CN116798664A - Critical control method, control device, equipment and storage medium for nuclear reactor - Google Patents
Critical control method, control device, equipment and storage medium for nuclear reactor Download PDFInfo
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- 238000000034 method Methods 0.000 title claims abstract description 69
- 238000010790 dilution Methods 0.000 claims abstract description 172
- 239000012895 dilution Substances 0.000 claims abstract description 172
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 144
- 229910052796 boron Inorganic materials 0.000 claims abstract description 144
- 238000007865 diluting Methods 0.000 claims abstract description 66
- 238000003780 insertion Methods 0.000 claims abstract description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 76
- 238000013213 extrapolation Methods 0.000 claims description 38
- 238000004364 calculation method Methods 0.000 claims description 34
- 238000004590 computer program Methods 0.000 claims description 16
- 230000008569 process Effects 0.000 claims description 14
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- 230000008439 repair process Effects 0.000 claims description 4
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- 230000037431 insertion Effects 0.000 description 5
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- 230000009286 beneficial effect Effects 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
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- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/36—Control circuits
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Abstract
The embodiment of the invention discloses a critical control method, a control device, equipment and a storage medium of a nuclear reactor. The critical control method of the nuclear reactor comprises the following steps: in the first dilution stage, diluting the reactor core to dilute the boron concentration of the primary loop to a first target concentration, wherein the first target concentration is larger than a boron concentration estimated value in a critical state; in the rod lifting stage, lifting control rods in various control rod groups from the full-insertion position to a target rod position; in the second dilution stage, when the boron concentration of the primary loop meets the preset concentration condition, the reactor core is diluted until the reactor meets the critical state condition. According to the technical scheme, the first critical operation after finishing the refueling during the overhaul of the nuclear power station is controlled, so that the reactor can safely, stably and rapidly enter a critical state, the integral time of the overhaul of the nuclear power station is saved, and the operation economy of the nuclear power station is improved.
Description
Technical Field
The embodiment of the invention relates to the technical field of nuclear power, in particular to a critical control method, a critical control device, critical control equipment and critical control storage medium of a nuclear reactor.
Background
Reactor startup refers to the process of starting the reactor from a subcritical state to a critical state, and achieving a self-sustaining chain fission reaction. The criticality is the most fundamental problem of reactor physics and can be generally divided into the first criticality (i.e., the criticality after refueling) and the recovery criticality. The purpose of the critical test is to safely and smoothly reach the critical state of the reactor and to determine the conditions in this state, i.e., critical conditions. The rod position and boron concentration at the critical time are referred to as critical rod position and critical boron concentration.
The start-up methods differ from one reactor to another, depending on the type of reactor. However, the principles of reactor criticality are the same, with the basic approach being commonality: the critical operation is carried out by determining a subcritical state in advance according to the requirements of operation technical specifications and taking the critical degree as a basis according to the existing critical experimental experience value, the past critical experimental value or the theoretical value which is credible. Pressurized water reactor nuclear power plants are designed to bring the reactor to a critical level by the extraction of control rods and dilution of boron concentration, with the nuclear fission materials, moderators, structural materials and absorption materials (control rods and chemical poisons) already established.
The nuclear power station needs to be subjected to material changing overhaul after each cycle is finished, the overhaul time is usually 20-30 days, the length of the overhaul time is related to the economical efficiency of the power station, the reactor reaching critical test belongs to an overhaul critical path, and the test time length is directly related to the overhaul time of the power station. At present, the problem that the time consumed for the first critical operation after the refueling during the overhaul is longer affects the economy of the nuclear power station, and the safety and the stability of the critical operation are required to be improved.
Disclosure of Invention
The embodiment of the invention provides a critical control method, a control device, equipment and a storage medium for a nuclear reactor, which are used for controlling the first critical operation after finishing the refueling during the overhaul of the nuclear power plant, and are beneficial to ensuring that the reactor safely, stably and rapidly enters a critical state, saving the integral time of the overhaul of the nuclear power plant and improving the operating economy of the nuclear power plant.
According to an aspect of the present invention, there is provided a critical control method of a nuclear reactor adapted to control a first critical operation after finishing a refueling during a major repair of a nuclear power plant, the critical control method of the nuclear reactor comprising:
in a first dilution stage, diluting the reactor core to dilute the boron concentration of a loop to a first target concentration, wherein the first target concentration is greater than a critical state boron concentration predicted value;
In the rod lifting stage, lifting control rods in various control rod groups from the full-insertion position to a target rod position;
in the second dilution stage, when the boron concentration of the primary loop meets a preset concentration condition, diluting the reactor core until the reactor meets a critical state condition;
wherein the lifting stage is located between the first dilution stage and the second dilution stage.
Optionally, diluting the reactor core to dilute the boron concentration of the first circuit to a first target concentration, comprising:
obtaining a boron concentration predicted value in a critical state and an initial boron concentration of a loop;
calculating a first target water quantity required for diluting the boron concentration of the primary circuit to a first target concentration according to the initial boron concentration and the critical state boron concentration predicted value;
diluting the reactor core with the first target water quantity;
wherein, the first target water quantity is calculated as:
wherein V is 0 Indicating the first target water quantity, CB 0 Indicating the initial boron concentration, CB ECC A predicted value of boron concentration representing the critical state.
Optionally, the critical control method of the nuclear reactor further comprises:
in the first dilution stage, carrying out neutron countdown rate ratio extrapolation calculation by taking a first set time length as a period;
Determining whether the reactor reaches the critical state within the next first set period of time, and a dilution total water amount extrapolated calculated value and a boron concentration extrapolated calculated value required by the reactor to reach the critical state, based on a result of the neutron count down ratio extrapolated calculation;
and monitoring the critical process of the reactor according to whether the reactor reaches the critical state in the next first set time period, and the extrapolated calculated value of the total dilution water quantity and the extrapolated calculated value of the boron concentration.
Optionally, the critical control method of the nuclear reactor further comprises:
stopping diluting the reactor core when determining that the reactor will reach the critical state in the next first set time period based on the result of the neutron countdown rate ratio extrapolation calculation;
in the first dilution stage, when the difference value between the current boron concentration of the first loop and the first target concentration is smaller than a preset difference value based on the result of the neutron countdown rate ratio extrapolation calculation, stopping diluting the reactor core;
and in the first dilution stage, stopping diluting the reactor core when the current measured value of the boron concentration of the first loop is smaller than or equal to the first target concentration.
Optionally, the boron concentration of the first circuit meets a preset concentration condition, including:
the boron concentration of the primary loop is greater than a second target concentration, which is greater than the threshold state boron concentration estimate and less than the first target concentration.
Optionally, the critical control method of the nuclear reactor further comprises:
recording the actual dilution water quantity adopted by the first dilution stage for diluting the reactor core;
diluting the reactor core until the reactor meets critical state conditions, comprising:
calculating the total dilution water amount required for diluting the boron concentration of the first circuit to the estimated boron concentration value of the critical state according to the initial boron concentration of the first circuit and the estimated boron concentration value of the critical state;
determining the difference between the total dilution water amount and the actual dilution water amount as the residual dilution water amount required for diluting the boron concentration of the primary circuit to the boron concentration estimated value in the critical state;
and diluting the reactor core by adopting the residual dilution water amount until the reactor meets the critical state condition.
Optionally, in the first time interval of the second dilution stage and the first dilution stage, diluting the reactor core at a first dilution rate, and performing neutron countdown ratio extrapolation calculation with a first set duration as a period;
Diluting the reactor core at a second dilution rate in a second time interval of the second dilution stage, and performing neutron countdown rate ratio extrapolation calculation with a second set duration as a period;
wherein the first dilution rate is greater than the second dilution rate, and the second set duration is less than the first set duration; the first time interval is a time interval in which the total water injected into the reactor core in the second dilution stage is more than half of the residual dilution water, and the neutron countdown ratio is more than 0.5; the second time interval is a time interval in which the total water injected into the reactor core in the second dilution stage is less than or equal to half of the remaining dilution water amount, and/or a time interval in which a neutron countdown ratio is less than or equal to 0.5.
According to another aspect of the present invention, there is provided a critical control apparatus for a nuclear reactor adapted to control a first critical operation after completion of refueling during a major repair of the nuclear reactor, the critical control apparatus comprising:
the first dilution control module is used for diluting the reactor core in a first dilution stage so as to dilute the boron concentration of the primary loop to a first target concentration, wherein the first target concentration is larger than a boron concentration estimated value in a critical state;
The rod lifting control module is used for lifting control rods in various control rod groups from the full-insertion position to a target rod position in a rod lifting stage;
the second dilution control module is used for diluting the reactor core until the reactor meets the critical state condition when the boron concentration of the primary loop meets the preset concentration condition in the second dilution stage;
wherein the lifting stage is located between the first dilution stage and the second dilution stage.
According to another aspect of the present invention, there is provided an electronic apparatus including:
at least one processor; and
a memory communicatively coupled to the at least one processor; wherein,,
the memory stores a computer program executable by the at least one processor to enable the at least one processor to perform the critical control method of a nuclear reactor according to any of the embodiments of the present invention.
According to another aspect of the present invention, there is provided a computer readable storage medium storing computer instructions for causing a processor to execute a critical control method of a nuclear reactor according to any of the embodiments of the present invention.
According to the critical control method, the control device, the equipment and the storage medium of the nuclear reactor, the critical control method, the control device and the storage medium of the nuclear reactor are used for diluting the reactor core in a first dilution stage so as to dilute the boron concentration of a loop to a first target concentration, in a rod lifting stage, control rods in various control rod groups are lifted to the target rod positions from the full insertion positions, in a second dilution stage, when the boron concentration of the loop meets the preset concentration condition, the reactor core is diluted until the reactor meets the critical state condition, the first critical operation after finishing the refueling during the overhaul of the nuclear power plant is controlled, the reactor core is diluted in stages, the safety and the stability of the reactor entering the critical state are improved, the rod lifting stage is arranged between the first dilution stage and the second dilution stage, the whole critical process is not required after the rod lifting operation is approved, the speed of the reactor entering the critical state is improved, and the whole time of the overhaul of the nuclear power plant is saved, and the economical efficiency of the operation of the nuclear power plant is improved.
It should be understood that the description in this section is not intended to identify key or critical features of the embodiments of the invention or to delineate the scope of the invention. Other features of the present invention will become apparent from the description that follows.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required for the description of the embodiments will be briefly described below, and it is apparent that the drawings in the following description are only some embodiments of the present invention, and other drawings may be obtained according to these drawings without inventive effort for a person skilled in the art.
FIG. 1 is a flow chart of a method for critical control of a nuclear reactor according to an embodiment of the present invention;
FIG. 2 is a flow chart of another method for critical control of a nuclear reactor according to an embodiment of the present invention;
FIG. 3 is a schematic illustration of a neutron count down ratio extrapolation graph according to an embodiment of the present invention;
FIG. 4 is a flow chart of another method for critical control of a nuclear reactor according to an embodiment of the present invention;
FIG. 5 is a schematic view of a critical control apparatus for a nuclear reactor according to an embodiment of the present invention;
fig. 6 is a schematic structural diagram of an electronic device according to an embodiment of the present invention.
Detailed Description
In order that those skilled in the art will better understand the present invention, a technical solution in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in which it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
It should be noted that the terms "first," "second," and the like in the description and the claims of the present invention and the above figures are used for distinguishing between similar objects and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used may be interchanged where appropriate such that the embodiments of the invention described herein may be implemented in sequences other than those illustrated or otherwise 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, system, article, or apparatus 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 apparatus.
Fig. 1 is a flow chart of a critical control method of a nuclear reactor according to an embodiment of the present invention, where the method may be performed by a critical control device of the nuclear reactor, which may be implemented in hardware and/or software, and the critical control device of the nuclear reactor may be configured in an electronic device. Referring to fig. 1, the method specifically includes the following steps:
S110, in a first dilution stage, diluting the reactor core to dilute the boron concentration of the primary loop to a first target concentration, wherein the first target concentration is larger than a critical state boron concentration predicted value.
Specifically, the first target concentration is less than the initial boron concentration of the primary circuit and greater than the threshold state boron concentration estimate. The estimated value of the boron concentration in the critical state refers to an estimated value of the boron concentration reaching the critical first time after finishing the refueling during the overhaul period of the nuclear power station, for example, the estimated critical boron concentration of the control rod in the full lifting state, namely, the estimated critical state (Estimate Critical Condition, ECC) boron concentration, and the estimated value can be obtained through analysis and calculation by nuclear design software.
And S120, in the rod lifting stage, lifting the control rods in various control rod groups from the full-insertion position to the target rod position.
S130, in the second dilution stage, when the boron concentration of the primary loop meets the preset concentration condition, the reactor core is diluted until the reactor meets the critical state condition.
Wherein the lifting rod stage is positioned between the first dilution stage and the second dilution stage. The target rod positions may be set according to actual requirements, in one embodiment, the target rod positions are reactor tops, so that each control rod is lifted from the full insertion position to the reactor tops before the second dilution stage. Because the rod lifting operation needs to be carried out after approval, the rod lifting stage is arranged between the first dilution stage and the second dilution stage, and the first dilution stage can be preferentially carried out before the rod lifting stage.
The preset concentration condition can be set according to actual requirements. After the rod lifting stage is finished, a second dilution stage is carried out, whether the current boron concentration of a loop meets the preset concentration condition is judged, and if the current boron concentration of the loop meets the preset concentration condition, the reactor core is diluted again until the reactor meets the critical state condition. The reactor core is diluted in the first dilution stage and the second dilution stage respectively, so that the safety and stability of the reactor entering the critical state are improved.
In summary, in the technical scheme of the embodiment of the invention, in the first dilution stage, the reactor core is diluted to dilute the boron concentration of a loop to the first target concentration, in the rod lifting stage, the control rods in various control rod groups are lifted to the target rod positions from the full insertion positions, in the second dilution stage, when the boron concentration of the loop meets the preset concentration condition, the reactor core is diluted until the reactor meets the critical condition, the first critical operation after finishing the refueling during the overhaul of the nuclear power plant is controlled, the reactor core is diluted by stages, the safety and the stability of the reactor entering the critical state are improved, the rod lifting stage is arranged between the first dilution stage and the second dilution stage, the whole critical process is not required to be carried out after the rod lifting operation is approved, and the speed of the reactor entering the critical state is improved, so that the integral time of the overhaul of the nuclear power plant is saved, and the economical efficiency of the operation of the nuclear power plant is improved.
On the basis of the above embodiments, the present embodiment optimizes a critical control method of a nuclear reactor. FIG. 2 is a flow chart of another method for critical control of a nuclear reactor according to an embodiment of the present invention. Referring to fig. 2, the method specifically includes the steps of:
s210, in a first dilution stage, obtaining a boron concentration estimated value in a critical state and an initial boron concentration of a loop.
Wherein an initial sampled boron concentration of the reactor coolant system (Reactor Coolant System, RCS), i.e. an initial boron concentration of the primary loop, of the unit is obtained from the nuclear power plant prior to performing the critical operation.
S220, calculating a first target water quantity required for diluting the boron concentration of the primary circuit to the first target concentration according to the initial boron concentration and the boron concentration estimated value of the critical state.
Wherein the first target concentration may be expressed as CB ECC +C1，CB ECC The predicted boron concentration value for the critical state is 100ppm < C1 < 200ppm. Alternatively, in one embodiment, c1=150 ppm, i.e. the first target concentration is CB ECC +150ppm. Accordingly, the first target water amount is calculated as:
wherein V is 0 Indicating a first target water quantity, CB 0 Indicating the initial boron concentration.
S230, diluting the reactor core by adopting the first target water quantity.
Optionally, the critical control method of the nuclear reactor further comprises:
in the first dilution stage, carrying out neutron countdown rate ratio extrapolation calculation by taking the first set duration as a period; determining whether the reactor reaches a critical state within a next first set period of time based on a result of the neutron count-down rate ratio extrapolation calculation, and a dilution total water amount extrapolation calculation value and a boron concentration extrapolation calculation value required for the reactor to reach the critical state; and monitoring the critical process of the reactor according to whether the reactor reaches the critical state within the next first set time period, and the extrapolated calculated value of the total dilution water quantity and the extrapolated calculated value of the boron concentration.
The size of the first set duration can be set according to requirements. For example, the first set period of time is 10 minutes, and in the first dilution stage, an extrapolation of the neutron count down ratio (Inverse Count Rate Ratio, ICRR) is performed every 10 minutes to determine whether the reactor reaches a critical state in the next time interval (i.e., the time interval corresponding to the first set period of time). In the dilution process, the measured neutron countdown rate and the boron concentration of a loop are acquired every first set time interval, and the latest two measuring points are utilized for linear extrapolation to determine a total dilution water extrapolated calculated value and a boron concentration extrapolated calculated value required by the reactor to reach a critical state, so that safety monitoring is carried out on the critical process of the reactor according to the total dilution water extrapolated calculated value and the boron concentration extrapolated calculated value, for example, an alarm can be given when the fact that the total dilution water quantity of the reactor is greater than or equal to the total dilution water extrapolated calculated value is monitored, and an alarm is given when the current boron concentration of the loop is greater than or equal to the boron concentration extrapolated calculated value.
Optionally, the critical control method of the nuclear reactor further comprises:
stopping diluting the reactor core when determining that the reactor will reach a critical state within a next first set period of time based on the result of the neutron count-down rate ratio extrapolation calculation; in the first dilution stage, when the difference value between the current boron concentration of the loop and the first target concentration is smaller than a preset difference value based on the result of neutron countdown rate ratio extrapolation calculation, stopping diluting the reactor core; in the first dilution stage, dilution of the reactor core is stopped when the current boron concentration measurement of the primary loop is less than or equal to the first target concentration.
Specifically, after the first dilution stage begins to dilute the reactor core:
if the result of the neutron count-down ratio extrapolation calculation is based on that the reactor is detected to reach a critical state within the next first set time period, the dilution of the reactor core is stopped, and the continuous dilution operation is forbidden before the cause is found out; if the current boron concentration measurement of a circuit is less than or equal to the first target concentration, e.g., less than or equal to CB ECC +150ppm, stopping diluting the reactor core; calculating the boron concentration of a loop based on the neutron countdown rate ratio extrapolation, if the difference between the boron concentration of the loop and the first target concentration is smaller than the preset difference, namely the boron concentration of the loop is about to reach CB ECC +150ppm, the dilution of the reactor core is stopped.
After the dilution of the reactor core is stopped, the actual dilution water amount employed to dilute the reactor core is recorded.
The principle of neutron count down rate ratio extrapolation calculation is described below:
the neutron countdown ratio may be expressed as 1/M, and 1/M may be defined as:
1M＝N 0 N i ；
wherein N is 0 Represents the reference neutron count rate, N i Representing the correspondence at different rod positions, different boron concentrations, different amounts of dilution water or different timesCore neutron count rate. The background counting rate of the reactor core at the first critical time is small and can be ignored, so that the influence of the background counting rate is not considered.
Before starting critical operation, determining current reference neutron count rate N 0 In the subsequent operation, each time positive reactivity is added to the core, the reference neutron count rate N is used 0 Divided by the current latest core neutron count rate N i To calculate 1/M. Therefore, the value of 1/M is close to 1 in the initial state, and N is the reason when the core is close to the critical state i Tends to be infinite and is far greater than the reference neutron count rate N 0 The value of 1/M tends to 0, the countdown rate curve proceeds toward the direction approaching the abscissa, and the experimenter can judge whether the reactor approaches the critical or not according to the countdown rate curve, and the final critical state is predicted through neutron countdown rate ratio extrapolation calculation.
FIG. 3 is a schematic diagram of a neutron countdown rate ratio extrapolation curve provided by an embodiment of the invention, wherein the abscissa is the rod position of a control rod or the dilution water amount of a reactor core, and the ordinate is the neutron countdown rate ratio 1/M. Referring to FIG. 3, illustratively, when the control rod is raised to rod position h1, the corresponding neutron count down ratio is N, according to the critical operating protocol 0 /N 1 When the control rod is lifted to the rod position h2, the corresponding neutron countdown rate ratio is N 0 /N 2 . The two points corresponding to the rod positions h1 and h2 can be connected into a straight line, and the intersection point of the straight line and the abscissa is the extrapolated rod position hx of the reactor in the critical state. The extrapolation calculation mode adopts the principle of similar triangles, and the specific calculation mode is as follows:
where a=h2-h 1 and x=hx-h 2. From the above formula:
thus, the extrapolated rod position of the reactor in the critical state can be calculated:
when the abscissa shown in fig. 3 is the rod position, the extrapolated rod position of the reactor in the critical state can be calculated by adopting the extrapolation calculation method. Alternatively, the abscissa shown in fig. 3 may be the amount of dilution water injected into the reactor core during the critical process/the core boron concentration, so that the total amount of dilution water required for the reactor to be in the critical state (i.e., the above extrapolated calculated amount of dilution total water)/the core boron concentration in the critical state (i.e., the above extrapolated calculated amount of boron concentration) is calculated.
S240, in the rod lifting stage, lifting the control rods in various control rod groups from the full-insertion position to the target rod position.
In this embodiment, an AP1000 type advanced third generation nuclear power unit may be used, and the reactivity control feature is that the reactor is designed with 69 groups of control rods, which are divided into 3 groups of control rod groups, namely, a shutdown rod group (including control rods SD1 to SD 4), a control rod group (control rod M2, control rod M1, control rod MA to control rod MD), and an axial offset control rod group (AO rod). The control rods MA-MD in the control rod group are gray rods, 24 tungsten rods are used as absorber materials, and the reactivity value is far smaller than that of other control rod groups.
Table 1 shows the rod positions of the control rods in the shutdown rod group at different status points. The control rods SD1 to SD4 in the shutdown rod group are lifted from the full insertion position to the target rod position according to the status points shown in the following table. In this embodiment, the target rod position may be the reactor roof. And after the counting rate of the selected nuclear detection channel is stable, performing neutron countdown rate ratio extrapolation monitoring to judge whether the reactor can reach a critical value at the next state point.
TABLE 1
| State point | SD1 | SD2 | SD3 | SD4 |
| 1 | 0 | 0 | 0 | 0 |
| 2 | 132 | 0 | 0 | 0 |
| 3 | 264 | 0 | 0 | 0 |
| 4 | 264 | 132 | 0 | 0 |
| 5 | 264 | 264 | 0 | 0 |
| 6 | 264 | 264 | 132 | 0 |
| 7 | 264 | 264 | 264 | 0 |
| 8 | 264 | 264 | 264 | 132 |
| 9 | 264 | 264 | 264 | 264 |
Table 2 shows the rod positions of the control rods in the control rod group and the axial offset control rod group at different state points. Control rod M2, control rod M1, control rods MA through MD, and AO rods were pulled up from the full insert position to the target rod position according to the status points shown in the following table. In this embodiment, the target rod position may be the reactor roof. And after the counting rate of the selected nuclear detection channel is stable, performing neutron countdown rate ratio extrapolation monitoring to judge whether the reactor can reach a critical value at the next state point.
TABLE 2
| State point | AO | M2 | M1 | MA | MB | MC | MD |
| 1 | 0 | 0 | 0 | 0 | 0 | 0 | 0 |
| 2 | 132 | 0 | 0 | 0 | 0 | 0 | 0 |
| 3 | 264 | 0 | 0 | 0 | 0 | 0 | 0 |
| 4 | 264 | 176 | 0 | 0 | 0 | 0 | 0 |
| 5 | 264 | 264 | 88 | 0 | 0 | 0 | 0 |
| 6 | 264 | 264 | 176 | 0 | 0 | 0 | 0 |
| 7 | 264 | 264 | 264 | 88 | 0 | 0 | 0 |
| 8 | 264 | 264 | 264 | 176 | 0 | 0 | 0 |
| 9 | 264 | 264 | 264 | 264 | 88 | 0 | 0 |
| 10 | 264 | 264 | 264 | 264 | 176 | 0 | 0 |
| 11 | 264 | 264 | 264 | 264 | 264 | 88 | 0 |
| 12 | 264 | 264 | 264 | 264 | 264 | 176 | 0 |
| 13 | 264 | 264 | 264 | 264 | 264 | 264 | 88 |
| 14 | 264 | 264 | 264 | 264 | 264 | 264 | 176 |
| 15 | 264 | 264 | 264 | 264 | 264 | 264 | 264 |
S250, in the second dilution stage, judging whether the boron concentration of the primary circuit meets the preset concentration condition.
Optionally, the boron concentration of the first circuit satisfies a preset concentration condition, including: the boron concentration of the loop is greater than a second target concentration, which is greater than the threshold boron concentration estimate and less than the first target concentration.
Wherein the second target concentration may be expressed as CB ECC +C2, 50ppm < C1 < 150ppm. Alternatively, in one embodiment, c2=100 ppm, i.e. the second target concentration is CB ECC +100ppm。
Illustratively, in the second dilution stage, the boron concentration of the first circuit is sampled to determine whether the first circuit meets the preset concentration condition, if the boron concentration of the first circuit is greater than CB ECC +100ppm, it can be determined that the boron concentration of the primary circuit satisfies the preset concentration condition, otherwise it does not.
S260, calculating the total dilution water amount required for diluting the boron concentration of the loop to the estimated boron concentration of the critical state according to the initial boron concentration of the loop and the estimated boron concentration of the critical state.
Specifically, the total dilution water amount V required to dilute the boron concentration of the primary circuit to the estimated value of the boron concentration in the critical state can be calculated according to the following formula Total (S) ：
Optionally, the critical control method of the nuclear reactor further comprises: recording the actual dilution water volume V adopted by the first dilution stage for diluting the reactor core 00 。
S270, determining the difference between the total dilution water amount and the actual dilution water amount as the residual dilution water amount required for diluting the boron concentration of the primary circuit to the boron concentration estimated value of the critical state.
The residual dilution water quantity V required for diluting the boron concentration of the primary circuit to the estimated value of the boron concentration in the critical state 1 It can be calculated as: v (V) 1 ＝V Total (S) -V 00 。
S280, diluting the reactor core by adopting the residual dilution water amount until the reactor meets the critical state condition.
Optionally, in a first time interval of the second dilution stage and the first dilution stage, diluting the reactor core at a first dilution rate, and performing neutron countdown rate ratio extrapolation calculation with a first set duration as a period; and diluting the reactor core at a second dilution rate in a second time interval of the second dilution stage, and performing neutron countdown rate ratio extrapolation calculation with a second set duration as a period.
The first dilution rate is greater than the second dilution rate, and the second set duration is less than the first set duration; the first time interval is a time interval in which the total water injected into the reactor core in the second dilution stage is more than half of the residual dilution water, and the neutron countdown ratio is more than 0.5; the second time interval is a time interval in which the total amount of water injected into the reactor core in the second dilution stage is less than or equal to half of the amount of dilution water remaining, and/or a time interval in which the neutron countdown ratio is less than or equal to 0.5.
Exemplary, the first dilution rate is 22.7m 3 And/h, the second dilution rate was 7.6m 3 A value of/h or less. The first set time period is 10 minutes, and the second set time period is 5 minutes. In the first dilution stage, at 22.7m 3 And (3) diluting the reactor core at a high flow rate by the dilution rate of/h, and simultaneously, performing neutron countdown ratio extrapolation calculation once every 10 minutes to judge whether the reactor reaches a critical state in the next time interval (namely, the time interval corresponding to the first set duration). In the second dilution stage, first at 22.7m 3 Diluting the reactor core at a dilution rate of/h at a low flow rate when the total water injected into the reactor core is less than or equal to 1/V 1 When the ratio of the ratio to the total sum is 1/M is less than or equal to 0.5, the following adjustment is carried out: at 7.6m 3 And diluting the reactor core at a high flow rate at a dilution rate of/h or lower, and performing neutron countdown ratio extrapolation calculation at intervals of 5 minutes to judge whether the reactor reaches a critical state in the next time interval (namely, the time interval corresponding to the second set duration).
Alternatively, critical state conditions of the reactor include, but are not limited to, any of the following: a steady start rate of about 0.15dpm was shown on either off-stack detector power scale channel, an indication of +35pcm reactivity was present on the reactivity meter, and the SR count rate trend showed a significant exponential increase. When the critical condition is satisfied, the dilution of the reactor core is stopped.
According to the technical scheme, the first critical reaching operation after finishing the refueling during the overhaul of the nuclear power station is controlled, the reactor core is diluted in stages, so that the safety and stability of the reactor entering a critical state can be improved, the rod lifting stage is arranged between the first dilution stage and the second dilution stage, the whole critical reaching process is not required after the rod lifting operation is approved, the speed of the reactor entering the critical state can be improved, and therefore the integral time of the overhaul of the nuclear power station is saved, and the operating economy of the nuclear power station is improved.
On the basis of the above embodiments, the present embodiment optimizes a critical control method of a nuclear reactor. Fig. 4 is a flow chart of another method for critical control of a nuclear reactor according to an embodiment of the present invention. Referring to fig. 4, the method specifically includes the steps of:
s310, obtaining a boron concentration predicted value in a critical state and an initial boron concentration of a loop.
S320, calculating a first target water quantity required for diluting the boron concentration of the primary circuit to the first target concentration according to the initial boron concentration and the boron concentration estimated value of the critical state.
S330, diluting the reactor core by a first target water quantity in a large flow.
And S340, lifting the control rods in the various control rod groups from the full-insertion position to the top of the pile.
S350, calculating the residual dilution water amount required for diluting the boron concentration of the primary circuit to the boron concentration estimated value of the critical state.
S360, diluting the reactor core at a large flow rate by half of the residual dilution water quantity, and diluting the reactor core at a small flow rate by the residual dilution water quantity.
And S370, stopping dilution and declaring that the reactor reaches the critical state when the reactor meets the critical state condition.
According to the technical scheme, the first critical reaching operation after finishing the refueling during the overhaul of the nuclear power station is controlled, the reactor core is diluted in stages, so that the safety and stability of the reactor entering a critical state can be improved, the rod lifting stage is arranged between the first dilution stage and the second dilution stage, the whole critical reaching process is not required after the rod lifting operation is approved, the speed of the reactor entering the critical state can be improved, and therefore the integral time of the overhaul of the nuclear power station is saved, and the operating economy of the nuclear power station is improved.
The embodiment of the invention also provides a critical control device of the nuclear reactor, which is suitable for controlling the first critical operation after finishing the refueling during the overhaul of the nuclear power station. Fig. 5 is a schematic structural view of a critical control apparatus of a nuclear reactor according to an embodiment of the present invention. Referring to fig. 5, the apparatus includes: a first dilution control module 410, a lifter control module 420, and a second dilution control module 430, wherein:
The first dilution control module 410 is configured to dilute the reactor core during a first dilution stage to dilute the boron concentration of the first circuit to a first target concentration, where the first target concentration is greater than the threshold boron concentration estimated value;
the rod lifting control module 420 is used for lifting control rods in various control rod groups from the full insertion position to a target rod position in a rod lifting stage;
the second dilution control module 430 is configured to dilute the reactor core until the reactor meets the critical state condition when the boron concentration of the primary loop meets the preset concentration condition in the second dilution stage;
wherein the lifting rod stage is positioned between the first dilution stage and the second dilution stage.
The critical control device for a nuclear reactor provided by the embodiment of the invention can execute the critical control method for a nuclear reactor provided by any embodiment of the invention, and has corresponding functional modules and beneficial effects of the execution method, and is not repeated here.
In addition to the above embodiments, optionally diluting the reactor core to dilute the boron concentration of the first circuit to a first target concentration includes:
obtaining a boron concentration predicted value in a critical state and an initial boron concentration of a loop;
And calculating a first target water quantity required for diluting the boron concentration of the first loop to the first target concentration according to the initial boron concentration and the boron concentration predicted value of the critical state.
Optionally, the critical control device of the nuclear reactor further comprises:
the first calculation module is used for carrying out neutron countdown rate ratio extrapolation calculation by taking the first set duration as a period in the first dilution stage;
the critical determining module is used for determining whether the reactor reaches a critical state in the next first set time period based on the result of the neutron countdown rate ratio extrapolation calculation, and a dilution total water extrapolation calculated value and a boron concentration extrapolation calculated value required by the reactor reaching the critical state;
and the monitoring module is used for monitoring the critical process of the reactor according to whether the reactor reaches the critical state in the next first set time length, the extrapolated calculated value of the total dilution water quantity and the extrapolated calculated value of the boron concentration.
Optionally, the critical control device of the nuclear reactor further comprises:
the first dilution control unit is used for stopping diluting the reactor core when determining that the reactor will reach a critical state in the next first set duration based on the result of the neutron countdown rate ratio extrapolation calculation;
The second dilution control unit is used for stopping diluting the reactor core when the difference value between the current boron concentration of the first loop and the first target concentration is smaller than a preset difference value based on the result of the neutron countdown ratio extrapolation calculation in the first dilution stage;
and the third dilution control unit is used for stopping diluting the reactor core when the current measured value of the boron concentration of the primary circuit is smaller than or equal to the first target concentration in the first dilution stage.
Optionally, the critical control device of the nuclear reactor is further configured to: recording the actual dilution water quantity adopted by the first dilution stage for diluting the reactor core; accordingly, diluting the reactor core until the reactor meets the critical state condition, comprising:
calculating the total dilution water amount required for diluting the boron concentration of the loop to the estimated boron concentration in the critical state according to the initial boron concentration of the loop and the estimated boron concentration in the critical state;
determining the difference between the total dilution water amount and the actual dilution water amount as the residual dilution water amount required for diluting the boron concentration of the primary circuit to the boron concentration predicted value of the critical state;
and diluting the reactor core by adopting the residual dilution water amount until the reactor meets the critical state condition.
Fig. 6 is a schematic structural diagram of an electronic device according to an embodiment of the present invention. Electronic devices are intended to represent various forms of digital computers, such as laptops, desktops, workstations, personal digital assistants, servers, blade servers, mainframes, and other appropriate computers. Electronic equipment may also represent various forms of mobile devices, such as personal digital processing, cellular telephones, smartphones, wearable devices (e.g., helmets, glasses, watches, etc.), and other similar computing devices. The components shown herein, their connections and relationships, and their functions, are meant to be exemplary only, and are not meant to limit implementations of the inventions described and/or claimed herein.
As shown in fig. 6, the electronic device 10 includes at least one processor 11, and a memory, such as a Read Only Memory (ROM) 12, a Random Access Memory (RAM) 13, etc., communicatively connected to the at least one processor 11, in which the memory stores a computer program executable by the at least one processor, and the processor 11 may perform various appropriate actions and processes according to the computer program stored in the Read Only Memory (ROM) 12 or the computer program loaded from the storage unit 18 into the Random Access Memory (RAM) 13. In the RAM 13, various programs and data required for the operation of the electronic device 10 may also be stored. The processor 11, the ROM 12 and the RAM 13 are connected to each other via a bus 14. An input/output (I/O) interface 15 is also connected to bus 14.
Various components in the electronic device 10 are connected to the I/O interface 15, including: an input unit 16 such as a keyboard, a mouse, etc.; an output unit 17 such as various types of displays, speakers, and the like; a storage unit 18 such as a magnetic disk, an optical disk, or the like; and a communication unit 19 such as a network card, modem, wireless communication transceiver, etc. The communication unit 19 allows the electronic device 10 to exchange information/data with other devices via a computer network, such as the internet, and/or various telecommunication networks.
The processor 11 may be a variety of general and/or special purpose processing components having processing and computing capabilities. Some examples of processor 11 include, but are not limited to, a Central Processing Unit (CPU), a Graphics Processing Unit (GPU), various specialized Artificial Intelligence (AI) computing chips, various processors running machine learning model algorithms, digital Signal Processors (DSPs), and any suitable processor, controller, microcontroller, etc. The processor 11 performs the various methods and processes described above, such as critical control methods for nuclear reactors.
In some embodiments, the critical control method of a nuclear reactor may be implemented as a computer program tangibly embodied on a computer-readable storage medium, such as the storage unit 18. In some embodiments, part or all of the computer program may be loaded and/or installed onto the electronic device 10 via the ROM 12 and/or the communication unit 19. When the computer program is loaded into RAM 13 and executed by processor 11, one or more steps of the critical control method of a nuclear reactor described above may be performed. Alternatively, in other embodiments, the processor 11 may be configured to perform the critical control method of the nuclear reactor in any other suitable manner (e.g., by means of firmware).
Various implementations of the systems and techniques described here above may be implemented in digital electronic circuitry, integrated circuit systems, field Programmable Gate Arrays (FPGAs), application Specific Integrated Circuits (ASICs), application Specific Standard Products (ASSPs), systems On Chip (SOCs), load programmable logic devices (CPLDs), computer hardware, firmware, software, and/or combinations thereof. These various embodiments may include: implemented in one or more computer programs, the one or more computer programs may be executed and/or interpreted on a programmable system including at least one programmable processor, which may be a special purpose or general-purpose programmable processor, that may receive data and instructions from, and transmit data and instructions to, a storage system, at least one input device, and at least one output device.
A computer program for carrying out methods of the present invention may be written in any combination of one or more programming languages. These computer programs may be provided to a processor of a general purpose computer, special purpose computer, or other programmable data processing apparatus, such that the computer programs, when executed by the processor, cause the functions/acts specified in the flowchart and/or block diagram block or blocks to be implemented. The computer program may execute entirely on the machine, partly on the machine, as a stand-alone software package, partly on the machine and partly on a remote machine or entirely on the remote machine or server.
In the context of the present invention, a computer-readable storage medium may be a tangible medium that can contain, or store a computer program for use by or in connection with an instruction execution system, apparatus, or device. The computer readable storage medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any suitable combination of the foregoing. Alternatively, the computer readable storage medium may be a machine readable signal medium. More specific examples of a machine-readable storage medium would include an electrical connection based on one or more wires, a portable computer diskette, a hard disk, a Random Access Memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disc read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.
To provide for interaction with a user, the systems and techniques described here can be implemented on an electronic device having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to a user; and a keyboard and a pointing device (e.g., a mouse or a trackball) through which a user can provide input to the electronic device. Other kinds of devices may also be used to provide for interaction with a user; for example, feedback provided to the user may be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user may be received in any form, including acoustic input, speech input, or tactile input.
The systems and techniques described here can be implemented in a computing system that includes a background component (e.g., as a data server), or that includes a middleware component (e.g., an application server), or that includes a front-end component (e.g., a user computer having a graphical user interface or a web browser through which a user can interact with an implementation of the systems and techniques described here), or any combination of such background, middleware, or front-end components. The components of the system can be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: local Area Networks (LANs), wide Area Networks (WANs), blockchain networks, and the internet.
The computing system may include clients and servers. The client and server are typically remote from each other and typically interact through a communication network. The relationship of client and server arises by virtue of computer programs running on the respective computers and having a client-server relationship to each other. The server can be a cloud server, also called a cloud computing server or a cloud host, and is a host product in a cloud computing service system, so that the defects of high management difficulty and weak service expansibility in the traditional physical hosts and VPS service are overcome.
It should be appreciated that various forms of the flows shown above may be used to reorder, add, or delete steps. For example, the steps described in the present invention may be performed in parallel, sequentially, or in a different order, so long as the desired results of the technical solution of the present invention are achieved, and the present invention is not limited herein.
The above embodiments do not limit the scope of the present invention. It will be apparent to those skilled in the art that various modifications, combinations, sub-combinations and alternatives are possible, depending on design requirements and other factors. Any modifications, equivalent substitutions and improvements made within the spirit and principles of the present invention should be included in the scope of the present invention.
Claims (10)
1. A critical control method for a nuclear reactor, which is adapted to control a first critical operation after finishing a refueling during a major repair of a nuclear power plant, the critical control method comprising:
in a first dilution stage, diluting the reactor core to dilute the boron concentration of a loop to a first target concentration, wherein the first target concentration is greater than a critical state boron concentration predicted value;
In the rod lifting stage, lifting control rods in various control rod groups from the full-insertion position to a target rod position;
in the second dilution stage, when the boron concentration of the primary loop meets a preset concentration condition, diluting the reactor core until the reactor meets a critical state condition;
wherein the lifting stage is located between the first dilution stage and the second dilution stage.
2. The method of critically controlling a nuclear reactor according to claim 1, wherein diluting the reactor core to dilute the boron concentration of the primary circuit to a first target concentration comprises:
obtaining a boron concentration predicted value in a critical state and an initial boron concentration of a loop;
calculating a first target water quantity required for diluting the boron concentration of the primary circuit to a first target concentration according to the initial boron concentration and the critical state boron concentration predicted value;
diluting the reactor core with the first target water quantity;
wherein, the first target water quantity is calculated as:
wherein V is 0 Indicating the first target water quantity, CB 0 Indicating the initial boron concentration, CB ECC A predicted value of boron concentration representing the critical state.
3. The critical control method of a nuclear reactor of claim 1, further comprising:
In the first dilution stage, carrying out neutron countdown rate ratio extrapolation calculation by taking a first set time length as a period;
determining whether the reactor reaches the critical state within the next first set period of time, and a dilution total water amount extrapolated calculated value and a boron concentration extrapolated calculated value required by the reactor to reach the critical state, based on a result of the neutron count down ratio extrapolated calculation;
and monitoring the critical process of the reactor according to whether the reactor reaches the critical state in the next first set time period, and the extrapolated calculated value of the total dilution water quantity and the extrapolated calculated value of the boron concentration.
4. The critical control method of a nuclear reactor of claim 3, further comprising:
stopping diluting the reactor core when determining that the reactor will reach the critical state in the next first set time period based on the result of the neutron countdown rate ratio extrapolation calculation;
in the first dilution stage, when the difference value between the current boron concentration of the first loop and the first target concentration is smaller than a preset difference value based on the result of the neutron countdown rate ratio extrapolation calculation, stopping diluting the reactor core;
And in the first dilution stage, stopping diluting the reactor core when the current measured value of the boron concentration of the first loop is smaller than or equal to the first target concentration.
5. The method of claim 1, wherein the boron concentration of the primary circuit satisfies a predetermined concentration condition, comprising:
the boron concentration of the primary loop is greater than a second target concentration, which is greater than the threshold state boron concentration estimate and less than the first target concentration.
6. The critical control method of a nuclear reactor according to any of claims 1-5, further comprising:
recording the actual dilution water quantity adopted by the first dilution stage for diluting the reactor core;
diluting the reactor core until the reactor meets critical state conditions, comprising:
calculating the total dilution water amount required for diluting the boron concentration of the first circuit to the estimated boron concentration value of the critical state according to the initial boron concentration of the first circuit and the estimated boron concentration value of the critical state;
determining the difference between the total dilution water amount and the actual dilution water amount as the residual dilution water amount required for diluting the boron concentration of the primary circuit to the boron concentration estimated value in the critical state;
And diluting the reactor core by adopting the residual dilution water amount until the reactor meets the critical state condition.
7. The method of claim 6, wherein the reactor core is diluted at a first dilution rate during a first time interval of the second dilution stage and the first dilution stage, and the neutron count down ratio extrapolation calculation is performed with a first set period of time;
diluting the reactor core at a second dilution rate in a second time interval of the second dilution stage, and performing neutron countdown rate ratio extrapolation calculation with a second set duration as a period;
wherein the first dilution rate is greater than the second dilution rate, and the second set duration is less than the first set duration; the first time interval is a time interval in which the total water injected into the reactor core in the second dilution stage is more than half of the residual dilution water, and the neutron countdown ratio is more than 0.5; the second time interval is a time interval in which the total water injected into the reactor core in the second dilution stage is less than or equal to half of the remaining dilution water amount, and/or a time interval in which a neutron countdown ratio is less than or equal to 0.5.
8. A critical control apparatus for a nuclear reactor adapted to control a first critical operation after a refueling completion during a major repair of the nuclear power plant, the critical control apparatus comprising:
the first dilution control module is used for diluting the reactor core in a first dilution stage so as to dilute the boron concentration of the primary loop to a first target concentration, wherein the first target concentration is larger than a boron concentration estimated value in a critical state;
the rod lifting control module is used for lifting control rods in various control rod groups from the full-insertion position to a target rod position in a rod lifting stage;
the second dilution control module is used for diluting the reactor core until the reactor meets the critical state condition when the boron concentration of the primary loop meets the preset concentration condition in the second dilution stage;
wherein the lifting stage is located between the first dilution stage and the second dilution stage.
9. An electronic device, the electronic device comprising:
at least one processor; and
a memory communicatively coupled to the at least one processor; wherein,,
the memory stores a computer program executable by the at least one processor to enable the at least one processor to perform the critical control method of the nuclear reactor of any of claims 1-7.
10. A computer readable storage medium storing computer instructions for causing a processor to perform the critical control method of the nuclear reactor of any of claims 1-7.
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