the middle section and/or the hot end of the nuclear power unit is abnormal; or,
if the third calculated electric power difference is smaller than 0, judging that the output of the middle section and/or the cold end of the nuclear power unit is abnormal; or,
if the fourth converted electric power difference is smaller than 0, judging that the output of the middle section of the nuclear power unit is abnormal; or,
calculating respective output lifting contributions of the hot end, the middle section and the cold end according to at least three of the four converted electric power difference values, wherein if the output lifting contribution of the hot end is a negative value, the output of the hot end of the nuclear power unit is abnormal; if the output promotion contribution of the middle section is a negative value, the output of the middle section of the nuclear power unit is abnormal; and if the contribution of the output promotion of the cold end is a negative value, the output of the cold end of the nuclear power unit is abnormal.
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