CN111753394B - Design method for debugging primary loop rapid cooling function of advanced pressurized water reactor nuclear power plant - Google Patents
Design method for debugging primary loop rapid cooling function of advanced pressurized water reactor nuclear power plant Download PDFInfo
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Abstract
The invention provides a design method for debugging a primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant, which comprises the following steps: (1) Analyzing the system configuration and the functions of the advanced pressurized water reactor nuclear power plant, analyzing the requirement of the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, and making the aim of debugging; (2) Based on the carding analysis of the system configuration and the functions, making acceptance criteria of the functions according to the principle of a loop rapid cooling function; (3) Designing debugging time based on an acceptance criterion of the circuit rapid cooling function debugging and combining an atmospheric relief valve pressure set value curve; (4) According to the system configuration and the function of the advanced pressurized water reactor nuclear power plant, initial conditions of a debugging test are designed; and (5) designing test contents in the debugging process. The invention fills the blank of the debugging method of the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, and ensures the safety, the high efficiency and the order of the debugging work of the advanced pressurized water reactor nuclear power plant.
Description
Technical Field
The invention belongs to the nuclear power plant design technology, and particularly relates to a design method for debugging a primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant.
Background
Debugging of a nuclear power plant refers to all activities to be performed by bringing structures, systems and components into a certain operation mode after installation work is basically completed, so as to comprehensively verify the design, equipment manufacturing, construction and installation quality of the nuclear power plant, and ensure continuous and stable operation of the nuclear power plant under rated power. The debugging process is mainly divided into two parts of non-core test and core test. Debugging is the last step of the construction stage of the nuclear power plant and the first step of the operation stage, and the comprehensiveness, safety and effectiveness of the debugging test are important for the safe and reliable operation of the nuclear power plant.
After the Japanese Fudao nuclear accident, according to the adjustment of the national nuclear energy policy and the development of the international trend, the new nuclear power plant in China adopts an advanced pressurized water reactor nuclear power technology with higher safety and stronger accident resistance. The advanced pressurized water reactor nuclear power plant firstly improves the overall safety of the nuclear power plant from the design angle, the design concept is mostly based on the design, manufacturing, construction and operation experience of the second generation improved pressurized water reactor nuclear power plant, new conceptual designs and items with new design characteristics are introduced, and the introduction of the new items tends to cause the change of the related contents of the debugging design method.
At present, in a second-generation or second-generation improved pressurized water reactor nuclear power plant, the frequency of occurrence of the accident of cracking of the heat transfer tube of the steam generator is high, and the damaged steam generator can overflow to release radioactivity into the atmosphere, and can also cause serious accidents caused by the clamping opening of a safety valve. In order to prevent the overflow of the steam generator, the advanced pressurized water reactor nuclear power plant reduces the closing lift of the safety injection pump in design, and adopts the medium-pressure safety injection pump to reduce the leakage from the primary loop to the secondary loop. Under certain small break accidents, the medium-pressure safety injection system can not be injected, in order to enable the safety injection system to be injected normally, the advanced pressurized water reactor nuclear power plant is designed with a rapid cooling function, reactor coolant is cooled rapidly through a secondary side atmosphere release valve of a steam generator, and the unit is cooled to a condition that waste heat is discharged and enters or the operation is finished when the operator intervenes according to a certain rate.
Because the function adopts a new design concept, no similar debugging scheme is used for reference in the domestic nuclear power station, and no related design file or literature is used for determining how the function is debugged and verified at present.
Disclosure of Invention
The invention aims to provide a design method for debugging a primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant, so that the type and main content of a debugging procedure file technical basis are definitely formulated, the first reactor test of the advanced pressurized water reactor nuclear power plant is guided, and the basis is provided for the debugging project of a subsequent unit of the same type.
The technical scheme of the invention is as follows: a design method for debugging a primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant comprises the following steps:
(1) Analyzing the system configuration and the functions of the advanced pressurized water reactor nuclear power plant, analyzing the requirement of the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, and making the aim of debugging;
(2) Based on the carding analysis of the system configuration and the functions, making acceptance criteria of the functions according to the principle of a loop rapid cooling function;
(3) Designing debugging time based on an acceptance criterion of the circuit rapid cooling function debugging and combining an atmospheric relief valve pressure set value curve;
(4) According to the system configuration and the function of the advanced pressurized water reactor nuclear power plant, initial conditions of a debugging test are designed;
(5) The test content in the debugging process is designed, and the test content comprises corresponding parameter settings of the first loop and the second loop and an adjusting scheme of a related control system.
In the step (1), the "safe injection signal" designed for the advanced pressurized water reactor nuclear power plant triggers the rapid cooling function of the first loop, and after receiving the safe injection signal, the rapid cooling is executed by the three atmosphere release valves, so as to verify whether the depressurization rate of the second loop meets the design requirement when the two atmosphere release valves are automatically adjusted.
Further, in the design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, in the step (2), the acceptance of the primary loop rapid cooling function is converted into the acceptance of the pressure of the secondary loop to meet the pressure set value curve of the atmospheric relief valve; the specific acceptance criteria established are: after triggering the quick cooling of the loop, the steam pressure is maintained within the error range of the pressure set value curve of the atmospheric relief valve within the period from the start of the steam pressure reaching the target pressure through the control of the atmospheric relief valve, so that the design requirement of the quick cooling of the loop is met.
Furthermore, as described above, the design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, the pressure set value curve of the atmospheric relief valve in the step (3) is as follows:
P＝K×GradT×Δt×(dP/dT)+P(t-Δt)；
Wherein K is a constant, and generally K is more than or equal to 2.2; gradT is the cooling rate, which can be 100 ℃/h; Δt is the time step between two cycles, e.g. 5s; dP/dT is the ratio of the saturation pressure to the saturation temperature of the two loops; p (t) is an atmospheric emission threshold value at the moment t; p= 0.8162T-383.46 (where T is in units of K) at 10 bar.ltoreq.P.ltoreq.100 bar.
Based on the curve, the pressure set point curve of the atmosphere relief valve is linear, and the total time for executing the rapid cooling function refers to the time for gradually reducing the pressure set point of the atmosphere relief valve from 7.85Mpa (a) to 4.5Mpa (a), and only a period of time is required to be verified during the test.
Further, the design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant as described above, wherein the initial conditions of the debugging test in the step (4) include:
the test should be performed with the loop in normal thermal shutdown conditions,
The pressurizer liquid level was set to 70%,
The three main pumps are put into operation,
The pressure and the liquid level of the pressure stabilizer are in an automatic control state,
The set value of the atmospheric relief valve pressure before the test was set to 7.85Mpa (a),
The steam generator water level is maintained at 50% by an auxiliary feedwater electric pump,
The lock-in signal triggers other action signals than rapid cooling.
Further, the design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant as described above, wherein the test content in the step (5) comprises:
and modifying the final set value of the atmospheric relief valve pressure into a target value, triggering a loop to quickly cool down in a transient state by an analog safety injection signal after the liquid level of the pressure stabilizer is stable, enabling the pressure stabilizer and the liquid level to be in an automatic control state, supplementing water for the steam generator by an auxiliary water supply electric pump, and closely monitoring the liquid level of the pressure stabilizer and the liquid level of the steam generator. The valve of the steam condenser should be closed automatically, and the temperature and pressure of the first loop and the second loop are monitored respectively; and when the pressure of the second loop reaches the target pressure, stopping the test, and recovering to the initial state to maintain the stability of the unit.
The beneficial effects of the invention are as follows:
the invention analyzes the system configuration and the function aiming at the advanced pressurized water reactor nuclear power plant, analyzes the requirement of the primary loop rapid cooling function, and fills the blank of the debugging design method of the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant.
According to the invention, through the design acceptance criterion, the acceptance of the primary loop rapid cooling function is converted into the acceptance of the secondary loop steam pressure to meet the pressure set value curve of the atmospheric relief valve, so that the requirements on design can be met, on-site debugging personnel can be enabled to operate more easily, and a foundation is laid for the smooth proceeding of subsequent on-site debugging.
Because the rapid cooling and injection of the loop can cause larger thermal shock of the loop in the debugging process, the invention designs the test duration and reduces the thermal shock of the loop as much as possible. Because the duration of the test is reduced, the technical scheme improves the efficiency of on-site debugging while ensuring that the function verification requirement is met, thereby reasonably and efficiently preparing a method for debugging the quick cooling function of the primary loop.
Because the advanced pressurized water reactor adopts a new design concept, the aim of debugging is to verify the correctness of the performance and the design compliance of the pressurized water reactor, and when the new designs adopt standardized designs and are not changed along with the site characteristics of the nuclear power plant, the first reactor test result can be used for the same series of nuclear power units. The design method of the invention can provide guidance for the first-pile test, improve the test efficiency and increase the economy of the nuclear power plant.
Drawings
FIG. 1 is a flow chart of a method for debugging and designing a quick cooling function of a primary loop of an advanced pressurized water reactor nuclear power plant.
Detailed Description
The present invention will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present invention more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention.
The advanced pressurized water reactor nuclear power plant is based on a second generation improved pressurized water reactor nuclear power plant, and a loop rapid cooling function is introduced, so that the related content of the debugging design method is changed. The invention provides a design method for debugging the quick cooling function of a primary loop of an advanced pressurized water reactor nuclear power plant, which is used as a brand new function, and has no related debugging experience, so that the type and main content of the technical basis of a debugging procedure file are definitely formulated. The design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, which is researched by the design method, comprises the test purpose, the acceptance criterion, the initial condition and the test content, so that field debugging personnel can conveniently formulate detailed debugging rules.
The design method of the invention is described in detail by taking an advanced pressurized water reactor 'safe injection signal triggering automatic rapid cooling, and rapidly cooling reactor coolant through three atmosphere release valves on the secondary side of a steam generator until the pressure of steam in the second loop is reduced to 4.5 MPa' as an example:
(1) Design test purpose
Aiming at an advanced pressurized water reactor nuclear power plant, the system configuration and the function of the advanced pressurized water reactor nuclear power plant are analyzed in detail through basic technical files (such as a system design manual), and the requirement of the rapid cooling function of a primary loop of the advanced pressurized water reactor is analyzed, so that the aim of debugging is formulated.
When the accident condition (such as small and medium LOCA, SGTR, etc.) that the primary circuit water content is reduced occurs in the advanced pressurized water reactor nuclear power plant, the safety injection system needs to inject safety water into the primary circuit to maintain the water content of the primary circuit system. Because the advanced pressurized water reactor nuclear power plant adopts the medium-pressure safety injection, when accidents such as middle and small LOCA and SGTR occur, the pressure of a loop is higher than the injection pressure of the medium-pressure safety injection, and the safety injection cannot be injected into the loop temporarily, the pressure of a reactor coolant system needs to be reduced rapidly, so that the medium-pressure safety injection can be injected into the loop system as soon as possible. Based on the thought, an 'safe injection signal triggering one-loop rapid cooling' function is designed in the advanced pressurized water reactor. It is therefore necessary to verify that the existing arrangement is capable of achieving a rapid cooling function. According to the system design, after receiving the safety injection signal under the accident working condition, the three atmosphere release valves can automatically execute the rapid cooling function. When the test verifies, the working condition of single fault is considered, namely, one atmosphere release valve is isolated, and whether the depressurization rate of the two loops meets the design requirement when the safety injection signal triggers the automatic adjustment of the two atmosphere release valves is verified.
(2) Design acceptance criteria
Based on the system configuration and the carding and analysis of the functions, the acceptance method of the functions is equivalently converted into a test method which is easy to operate by field debugging personnel according to the principle of a quick cooling function of a loop, so that corresponding acceptance criteria are formulated.
When the safety injection signal triggers rapid cooling, the change-over switch is automatically switched to the channel of the function generator, so that the pressure set value of the atmosphere relief valve is gradually reduced from 7.85MPa (a) to 4.5MPa (a). To verify that the primary loop can realize the rapid cooling function, firstly, through safety analysis, the pressure reduction rate of the secondary side of the steam generator is ensured to meet the design requirement, and then the verification of the primary loop rapid cooling function is converted into verification of the secondary loop steam pressure curve to meet the design requirement, namely, the verification of the secondary loop steam pressure curve to meet the set pressure curve of the atmospheric relief valve. Therefore, after triggering the rapid cooling, the steam pressure is maintained within the error range of the pressure set value curve of the atmospheric discharge valve in the period from the start of the steam pressure reaching the target pressure through the control of the atmospheric release valve, namely, the design requirement of the rapid cooling of the primary circuit is met. Checking the steam pressure is more beneficial to the operation of on-site commissioning personnel.
(3) Design debug time
Based on the debugging acceptance criteria of the quick cooling function of the primary loop of the advanced pressurized water reactor nuclear power plant and in combination with the design and debugging time of the pressure set value curve of the atmospheric relief valve, in order to reduce the thermal shock of the quick cooling to the primary loop, the test time should be considered to be reduced as much as possible, and the test should be considered to be stopped before the pressure of the primary loop approaches the safety injection pressure so as to prevent the thermal shock caused by the safety injection to the primary loop. The test time should be minimized. From the acceptance criteria, verifying the primary circuit rapid cooling function is equivalent to verifying that the secondary circuit vapor pressure profile meets the atmospheric relief valve pressure set point profile as follows:
P＝K×GradT×Δt×(dP/dT)+P(t-Δt)
wherein K is a constant, and generally K is more than or equal to 2.2; gradT is the cooling rate, and 100 ℃/h is taken; Δt is the time step between two cycles, 5s; dP/dT is the ratio of the saturation pressure to the saturation temperature of the two loops; p (t) is an atmospheric emission threshold value at the moment t; at 10.ltoreq.P.ltoreq.100 bar, P= 0.8162T-383.46 (where T is in K).
The total time for executing the rapid cooling function refers to the time for gradually reducing the pressure set value of the atmospheric relief valve from 7.85Mpa (a) to 4.5Mpa (a), and the test is carried out only by verifying the pressure set value of the atmospheric relief valve for a period of time because the pressure set value curve of the atmospheric relief valve is linear. The test can be stopped when the secondary side pressure reaches a certain target pressure (higher than 4.5MPa (a), and the primary circuit pressure is higher than Yu An injection pressure at the moment). That is, the test should be stopped before the pressure in the one circuit approaches the safe injection pressure. Through calculation, the debugging time of the quick cooling function of the primary loop of the advanced pressurized water reactor nuclear power plant can be set to be 6 minutes, so that the thermal shock of the quick cooling to the primary loop is greatly reduced, and the test time is saved.
(4) Initial conditions of design test
According to the configuration and the function of an advanced pressurized water reactor nuclear power plant system, in order to simulate the actual operation working condition of the nuclear power plant as far as possible, debugging tests are carried out under the condition that a loop is in a normal thermal shutdown working condition, three main pumps are put into operation, and the pressure and the liquid level of a pressure stabilizer are in an automatic control state. Because the loop is rapidly cooled and depressurized in the test process, the coolant can shrink severely, and the liquid level of the voltage stabilizer is reduced, so that the liquid level of the voltage stabilizer needs to be raised to 70% before the test. The atmospheric relief valve should be in an isolated state before the test, and the atmospheric relief valve pressure set point is set to 7.85Mpa (a). The steam pressure is controlled by a condenser, and the water level of the steam generator is controlled to be 50% by an auxiliary water supply electric pump. To avoid safe injection malfunction, the safe injection signal is blocked before the test to trigger other action signals except quick cooling.
(5) Design test content
According to the configuration and functions of the advanced pressurized water reactor nuclear power plant system and the test purpose, corresponding parameter settings of the first loop and the second loop and the adjustment scheme of the related control system in the debugging process are designed.
Because a large amount of steam is discharged in the test process, the liquid level of the steam generator can change greatly, the liquid level of the steam generator needs to be monitored closely, measures should be taken to prevent the liquid level of the steam generator from being too high and avoid overflow of the secondary side of the steam generator, and measures should also be taken to prevent the liquid level of the steam generator from being too low and avoid exposure of heat transfer tubes of the steam generator. Because the primary loop coolant contracts rapidly, the liquid level of the voltage stabilizer needs to be monitored closely, measures should be taken to prevent the liquid level of the voltage stabilizer from being too low and to avoid the exposure of the electric heater of the voltage stabilizer. In order to ensure that the verification result is effective, after the simulation safety injection signal triggers the quick cooling transient state of the first loop, the valve of the steam condenser should be automatically closed, and the temperature and the pressure of the first loop and the second loop are monitored. And when the set value of the atmospheric relief valve pressure reaches the target pressure, stopping the test, and recovering to the initial state to maintain the stability of the unit.
The invention analyzes and designs the design method for debugging the primary loop rapid cooling function of the domestic advanced pressurized water reactor nuclear power plant based on the design characteristics of the advanced pressurized water reactor nuclear power plant and the actual requirements of debugging work execution, and the method is used for verifying the correctness and the conformity with the design of the primary loop rapid cooling function, thereby ensuring the safety, the high efficiency and the ordering of the debugging work. The design method for debugging the primary cooling function of the primary loop of the advanced pressurized water reactor nuclear power plant can guide the primary loop test of the advanced pressurized water reactor nuclear power plant, and in addition, the debugging project of the follow-up homotypic unit can evaluate whether the test is repeated or not according to the coincidence of the items, so that the whole debugging period can be effectively shortened, and a foundation is laid for improving the economy and the safety of the nuclear power unit.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (7)
1. A design method for debugging a primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant comprises the following steps:
(1) Analyzing the system configuration and the functions of the advanced pressurized water reactor nuclear power plant, analyzing the requirement of the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant, and making the aim of debugging;
(2) Based on the carding analysis of the system configuration and the functions, making acceptance criteria of the functions according to the principle of a loop rapid cooling function;
(3) Designing debugging time based on an acceptance criterion of the circuit rapid cooling function debugging and combining an atmospheric relief valve pressure set value curve;
(4) According to the system configuration and the function of the advanced pressurized water reactor nuclear power plant, initial conditions of a debugging test are designed;
(5) Designing test contents in the debugging process, wherein the test contents comprise: after the simulation safety injection signal triggers the quick cooling transient state of the first loop at the beginning of the test, the valve of the steam condenser is automatically closed, and the temperature and the pressure of the first loop and the second loop are respectively monitored; and when the pressure of the second loop reaches the target pressure, stopping the test, and recovering to the initial state to maintain the stability of the unit.
2. The design method for debugging the primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant as set forth in claim 1, wherein: in the step (1), after receiving the safety injection signal, three atmosphere release valves are used for executing rapid cooling, and the debugging purpose is to verify whether the depressurization rate of the two loops meets the design requirement when the two atmosphere release valves are automatically regulated.
3. The design method for debugging the primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant as set forth in claim 1, wherein: in the step (2), the acceptance of the primary loop rapid cooling function is converted into the acceptance of the secondary loop steam pressure meeting the pressure set value curve of the atmosphere relief valve.
4. The design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant as set forth in claim 3, wherein: the specific acceptance criteria established in the step (2) are as follows: after triggering the quick cooling of the loop, the steam pressure is maintained within the error range of the pressure set value curve of the atmospheric relief valve within the period from the start of the steam pressure reaching the target pressure through the control of the atmospheric relief valve, so that the design requirement of the quick cooling of the loop is met.
5. The design method for debugging the primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant as set forth in claim 1, wherein: the atmospheric relief valve pressure set point profile described in step (3) is:
P＝K×GradT×Δt×(dP/dT)+P(t-Δt)
Wherein K is a constant; gradT is the cooling rate; Δt is the time step between two cycles; dP/dT is the ratio of the saturation pressure to the saturation temperature of the two loops; p (t) is the atmospheric emission threshold value at time t.
6. The design method for debugging the primary loop rapid cooling function of the advanced pressurized water reactor nuclear power plant as set forth in claim 5, wherein: the total time for performing the rapid cooling function means the time taken for the atmospheric relief valve pressure set point to gradually decrease from 7.85Mpa (a) to 4.5Mpa (a).
7. The design method for debugging the primary loop rapid cooling function of an advanced pressurized water reactor nuclear power plant as set forth in claim 1, wherein: the initial conditions of the debug test described in step (4) include:
the test should be performed with the loop in normal thermal shutdown conditions,
The pressurizer liquid level was set to 70%,
The three main pumps are put into operation,
The pressure and the liquid level of the pressure stabilizer are in an automatic control state,
The set value of the atmospheric relief valve pressure before the test was set to 7.85Mpa (a),
The steam generator water level is maintained at 50% by an auxiliary feedwater electric pump,
The lock-in signal triggers other action signals than rapid cooling.
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