CN116011649A - Method for making load regulation operation scheme of pressurized water reactor unit - Google Patents

Method for making load regulation operation scheme of pressurized water reactor unit Download PDF

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CN116011649A
CN116011649A CN202310013564.8A CN202310013564A CN116011649A CN 116011649 A CN116011649 A CN 116011649A CN 202310013564 A CN202310013564 A CN 202310013564A CN 116011649 A CN116011649 A CN 116011649A
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rod
rod position
searching
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吕栋
王涛
鲍家东
金越
蒋校丰
骆文
陈超
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Shanghai Nustar Nuclear Power Technology Co ltd
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Abstract

The invention discloses a method for making a load regulation operation scheme of a pressurized water reactor unit, which comprises the steps of initializing a R rod position, optimizing the total length of time for inserting a C rod, and optimizing a boride-dilution strategy. The invention provides a standardized method for making a load regulation operation scheme of a pressurized water reactor unit, which can meet the scene requirements of all the requirements for load regulation, namely, operators can complete the making of the operation scheme according to the method without individual experience skills.

Description

Method for making load regulation operation scheme of pressurized water reactor unit
Technical Field
The invention belongs to the technical support field of nuclear power station operation, relates to a calculation and analysis method and a flow of a pressurized water moderated cooling reactor (pressurized water reactor) core, and particularly relates to a method for making a load (power) adjusting operation scheme of a pressurized water reactor unit.
Background
Currently, the pressurized water reactor unit used at home and abroad is mainly a second-generation pressurized water reactor nuclear motor unit. The core design of the second generation unit mainly considers the full-power basic load operation state, and the capacity of carrying out load tracking adjustment according to the power grid requirement is very limited. Therefore, when the unit needs to adjust the load level according to the plan, an operator can report the load adjustment plan to a technical support department in advance, and a targeted operation scheme is formulated by the unit through theoretical analysis. Technical support staff generally determine a scheme iteration path based on the current operating characteristics of the reactor core and similar past experiences, the whole process lacks necessary flow standardization, and also lacks multi-dimensional quantitative evaluation of scheme safety, economy and the like, and the technical support staff are too dependent on expertise stores and experience accumulation of related staff.
The mainstream pressurized water reactor core generator set typically comprises a reactor core in a square fuel assembly arrangement, a radial view of which is shown in fig. 1. At the top of the several fuel assembly locations within the stack is arranged a control rod drive mechanism that axially inserts or withdraws the core by adjusting the control rod absorbers. The control rods are generally functionally divided into a main regulation rod group, a power compensation rod group and a shutdown rod group, wherein the main regulation rod group is generally called R rod, the power compensation rod group is called C rod, and the typical distribution situation of different types of control rods in the pile is also shown in fig. 1. Different unit cores will differ in fuel and control rod distribution, but the above features are substantially identical.
The reactor controls the reactor power by adjusting the reactivity, which includes both chemical compensation to adjust the concentration of soluble boron in the coolant and mechanical compensation to adjust the control rod insertion location (rod position). In addition to the need to adjust the reactivity to make the core power output meet the operational requirements all the time, the core power distribution shape needs to be controlled (especially the axial power distribution can always meet the requirements of the operational specifications, ensuring the operational safety of the reactor).
The chemical compensation mode has the advantage of small disturbance to the power distribution of the reactor core, but the introduction of the chemical compensation mode is not as good as the mechanical compensation, and the frequent boronization and dilution of the coolant increase the operation complexity and simultaneously inevitably lead to the increase of the total amount of radioactive wastewater, so as to influence the economical level of the operation of the reactor core. Thus, chemical compensation is typically used to control the reactivity of slow changes such as core burnup, xenon toxicity changes, and slower load changes. For relatively faster load changes, it is often also necessary to control the reactivity by means of mechanical compensation. The mechanical compensation mode has the advantages of timely introduction of reactivity and no additional generation of radioactive wastewater, but can obviously change the power distribution of the reactor core while adjusting the reactivity. The reactor core power distribution always meets the operation safety requirement, and the high requirement on the operation control is provided while the reactivity regulation requirement is met; meanwhile, the xenon distribution of the reactor core in the load change process also deviates from a stable equilibrium xenon state, the change of the xenon distribution and the total amount can also have a remarkable influence on the reactor core reactivity and the power distribution, the complexity and the uncertainty of the operation control are further increased, and the operation control in the load adjustment process is always one of the main difficulties of the operation of the reactor core for operators.
For different mechanical compensation adjustment modes, the shutdown rod must be always out of the stack in the load adjustment process, and cannot participate in the reactivity adjustment; only the main tuning rod and the power compensator rods are available for reactive tuning, the allowable rod bit intervals of the main tuning rod are severely limited, and the time that the power compensator rods are allowed to be inserted into the core during the powered operation phase is severely limited. It can be seen that the mechanical compensation adjustment mode is still limited by various conditions when being implemented, which further increases the difficulty of operation control.
After the load adjustment schedule is determined, the operator will notify the technical support personnel of the schedule, which uses the core calculation program to proceed with the processAnd performing theoretical calculation simulation. In the specific simulation, on the premise of meeting the application limit related to all the reactive regulation modes, technicians need to regulate the soluble boron concentration, the main regulation rod position and the power compensation rod position at each time point, so that the result of theoretical simulation can meet the actual unit operation control requirements on the reactive and axial power distribution control. In particular, for axial power distribution control, a constant axial power offset (AO) is often used as an operation control target, i.e. it is required to maintain the core AO value always at a preset standard AO value during load variation 0 Nearby. The calculation formula of AO is as follows:
Figure BDA0004039141940000021
p in the formula t And P b The total power of the core along the upper and lower axial halves, respectively. In practical application, the AO is not directly referred to, but is referred to an index DI directly related to the AO, and the calculation formula of DI is:
DI=P×AO
p is the core relative power level (100% at full power). DI is also known as axial power deviation, which is primarily affected by relative power level, xenon toxicity profile, and control rod position, where only control rod position can be used as a DI adjustment means. In the calculation of the reactor core program, the control rod positions are generally searched and determined first, and after the control rod positions capable of meeting the control target of the reactor core DI are determined, the requirements of reactivity control are met as a final adjusting means through chemical compensation.
Because the three adjustment modes can all influence the reactivity, the change of the rod positions of the control rods with different functions can also influence DI, obviously, the final operation scheme cannot only have a unique standard answer, and the generation of the final scheme is also an iterative asymptotic process. The traditional establishment of the operation scheme of the load adjusting process lacks standardization of the process, technical support staff can often only establish an initial scheme by referring to the similar load adjusting process, and gradually adjust and iterate according to the calculation result of the initial scheme until the requirement is completely met. It is difficult to ensure the efficiency of the project formulation process and to control the safety and economical level of the operating project from a global perspective with relatively arbitrary iterative processes.
Disclosure of Invention
In summary, the formulation of the load adjustment operation scheme in the prior art lacks necessary flow standardization, and also does not fully consider the actual feasibility of the operation scheme, so that a plurality of uncertain factors exist. The invention aims to provide a method for formulating a load regulation operation scheme of a pressurized water reactor unit based on the standardization of a scheme formulation flow of an existing reactor core theory calculation tool, so that the formulated operation scheme has good operability and can meet the requirements of operation safety and economy.
The method of the invention has the following general ideas: in the load change process, still taking a constant AO as a control target, firstly searching and determining a target rod position of a main regulating rod, and then further searching and determining a rod position of a power compensating rod; and then, fine tuning the positions of the main adjusting rod and the power compensating rod according to the change curve of the critical boron concentration so as to optimize the boronizing dilution strategy, thereby obtaining the running scheme of the final load adjusting process.
For the convenience of describing the specific model of the method of the invention, the following symbol definitions are made for each key technical parameter:
p: a unit power level;
t: run time;
i: the method comprises the steps of carrying out numerical simulation on a load change process to obtain a discrete state point sequence number, wherein a starting point value is 0;
r: a main adjusting rod position;
● C: a power compensation bar position;
● PPM: critical boron concentration;
DI: core axial power bias;
·AO 0 : an AO value corresponding to the normal AO operation strategy, wherein the AO value is a known condition;
based on the foregoing inventive concept, to achieve the object of the present invention, the following technical solutions are adopted:
a method for making a load regulation operation scheme of a pressurized water reactor unit comprises the following steps:
1) R rod position initialization
Firstly, using reactor core calculation program to make theoretical simulation of load change process, at all the state points i placing C rod outside reactor, using AO 0 Searching R rod positions for the target; at this stage, the R rod position limit value interval is not set, and the R rod position is marked as R after the calculation is completed 0 (i);
After the R rod position search is completed, the calculation results of all the state points are divided into three cases: (1) searching for target AO 0 Successfully, and the rod position meets the operation limit value interval requirement, (2) searching the target AO 0 Successful, but with a bar position outside the operational limit interval, (3) search for target AO 0 Unsuccessful;
for the condition (1), the R rod position obtained by searching can be directly accepted, and then R rod resetting is completed;
in the cases (2) and (3), R bar is required to be reset, and the R bar is reset to the operation target bar position and the search bar position R under the premise that the limit value range of the operation regulation is not exceeded 0 (i) Between them; repeat until searching for target AO 0 Successfully completing R bar reset;
after the R rod is reset, the load regulation process is simulated again, the function of searching a target DI running belt for the C rod position is used for initializing the C rod position, the running belt is reset according to the calculation result, the running belt is relaxed at the point which does not accord with the state, so that all the final state points DI can enter the reset DI running belt, and the initialization of the R/C rod position is completed; recording the initialized R/C rod position as R 1 (i) And C 1 (i) The critical boron concentration at this time was PPM 1 (i);
2) Optimization of total length of C-bar insertion
Checking whether the total insertion time of the C rod in the step 1) can meet the limit requirement of the operation procedure, and if the limit requirement of the total insertion time of the C rod is met, directly entering the step 3); if not, reselect C 1 (i) The R/C rod changing searching is started by inserting a status point with smaller rod position in the rod position sequence, firstly, the C rod is completely lifted out of the pile to lead DI to be positive,and DI is changed into negative through R rod insertion to maintain DI unchanged, so that the total insertion time of the C rod is effectively shortened; the R/C rod positions are respectively R 2 (i) And C 2 (i) Critical boron concentration of PPM 2 (i);
3) Boride-dilution strategy optimization
Critical boron concentration PPM for step 2) 2 (i) Resetting, namely, depressing the variation range of the critical boron concentration, reducing the frequency of the boride/dilution small-amplitude reciprocating operation, then carrying out critical rod position searching again on the state point subjected to critical boron concentration resetting, and if both R/C rods can be used for critical searching, preferentially selecting a control rod with higher value to carry out critical rod position searching according to the reactive microscopic value of the rod position where the R/C rod is positioned; considering that the rod position change also has an influence on DI, the operation belt can be reset again before the critical rod position search is carried out, so that the DI calculation result after the rod position adjustment can still meet the axial power distribution control requirement; the R/C rod positions are respectively R 3 (i) And C 3 (i) Resetting the boron concentration to PPM 3 (i) I.e. the final solution produced by the method according to the invention.
In the above step, the search switch for the critical boron concentration is always turned on, that is, the critical boron concentration search is performed after the R/C rod position is determined, so that the critical core is finally maintained. Thus, with each change in rod position, the corresponding critical boron concentration PPM is updated.
The invention provides a standardized method for making a load regulation operation scheme of a pressurized water reactor unit, which can meet the scene requirements of all the requirements for load regulation, namely, operators can complete the making of the operation scheme according to the method without individual experience skills.
Drawings
FIG. 1 is a radial view of the core distribution.
Fig. 2 is a flow chart of the present invention.
Detailed Description
See the drawings. The embodiment comprises the following steps:
1) R rod position initialization
First, makeTheoretical simulation is carried out on the load change process by using a reactor core calculation program, C rods are arranged outside the reactor at all state points i, and AO is used for calculating the load change process 0 Searching R rod positions for the target; at this stage, the R rod position limit value interval is not set, and the R rod position is marked as R after the calculation is completed 0 (i);
After the R rod position search is completed, the calculation results of all the state points are divided into three cases: (1) searching for target AO 0 Successfully, and the rod position meets the operation limit value interval requirement, (2) searching the target AO 0 Successful, but with a bar position outside the operational limit interval, (3) search for target AO 0 Unsuccessful;
for the condition (1), the R rod position obtained by searching can be directly accepted, and then R rod resetting is completed;
in the cases (2) and (3), R bar is required to be reset, and the R bar is reset to the operation target bar position and the search bar position R under the premise that the limit value range of the operation regulation is not exceeded 0 (i) Between them; repeat until searching for target AO 0 Successfully completing R bar reset;
after the R rod is reset, the load regulation process is simulated again, the function of searching a target DI running belt for the C rod position is used for initializing the C rod position, the running belt is reset according to the calculation result, the running belt is relaxed at the point which does not accord with the state, so that all the final state points DI can enter the reset DI running belt, and the initialization of the R/C rod position is completed; recording the initialized R/C rod position as R 1 (i) And C 1 (i) The critical boron concentration at this time was PPM 1 (i);
2) Optimization of total length of C-bar insertion
Checking whether the total insertion time of the C rod in the step 1) can meet the limit requirement of the operation procedure, and if the limit requirement of the total insertion time of the C rod is met, directly entering the step 3); if not, reselect C 1 (i) The method comprises the steps of starting R/C rod changing searching by inserting a smaller state point of a rod position in a rod position sequence, firstly, completely lifting a C rod out of a pile to enable DI to be positive, and enabling DI to be negative through R rod insertion to maintain DI unchanged, so that the total insertion time of the C rod is effectively shortened; the R/C rod positions are respectively R 2 (i) And C 2 (i) Critical boron concentration of PPM 2 (i);
3) Boride-dilution strategy optimization
Critical boron concentration PPM for step 2) 2 (i) Resetting, namely, depressing the variation range of the critical boron concentration, reducing the frequency of the boride/dilution small-amplitude reciprocating operation, then carrying out critical rod position searching again on the state point subjected to critical boron concentration resetting, and if both R/C rods can be used for critical searching, preferentially selecting a control rod with higher value to carry out critical rod position searching according to the reactive microscopic value of the rod position where the R/C rod is positioned; considering that the rod position change also has an influence on DI, the operation belt can be reset again before the critical rod position search is carried out, so that the DI calculation result after the rod position adjustment can still meet the axial power distribution control requirement; the R/C rod positions are respectively R 3 (i) And C 3 (i) Resetting the boron concentration to PPM 3 (i) I.e. the final solution produced by the method according to the invention.

Claims (1)

1. The method for making the load regulation operation scheme of the pressurized water reactor unit is characterized by comprising the following steps of:
1) R rod position initialization
Firstly, using reactor core calculation program to make theoretical simulation of load change process, at all the state points i placing C rod outside reactor, using AO 0 Searching R rod positions for the target; at this stage, the R rod position limit value interval is not set, and the R rod position is marked as R after the calculation is completed 0 (i);
After the R rod position search is completed, the calculation results of all the state points are divided into three cases: (1) searching for target AO 0 Successfully, and the rod position meets the operation limit value interval requirement, (2) searching the target AO 0 Successful, but with a bar position outside the operational limit interval, (3) search for target AO 0 Unsuccessful;
for the condition (1), the R rod position obtained by searching can be directly accepted, and then R rod resetting is completed;
in the cases (2) and (3), R bar is required to be reset, and the R bar is reset to the operation target bar position and the search bar position R under the premise that the limit value range of the operation regulation is not exceeded 0 (i) A kind of electronic deviceA compartment; repeat until searching for target AO 0 Successfully completing R bar reset;
after the R rod is reset, the load regulation process is simulated again, the function of searching a target DI running belt for the C rod position is used for initializing the C rod position, the running belt is reset according to the calculation result, the running belt is relaxed at the point which does not accord with the state, so that all the final state points DI can enter the reset DI running belt, and the initialization of the R/C rod position is completed; recording the initialized R/C rod position as R 1 (i) And C 1 (i) The critical boron concentration at this time was PPM 1 (i);
2) Optimization of total length of C-bar insertion
Checking whether the total insertion time of the C rod in the step 1) can meet the limit requirement of the operation procedure, and if the limit requirement of the total insertion time of the C rod is met, directly entering the step 3); if not, reselect C 1 (i) The method comprises the steps of starting R/C rod changing searching by inserting a smaller state point of a rod position in a rod position sequence, firstly, completely lifting a C rod out of a pile to enable DI to be positive, and enabling DI to be negative through R rod insertion to maintain DI unchanged, so that the total insertion time of the C rod is effectively shortened; the R/C rod positions are respectively R 2 (i) And C 2 (i) Critical boron concentration of PPM 2 (i);
3) Boride-dilution strategy optimization
Critical boron concentration PPM for step 2) 2 (i) Resetting, namely, depressing the variation range of the critical boron concentration, reducing the frequency of the boride/dilution small-amplitude reciprocating operation, then carrying out critical rod position searching again on the state point subjected to critical boron concentration resetting, and if both R/C rods can be used for critical searching, preferentially selecting a control rod with higher value to carry out critical rod position searching according to the reactive microscopic value of the rod position where the R/C rod is positioned; considering that the rod position change also has an influence on DI, the operation belt can be reset again before the critical rod position search is carried out, so that the DI calculation result after the rod position adjustment can still meet the axial power distribution control requirement; the R/C rod positions are respectively R 3 (i) And C 3 (i) Resetting the boron concentration to PPM 3 (i) I.e. the final solution produced by the method according to the invention.
CN202310013564.8A 2023-01-05 2023-01-05 Method for making load regulation operation scheme of pressurized water reactor unit Pending CN116011649A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114220560A (en) * 2021-12-13 2022-03-22 中国核动力研究设计院 Boron-controlled peak regulation method and system for pressurized water reactor nuclear power plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114220560A (en) * 2021-12-13 2022-03-22 中国核动力研究设计院 Boron-controlled peak regulation method and system for pressurized water reactor nuclear power plant
CN114220560B (en) * 2021-12-13 2024-05-07 中国核动力研究设计院 Boron control peak regulation method and system for pressurized water reactor nuclear power plant

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