CN108039213B - Processing method and system for load linear change test of nuclear power plant - Google Patents
Processing method and system for load linear change test of nuclear power plant Download PDFInfo
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Abstract
The invention discloses a processing method for a nuclear power plant load linear change test, which comprises the following steps: in the power reduction stage of the test, the dilution is started in advance; when the test power is reduced to the minimum power, the temperature control rod is kept at a low rod position, and the stay time of the test at the minimum power is controlled; and in the power-up stage of the test, inhibiting the lifting of the temperature control rod until the test is completed. The invention also discloses a processing system for the nuclear power plant load linear change test. The invention can make a processing scheme which is more feasible and can be operated quantitatively, and reduce the human risk.
Description
Technical Field
The invention relates to the technical field of nuclear power plants, in particular to a processing method and a processing system for a load linear change test of a nuclear power plant.
Background
The test reduces the load from 100% FP to 15% FP at the speed of 5% FP/min, and then increases the load back to 100% FP at the speed of 5% FP/min after the main parameters of the unit are stabilized, and the test cannot trigger the reactor protection action in the test process.
In the prior art, in order to meet the requirement that the load shedding is not triggered in the 100% FP load linear change test process, a method of boronizing or diluting and increasing and decreasing correction factors is adopted in the test process according to the supercooling trend and the axial power deviation change trend of a unit, so that the unit is ensured not to trigger the primary circuit supercooling load shedding or the axial power deviation exceeds the load shedding of an operation area.
Although the method can intervene in the primary circuit supercooling and axial power deviation change in the load linear change test process, the intervention effect on the primary circuit supercooling and axial power deviation has certain delay, intervention completely according to the unit supercooling trend and the axial power deviation change trend is too dependent on the skill of an operator, and misoperation is easy to occur to cause that the primary circuit supercooling load shedding or the axial power deviation exceeds the load shedding logic of the operation area. And the method for intervening according to the trend is also not systematic, can not be quantized and standardized, and can not fundamentally solve the problem that the test process is doubly restricted by primary circuit supercooling load shedding and axial power deviation exceeding the load shedding of an operation area.
Disclosure of Invention
Aiming at the problems in the prior art, the invention provides a processing method and a system for a linear load change test of a nuclear power plant, which can make a processing scheme with feasibility and quantized operation and reduce human risks.
The technical scheme provided by the invention for the technical problem is as follows:
in one aspect, the invention provides a processing method for a nuclear power plant load linear variation test, which comprises the following steps:
in the power reduction stage of the test, the dilution is started in advance; the method specifically comprises the following steps: in the power reduction stage of the test, when the load is reduced to 35% FP, large-flow dilution is started to balance xenon toxicity; the dilution flow is 20m3/h, and the dilution quantity is 8m3；
When the test power is reduced to the minimum power, the temperature control rod is kept at a low rod position, and the stay time of the test at the minimum power is controlled; when the test is reduced to the minimum power, the temperature control rod is kept at the low rod position, and the method specifically comprises the following steps: when the load is reduced to 15% FP in the test, the power of the steam turbine is reduced according to the supercooling condition of the reactor loop; after the reactor power is reduced along with the steam turbine power, increasing the reactor power to balance the steam turbine loop and the reactor loop, so that the temperature control rod keeps a low rod position; the control of the residence time of the test at the lowest power specifically comprises: when the test is reduced to the lowest power, the xenon poison is rapidly increased, and the retention time of the test at the lowest power is controlled to be 8min so as to reduce the xenon poison effect;
and in the power-up stage of the test, inhibiting the lifting of the temperature control rod until the test is completed.
Further, the increasing the reactor power specifically includes:
intervening in the position of a power control rod by increasing its correction factor to increase the reactor power.
Preferably, the steam turbine power is reduced five times, with each reduction of 10 MW.
Further, during the power-up stage of the test, the method for restraining the temperature control rod from lifting comprises the following specific steps:
in the power-up stage of the test, the reactor loop is over-cooled, the temperature control rod is lifted up rapidly, and the temperature control rod is restrained from lifting up to the top of the reactor by means of relieving over-cooling.
Further, the method for inhibiting the temperature control rod from lifting up through a supercooling relieving mode specifically comprises the following steps:
the temperature control rod lift is inhibited by increasing a correction factor of a power control rod and increasing a dilution amount, and the correction factor is decreased after the reactor loop subcooling is mitigated.
In another aspect, the present invention provides a processing system for a nuclear power plant load linear variation test, where the system is a system for implementing the processing method for the nuclear power plant load linear variation test, and the system includes:
the dilution module is used for starting dilution in advance in a power reduction stage of a test;
the control module is used for keeping the temperature control rod at a low rod position and controlling the stay time of the test at the lowest power when the test is reduced to the lowest power; and the number of the first and second groups,
and the inhibition module is used for inhibiting the lifting of the temperature control rod in the power-up stage of the test until the test is finished.
The technical scheme provided by the embodiment of the invention has the following beneficial effects:
the method is characterized in that a test process is analyzed based on historical data of a plurality of units and a control system design principle, a reactor loop supercooling and axial power deviation principle is analyzed and decoupling processing is carried out, a process control strategy of micro overheating is provided, the micro overheating state of the units and the low rod position state of a temperature control rod are maintained by diluting and compressing low power retention time in advance, supercooling in the power increasing process is relieved, the temperature control rod is prevented from being continuously lifted, decoupling of two controls is realized, the allowance of reactor loop supercooling protection and axial power deviation exceeding operation area protection is improved, the test method is more feasible and can be operated quantitatively, and human risks are reduced.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.
FIG. 1 is a schematic flow chart of a processing method for a linear variation test of a nuclear power plant load according to an embodiment of the present invention;
FIG. 2 is a graph illustrating axial power deviation variation during operation of a power control rod in a linear variation test of a nuclear power plant load according to an embodiment of the present invention;
FIG. 3 is a schematic diagram of logic for calculating a supercooling degree in a linear load variation test of a nuclear power plant according to an embodiment of the present invention;
FIG. 4 is a graph illustrating a change in a supercooling threshold of a reactor loop in a linear load change test of a nuclear power plant according to an embodiment of the present invention;
FIG. 5 is a schematic diagram of a logic for calculating a power control rod setting value in a linear variation test of a nuclear power plant load according to an embodiment of the present invention;
FIG. 6 is a temperature variation graph of a processing method for a linear variation test of a nuclear power plant load according to an embodiment of the present invention;
fig. 7 is a graph illustrating an axial power deviation variation in a processing method for a nuclear power plant load linear variation test according to an embodiment of the present invention;
fig. 8 is a schematic structural diagram of a processing system for a nuclear power plant load linear variation test according to a second embodiment of the present invention.
Detailed Description
In order to solve the technical problems that the load linear change test in the prior art cannot be quantized and standardized and has human risks and the like, the invention aims to provide a processing method of the load linear change test of a nuclear power plant, which has the core idea that: the micro-overheating state of the unit and the low rod position state of the temperature control rod are maintained by diluting and compressing the low-power retention time in advance in the power reduction stage of the test, the temperature control rod is prevented from being continuously lifted in the power increase stage of the test, the allowance of the supercooling protection and the axial power deviation of the reactor loop exceeding the protection of the operation area is improved, the test method is more feasible and quantifiable to operate, and the human factor risk is reduced.
In order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail with reference to the accompanying drawings.
Example one
The embodiment of the invention provides a processing method for a load linear change test of a nuclear power plant, and referring to fig. 1, the method comprises the following steps:
s1, in the power reduction stage of the test, beginning dilution in advance;
s2, when the test power is reduced to the lowest power, keeping the temperature control rod at a low rod position, and controlling the stay time of the test at the lowest power;
and S3, in the power-up stage of the test, inhibiting the temperature control rod from lifting upwards until the test is completed.
It should be noted that, in the embodiment, a process control strategy of micro overheating is provided after a test process is analyzed based on historical data of a plurality of units and a design principle of a control system, a supercooling and axial power deviation principle of a reactor loop is analyzed and decoupling processing is performed, that is, the processing method of the embodiment.
And analyzing the load shedding logic before the control strategy is appointed. The overcooling (C22) load shedding of the reactor loop and the axial power deviation load shedding beyond the operating zone (C21) are important logics for preventing the reactor protection action and ensuring the safety of the reactor. During the load linear variation test, the reactor loop and the steam turbine loop are unbalanced due to the xenon degree increase and the inherent characteristics of the control of the reactor and the steam turbine, and the C21/C22 load shedding logic is easy to trigger.
The load shedding logic analysis comprises axial power deviation protection logic analysis, reactor loop supercooling protection logic analysis and correction factor logic analysis.
And (3) performing axial power deviation protection logic analysis, wherein in order to protect the fuel cladding from being damaged due to overhigh temperature, a hot spot factor is strictly limited in the design of the nuclear power plant, but because the hot spot factor cannot be directly measured, an axial power deviation △ I is introduced to represent the axial unbalance condition of the reactor power.
The measurable △ I is controlled to control the hot spot factor of the unit, and the calculation formula of △ I is as follows:
△I＝AO*Pr。
wherein, PHIs upper power, PBLower power, AO is axial power offset, Pr is relative power.
When the operating point exceeds the left limit line or the right limit line, the axial power deviation exceeds the signal of the operating area C21, so that the steam turbine reduces the load at the speed of 200% Pn/min, and the reactor power also synchronously reduces because the reactor power automatically tracks the steam turbine power.
As can be seen from the formula, a greater increase in core upper power results in △ I moving to the right, and thus the factors for △ I moving to the right include xenon poisoning growth, reactor loop overcooling, temperature control rod lifting, etc., all of which occur in load linear variation tests, since the complexity of the effect of the action of the power control rods G on △ I is determined by the step-by-step action characteristics of the power control rods G, a greater effect on the upper portion of the power control rods G results in △ I moving to the right, whereas △ I moving to the left, and especially after the G1 rod groups exceed the middle point, the step-by-step effect disappears (all of the rod groups are on the upper portion of the core), and continued lifting of the power control rods G results in △ I moving to the right rapidly, as shown in FIG.
Reactor loop subcooling protection logic analysis: in the reactor-following mode, the power of the reactor loop tracks the power of the steam turbine loop, and the fixed value of the temperature of the reactor loop is determined by the power of the steam turbine loop represented by the inlet pressure of the steam turbine. When the two are deviated, the temperature control rod R is operated to adjust. When the temperature control rod R can not control the temperature deviation, the deviation is larger than the supercooling threshold value of the reactor loop, and the load dump protection of the reactor loop is triggered (C22).
The supercooling degree calculation logic diagram is shown in fig. 3, the minimum value of the average temperature of three loops of the reactor loop (primary loop), namely the minimum value of the temperature of the primary loop, is filtered, and the supercooling degree is generated by subtracting the constant value of the temperature of the primary loop from the supercooling margin formed according to the power of the steam turbine loop (secondary loop), and if the result is less than 0 ℃, a supercooling load shedding signal C22 of the reactor loop is generated. As in fig. 4, when the turbine loop power is between 43% FP and 90% FP, the subcooling threshold is 10 ℃; when the power load of the steam turbine loop is lower than 43% Pn, in order to prevent P12 from being generated, the supercooling threshold value is reduced to be 2 ℃ at least; to prevent steam quality deterioration when the load is above 90% Pn, the subcooling threshold is reduced, at a minimum of 3 ℃.
In the power-up process, because the power-up speed of the reactor loop is slightly lower than the power-up speed of the steam turbine loop, the power of the reactor loop and the power of the steam turbine loop are unbalanced, and the reactor loop is gradually overcooled. When the power is increased to 90% FP, the supercooling gradually reaches the peak value, and the supercooling threshold value is gradually reduced at the moment, so that the risk of load shedding caused by supercooling is increased greatly.
Meanwhile, in order to facilitate the fine adjustment and intervention of the rod position of the power control rod G, correction factor logic is added, so that an operator can intervene in the rod position of the power control rod G by increasing or decreasing the correction factor, the supercooling of the reactor loop can be relieved by increasing the correction factor, and △ I deterioration can be caused, wherein a logic diagram of the rod position setting value of the power control rod G is shown in FIG. 5.
By analyzing the supercooling and △ I right movement process in the linear load test process, the main difficulty of the test is that the severe supercooling of the reactor loop is caused by the xenon poison growth and the reactor tracking delay, the temperature control rod R is quickly lifted to the top of the reactor to lose the temperature regulation capacity, the supercooling of the reactor loop cannot be relieved, and simultaneously, the lifting of the temperature control rod R and the supercooling of the reactor loop can cause △ I right movement.
The countermeasures made by analyzing the main factors influencing the supercooling degree and △ I in the test process are shown in Table 1.
TABLE 1
According to the countermeasures taken for various influencing factors in table 1, a control strategy of the micro-overheating is made, namely, the processing method of the nuclear power plant load linear change test of the embodiment. The following is a detailed description of the processing method of the nuclear power plant load linear variation test provided in this embodiment.
In step S1, the starting of dilution in advance in the power reduction stage of the test specifically includes:
during the power down phase of the experiment, when the load was reduced to 35% FP, a large flow dilution was started to balance the xenon poison.
It should be noted that to ensure that dilution reaches the reactor loop quickly, the downcomer plates of the second chemical and volume control system were opened prior to the experiment. In the power reduction stage, large-flow dilution is started in advance through the opened lower discharge hole plate. In the power reduction stage, negative reactivity is introduced when the power control rod is inserted downwards, positive reactivity is introduced when dilution is performed, the technical specification does not allow the simultaneous introduction of the positive reactivity and the negative reactivity, the effect of diluting and introducing the positive reactivity needs about 5min, and the conservative consideration is that dilution is performed in advance for 4min, namely, the dilution with high flow rate is started when 35% FP is performed.
Meanwhile, in order to ensure the dilution effect and the dilution injection time, the dilution speed is set to be maximum 20m3H, dilution of 8m3。
Further, in step S2, when the test is performed to the minimum power, the maintaining the temperature control rod at the low rod position specifically includes:
when the load is reduced to 15% FP in the test, the power of the steam turbine is reduced according to the supercooling condition of the reactor loop;
and after the reactor power is reduced along with the steam turbine power, increasing the reactor power to balance the steam turbine loop and the reactor loop, so that the temperature control rod keeps a low rod position.
Further, the increasing the reactor power specifically includes:
intervening in the position of a power control rod by increasing its correction factor to increase the reactor power.
It should be noted that, in order to enhance the temperature regulating capability of the temperature control rod in the power-up stage, the power of the steam turbine should be appropriately reduced and the correction factor should be increased in the low-power stage according to the supercooling condition, so that the temperature control rod maintains the low rod position.
Preferably, the steam turbine power is reduced five times, with each reduction of 10 MW.
Further, in step S2, the controlling the time of the test staying at the lowest power specifically includes:
when the test is reduced to the lowest power, the xenon poison is rapidly increased, and the time of the test staying at the lowest power is controlled to be 10 minutes so as to reduce the xenon poison effect.
It should be noted that the low power platform has low neutron flux, weak xenon elimination effect, rapid xenon poison growth, and the retention time must be compressed as much as possible to reduce the xenon poison effect.
Further, in step S3, the inhibiting the temperature control rod from lifting in the power-up stage of the test specifically includes:
in the power-up stage of the test, the reactor loop is over-cooled, the temperature control rod is lifted up rapidly, and the temperature control rod is restrained from lifting up to the top of the reactor by means of relieving over-cooling.
Further, the method for inhibiting the temperature control rod from lifting up through a supercooling relieving mode specifically comprises the following steps:
the temperature control rod lift is inhibited by increasing a correction factor of a power control rod and increasing a dilution amount, and the correction factor is decreased after the reactor loop subcooling is mitigated.
It should be noted that lifting the temperature control rod to the top of the reactor results in the loss of temperature regulation capability, which cannot relieve the overcooling of the reactor loop, and on the other hand results in the displacement of △ I to the right, so that it is necessary to prevent the temperature control rod from lifting to the top of the reactor, and even if the temperature control rod is lifted to the top of the reactor, the time of the temperature control rod on the top of the reactor is reduced as much as possible.
Referring to FIGS. 6 and 7, the supercooling degree and △ I variation curves after the treatment method of this example are shown, it can be seen that the large flow dilution is started when the power is reduced to 35% FP, the dilution rate is 20m3/h, and the dilution amount is 8m3And the low-power retention time is 8min, the temperature control rod maintains a low rod position, wherein the minimum supercooling degree threshold value is 4 ℃, and the minimum △ I margin is 5% FP, so that the load shedding risk is basically eliminated.
The embodiment of the invention analyzes the test process based on the historical data of a plurality of sets and the design principle of a control system, analyzes the principles of loop supercooling and axial power deviation and performs decoupling treatment, provides a process control strategy of micro-overheating, maintains the micro-overheating state of the sets and the low rod position state of a temperature control rod by diluting and compressing low power residence time in advance, relieves supercooling in the power increasing process, prevents the temperature control rod from being continuously lifted, realizes the decoupling of two controls, improves the supercooling protection of a reactor loop and the exceeding of the axial power deviation beyond the protection margin of an operation area, ensures that the test method has feasibility and can be operated quantitatively, and reduces the human factor risk.
Example two
An embodiment of the present invention provides a system for implementing all processes of the processing method for the linear load change test of the nuclear power plant, and referring to fig. 8, the system includes:
the dilution module 1 is used for starting dilution in advance in a power reduction stage of a test;
the control module 2 is used for keeping the temperature control rod at a low rod position and controlling the stay time of the test at the lowest power when the test is reduced to the lowest power; and the number of the first and second groups,
and the suppression module 3 is used for suppressing the lifting of the temperature control rod in the power-up stage of the test until the test is completed.
The embodiment of the invention analyzes the test process based on the historical data of a plurality of sets and the design principle of a control system, analyzes the principles of loop supercooling and axial power deviation and performs decoupling treatment, provides a process control strategy of micro-overheating, maintains the micro-overheating state of the sets and the low rod position state of a temperature control rod by diluting and compressing low power residence time in advance, relieves supercooling in the power increasing process, prevents the temperature control rod from being continuously lifted, realizes the decoupling of two controls, improves the supercooling protection of a reactor loop and the exceeding of the axial power deviation beyond the protection margin of an operation area, ensures that the test method has feasibility and can be operated quantitatively, and reduces the human factor risk.
In conclusion, the invention provides a processing method and a system for a nuclear power plant load linear change test, which have better practical effects that a nuclear power unit has no axial power deviation control system, and the temperature control rod of an actuating mechanism of a reactor loop average temperature control system has certain limitation, so that the power-up stage of a 100% FP load linear change test is subjected to double restrictions of supercooling load shedding of the reactor loop and load shedding of the axial power deviation beyond an operating area, and the load shedding risk is large, if the micro-overheating control strategy provided by the embodiment of the invention is not adopted, the supercooling load shedding margin and the △ I load shedding margin are very low, namely the minimum supercooling degree margin is 1.6 ℃, the minimum △ I margin is 1.8% FP., and the micro-overheating control strategy provided by the embodiment of the invention is adopted to maintain the thermal balance state of a steady-state platform and carry out mass flow dilution in advance, so that the micro-overheating state and the low rod position of the temperature of the unit are maintained, the supercooling load shedding margin and the △ I supercooling load margin are 4 ℃ at the minimum, the minimum △ I, the minimum FP load margin is △ I, and the success rate of the control rod linear change test is greatly increased.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.
Claims (6)
1. A processing method for a nuclear power plant load linear change test is characterized by comprising the following steps:
in the power reduction stage of the test, the dilution is started in advance; the method specifically comprises the following steps: in the power reduction stage of the test, when the load is reduced to 35% FP, large-flow dilution is started to balance xenon toxicity; the dilution flow is 20m3H, dilution of 8m3；
When the test power is reduced to the minimum power, the temperature control rod is kept at a low rod position, and the stay time of the test at the minimum power is controlled; when the test is reduced to the minimum power, the temperature control rod is kept at the low rod position, and the method specifically comprises the following steps: when the load is reduced to 15% FP in the test, the power of the steam turbine is reduced according to the supercooling condition of the reactor loop; after the reactor power is reduced along with the steam turbine power, increasing the reactor power to balance the steam turbine loop and the reactor loop, so that the temperature control rod keeps a low rod position; the control of the residence time of the test at the lowest power specifically comprises: when the test is reduced to the lowest power, the xenon poison is rapidly increased, and the retention time of the test at the lowest power is controlled to be 8min so as to reduce the xenon poison effect;
and in the power-up stage of the test, inhibiting the lifting of the temperature control rod until the test is completed.
2. The method for processing the linear variation test of the nuclear power plant load according to claim 1, wherein the increasing the reactor power specifically includes:
intervening in the position of a power control rod by increasing its correction factor to increase the reactor power.
3. The method of handling a linear variation in nuclear power plant load test of claim 1, wherein the turbine power is reduced five times with each 10MW reduction.
4. The method for processing the linear variation test of the nuclear power plant load according to claim 1, wherein the step of inhibiting the temperature control rod from lifting in the power-up stage of the test specifically comprises:
in the power-up stage of the test, the reactor loop is over-cooled, the temperature control rod is lifted up rapidly, and the temperature control rod is restrained from lifting up to the top of the reactor by means of relieving over-cooling.
5. The method for processing the linear variation test of the nuclear power plant load according to claim 4, wherein the inhibiting the lifting of the temperature control rod by slowing down the overcooling comprises:
the temperature control rod lift is inhibited by increasing a correction factor of a power control rod and increasing a dilution amount, and the correction factor is decreased after the reactor loop subcooling is mitigated.
6. A processing system for a nuclear power plant load linear variation test, which is used for realizing the processing method for the nuclear power plant load linear variation test of any one of claims 1 to 5;
the system comprises:
the dilution module is used for starting dilution in advance in a power reduction stage of a test;
the control module is used for keeping the temperature control rod at a low rod position and controlling the stay time of the test at the lowest power when the test is reduced to the lowest power; and the number of the first and second groups,
and the inhibition module is used for inhibiting the lifting of the temperature control rod in the power-up stage of the test until the test is finished.
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| CN85106086A (en) * | 1985-08-12 | 1987-03-04 | 西屋电气公司 | The control in advance of xenon in the pressurized water reactor |
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