CN112906201A - Design method for loop system overpressure protection in pressurized water reactor operation state - Google Patents

Design method for loop system overpressure protection in pressurized water reactor operation state Download PDF

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CN112906201A
CN112906201A CN202110110001.1A CN202110110001A CN112906201A CN 112906201 A CN112906201 A CN 112906201A CN 202110110001 A CN202110110001 A CN 202110110001A CN 112906201 A CN112906201 A CN 112906201A
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overpressure
pressurized water
water reactor
analysis
protection
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CN112906201B (en
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张丹
邱志方
冉旭
刘松涛
周科
李喆
喻娜
邓坚
江光明
宋丹戎
钟发杰
曾畅
曾未
李峰
张航
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Nuclear Power Institute of China
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Abstract

The invention discloses a design method for loop system overpressure protection in a pressurized water reactor running state, which comprises the following steps: s1, constructing a pressurized water reactor model of the overpressure protection system to be designed; s2, obtaining the initial total discharge of the safety valve according to the change rule of the coolant volume along with time after the reactor and the primary circuit system are shut down due to an accident; s3, substituting the initial total displacement obtained in the step S2 into the pressurized water reactor model constructed in the step S1, and calculating the total displacement of the safety valve based on a deterministic analysis method; s4, optimizing a protection signal, a voltage stabilizer capacity and a surge pipe diameter corresponding to the overpressure protection system based on a deterministic theory analysis method; s5, determining the number of safety valves in the overpressure protection system based on probability theory, and designing an upstream pipeline, a downstream pipeline and an isolation valve. The problem of current overpressure protection design mainly confirm through the response analysis after the accident that lead to the number of iterations many, cycle length, be difficult to find out the total minimum discharge capacity of the relief valve that satisfies the safety requirement simultaneously is solved.

Description

Design method for loop system overpressure protection in pressurized water reactor operation state
Technical Field
The invention relates to the technical field of design of a pressurized water reactor nuclear power system, in particular to a design method for primary circuit system overpressure protection in a pressurized water reactor running state.
Background
For a pressurized water reactor nuclear power system, the coolant is in a high-temperature and high-pressure state under the power operation working condition, and when the operation transient state or the accident working condition occurs, the temperature and the pressure of the coolant system are likely to rise and even exceed the design pressure of the system, so that the pressure boundary of the coolant is damaged. In order to ensure the integrity of the pressure boundary of the primary circuit in the power running state, the overpressure protection design of a coolant system is required, and the overpressure risk is reduced through the combination of functions of shutdown protection, storage in a voltage stabilizer, overpressure discharge of a safety valve and the like. The safety valve is generally arranged at the top of the pressure stabilizer and used for discharging part of gas under the condition of overpressure so as to reduce the pressure in the loop, and the discharge amount of the safety valve is important for judging whether the system is overpressure or not. In the current engineering design, the overpressure protection design including the discharge capacity of the safety valve is mainly determined by overpressure response analysis after an accident, generally, a proper protection signal and the total discharge capacity of the valve are preliminarily selected by referring to engineering experience, the accident with the worst result on the overpressure of a coolant system is selected for safety analysis, an overpressure analysis result is obtained and fed back to system and equipment specialties, and finally, the final protection signal, relevant parameters of a voltage stabilizer and the total discharge capacity and the number of the safety valve are obtained by performing multiple design iterations in the period.
The design of the mode needs repeated iterative analysis of safety analysis and system design, the time period is long, and meanwhile, the total minimum discharge capacity of the safety valve meeting the safety requirement is difficult to find out, so that the improvement of the comprehensive performance of the nuclear power plant is not facilitated.
Disclosure of Invention
The invention aims to provide a design method for loop system overpressure protection in a pressurized water reactor running state, and solves the problems that the existing overpressure protection design is mainly determined by response analysis after an accident, so that the iteration times are large, the period is long, and the total minimum discharge capacity of a safety valve meeting the safety requirement is difficult to find.
The invention is realized by the following technical scheme:
the design method for the primary circuit system overpressure protection in the pressurized water reactor operation state comprises the following steps:
s1, constructing a pressurized water reactor model of the overpressure protection system to be designed;
s2, obtaining the initial total discharge of the safety valve according to the change rule of the coolant volume along with time after the reactor and the primary circuit system are shut down due to an accident;
s3, substituting the initial total displacement obtained in the step S2 into the pressurized water reactor model constructed in the step S1, and calculating the total displacement of the safety valve based on a deterministic analysis method;
s4, substituting the initial total discharge volume into a pressurized water reactor model, judging whether an overpressure criterion is met or not after the valve discharge volume is larger than or equal to the maximum fluctuation flow volume, directly carrying out the next step if the overpressure criterion is met, and optimizing a protection signal, a voltage stabilizer capacity and a fluctuation pipe diameter corresponding to an overpressure protection system based on a deterministic analysis method if the overpressure criterion is not met;
s5, determining the number of safety valves in the overpressure protection system based on probability theory, and designing the upstream pipeline, the downstream pipeline and the isolation valve, wherein the probability theory takes the principle of reducing the probability and the consequence of overpressure as much as possible.
Because the pressure regulation of the reactor coolant is realized by the voltage stabilizer, and the overpressure of the coolant system is caused by the expansion of the coolant system, aiming at the overpressure protection of a loop in a power running state, the requirement of the total discharge capacity of the safety valve of the voltage stabilizer to be at least as same as the maximum input capacity of the voltage stabilizer in an overpressure transient state is met, namely, the total discharge capacity of the safety valve of the voltage stabilizer is completely discharged out of the system through the safety valve of the voltage stabilizer due to the volume difference of the expansion of the system in the transient process, so that the overpressure of the system is avoided. Based on the requirement, the invention provides a new method for designing the loop overpressure protection in the power running state of the pressurized water reactor nuclear power plant, which can improve the working efficiency, better quantize the discharge capacity requirement and the quantity setting of the valve, optimize the design of protection signals and equipment or parts, and improve the comprehensive performance of a nuclear power system.
The initial total displacement described in step S2 of the present invention is an estimated value.
The design method is a new safety design method of primary circuit overpressure protection, which combines probability theory and definite theory, and combines estimation and system demonstration, thereby reducing the times of design iteration among professions and improving the working efficiency; meanwhile, the minimum discharge capacity requirement of the safety valve of the voltage stabilizer is better quantified, the design of equipment and parts is optimized, and the comprehensive performance of the nuclear power system is improved.
Further, the acquisition of the initial total displacement in step S2 includes a first overpressure analysis and a detailed demonstration analysis after the overpressure analysis.
Further, in the first overpressure analysis, if the steam generator adopted by the pressurized water reactor nuclear power is a saturated steam generator, the heat carrying capacity of the secondary side of the evaporator needs to be considered in the process of obtaining the initial total displacement, and if the steam generator adopted by the pressurized water reactor nuclear power is a direct-current steam generator, the heat carrying capacity of the secondary side of the evaporator does not need to be considered.
System heating value delta Q in t + delta t timetAnd specific heat C of fluidtMass m of fluidRCS、mSGAnd the temperature difference Δ T are as follows:
ΔQt＝Ct·mRCS·ΔT+Ct·mSG·ΔT
mRCS、·mSGthe water quality of the coolant system and the secondary side of the steam generator, respectively, for a once-through steam generator nuclear power plant, the heat capacity of the steam generator, i.e. C, may be disregardedt·mSGΔ T is assumed to be 0. When the accumulated variation of the volume of the primary loop water is larger than the steam space volume of the pressure stabilizer during normal operation, the pressure stabilizer is full of water, the change rate of the volume of the water in the loop at the moment is selected as a required value of the fluctuation discharge capacity of the fluctuation pipe, the total discharge capacity of the safety valve is not smaller than the flow, and the time point is used as the moment when the overpressure accident shutdown signal requires shutdown.
Further, in overpressure analysis after overpressure analysis, the initial total displacement of the safety valve of the voltage stabilizer is directly taken from the maximum fluctuation flow in the analysis.
Further, in step S3, the process of accounting for the total displacement of the safety valve based on the determinism analysis method is as follows:
if the initial total displacement is substituted into the pressurized water reactor model, the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is met, the next step is carried out, if the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is not met, the change rule of the coolant volume of the reactor and the loop system along with the time after the reactor is shut down due to an accident is re-analyzed and obtained, and the change rule is substituted into the pressurized water reactor model to carry out overpressure analysis and valve volume analysis until the requirement that the valve displacement is larger than or equal to the.
Further, in step S4, the protection signal and the volume of the pressurizer are obtained to ensure that the reactor is shut down before the pressurizer is full of water, and the caliber of the surge pipe is obtained to ensure that the liquid in a loop expands and is discharged into the pressurizer in time to avoid overpressure in the loop.
Specifically, by optimizing shutdown signals and setting values and the initial gas volume or total volume of the voltage stabilizer, the shutdown of the reactor is triggered before the voltage stabilizer is full of water, so that a loop water compact state is avoided; by optimizing the pressure drop of the surge pipe (the pipe diameter of the surge pipe), the expansion of liquid in the loop is ensured to be timely discharged into the voltage stabilizer, and the overpressure of the loop is avoided.
Further, the specific process of guard signal acquisition is as follows:
and when the overpressure criterion is not met, judging whether the pressure stabilizer is full of water before shutdown, if the overpressure criterion is not met, directly optimizing the pipe diameter of the fluctuation pipe, if the overpressure criterion is not met, indicating that the protection signal can be optimized, judging whether the optimization is carried out, if the optimization is required, substituting the protection signal into a pressurized water reactor model, determining the protection signal based on a determinacy analysis method, and if the optimization is not required, directly judging whether the capacity of the pressure stabilizer is optimized.
Further, the specific process of acquiring the capacity of the voltage stabilizer is as follows:
and after judging that the protection signal does not need to be optimized, judging whether the capacity of the voltage stabilizer is optimized or not, if so, substituting the capacity of the voltage stabilizer into a pressurized water reactor model, determining the capacity of the voltage stabilizer based on a determinacy analysis method, and if not, directly optimizing the pipe diameter of the fluctuation pipe.
Further, the specific process of acquiring the pipe diameter of the surge pipe is as follows:
and substituting the pipe diameter of the surge pipe into the pressurized water reactor model, and determining the pipe diameter of the surge pipe based on a determinacy analysis method.
Further, the specific process of step S5 is as follows:
on the premise that the safety valve meets single fault, probability theory analysis technology is adopted to analyze the probability and consequence of mistaken opening and blocking of the single-row valves, and the final number, upstream pipelines, downstream pipelines and isolation valve design of the safety valves are determined based on the probability theory analysis technology.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. the invention can quickly obtain the volume change of the primary loop water and the water full time of the voltage stabilizer after an overpressure accident occurs in the power running state of the reactor, thereby providing requirements for the safety valve of the voltage stabilizer, a shutdown signal, the gas volume of the voltage stabilizer and the fluctuation capacity of the fluctuation pipe under the transient state from the safety design angle of the primary loop overpressure protection.
2. The invention obtains the requirements of the safety design through the demonstration and analysis of safety analysis major, thereby guiding the relevant design of the protection signal, the voltage stabilizer, the surge pipe and the safety valve.
3. The invention obtains the number of safety valves and the configuration conditions of the pipeline valves upstream and downstream of the safety valves through probabilistic design; through the design, the working efficiency is greatly improved, and the reliability of overpressure protection and the safety of the reactor are ensured.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic flow chart of the method of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1:
as shown in fig. 1, the design method for the protection of the primary circuit system against overpressure in the operating state of the pressurized water reactor comprises the following steps:
s1, constructing a pressurized water reactor model of the overpressure protection system to be designed;
s2, obtaining the initial total discharge of the safety valve according to the change rule of the coolant volume along with time after the reactor and the primary circuit system are shut down due to an accident;
for this step, there is a discrepancy between the first estimate and the estimate after the overpressure analysis has been performed. For the first estimation, different methods of a steam generator adopted by pressurized water reactor nuclear power also have differences: for a saturated steam generator, because a large amount of supercooled water exists in the two loops, the heat carrying capacity of the secondary side of the evaporator needs to be properly considered, and for a pressurized water reactor adopting a direct-current steam generator, the water content of the secondary side is small, and the heat carrying capacity of the secondary side can be not considered.
System heating value delta Q in t + delta t timetAnd specific heat C of fluidtMass m of fluidRCS、mSGAnd the temperature difference Δ T are as follows:
ΔQt＝Ct·mRCS·ΔT+Ct·mSG·ΔT
mRCS、·mSGthe water quality of the coolant system and the secondary side of the steam generator, respectively, for a once-through steam generator nuclear power plant, the heat capacity of the steam generator, i.e. C, may be disregardedt·mSGΔ T is assumed to be 0. When the accumulated variation of the volume of the primary loop water is larger than the steam space volume of the pressure stabilizer during normal operation, the pressure stabilizer is full of water, the change rate of the volume of the water in the loop at the moment is selected as a required value of the fluctuation discharge capacity of the fluctuation pipe, the total discharge capacity of the safety valve is not smaller than the flow, and the time point is used as the moment when the overpressure accident shutdown signal requires shutdown.
For the valve capacity estimation after overpressure analysis, the maximum fluctuating flow in the analysis is taken directly.
S3, substituting the initial total displacement obtained in the step S2 into the pressurized water reactor model constructed in the step S1, and calculating the total displacement of the safety valve based on a deterministic analysis method; the specific process is as follows:
if the initial total displacement is substituted into the pressurized water reactor model, the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is met, the next step is carried out, if the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is not met, the change rule of the coolant volume of the reactor and the loop system along with the time after the reactor is shut down due to an accident is re-analyzed and obtained, and the change rule is substituted into the pressurized water reactor model until the requirement that the valve displacement is larger than or equal to the maximum fluctuation;
s4, substituting the initial total discharge volume into a pressurized water reactor model, judging whether an overpressure criterion is met or not after the valve discharge volume is larger than or equal to the maximum fluctuation flow volume, directly carrying out the next step if the overpressure criterion is met, and optimizing a protection signal, a voltage stabilizer capacity and a fluctuation pipe diameter corresponding to an overpressure protection system based on a deterministic analysis method if the overpressure criterion is not met;
the protection signal and the capacity of the voltage stabilizer are obtained on the principle of ensuring that the reactor is triggered to stop before the voltage stabilizer is full of water, the pipe diameter of the surge pipe is obtained on the principle of ensuring that the expansion of liquid in a loop is timely discharged into the voltage stabilizer to avoid the overpressure of the loop, and the specific process is as follows:
when the overpressure criterion is not met, judging whether the pressure stabilizer is full of water before shutdown, if the pressure stabilizer is judged not to be full of water before shutdown, directly optimizing the pipe diameter of a fluctuation pipe, if the pressure stabilizer is full of water before shutdown, indicating that a protection signal can be optimized, judging whether the optimization is performed, if the optimization is required, substituting the protection signal into a pressurized water reactor model, determining the protection signal based on a determinacy analysis method, and if the optimization is not required, directly judging whether the capacity of the pressure stabilizer is optimized;
judging whether the capacity of the voltage stabilizer is optimized or not after judging that the protection signal does not need to be optimized, substituting the capacity of the voltage stabilizer into a pressurized water reactor model if the capacity of the voltage stabilizer needs to be optimized, determining the capacity of the voltage stabilizer based on a deterministic theory analysis method, and directly optimizing the pipe diameter of a fluctuation pipe if the capacity of the voltage stabilizer does not need to be optimized;
and substituting the pipe diameter of the surge pipe into the pressurized water reactor model, and determining the pipe diameter of the surge pipe based on a determinacy analysis method.
S5, determining the number of safety valves in the overpressure protection system and designing an upstream pipeline, a downstream pipeline and an isolation valve based on probability theory, wherein the probability theory takes the principle of reducing the probability and the consequence of overpressure as much as possible:
the total discharge capacity of the safety valve, the protection signal corresponding to overpressure protection and the optimized pipe diameter of the surge pipe are determined by adopting a deterministic theory analysis method in the steps S1-S4, and a probabilistic theory method needs to be introduced in the section to realize high-reliability design of overpressure protection. The safety valve is clamped to be exposed as experience feedback of a nuclear power plant, accidents which seriously threaten the safety of a reactor core need to be reduced as far as possible, for the accidents, on the premise that the safety valve meets a single fault, the probability theory analysis technology is adopted to analyze the probability and consequence of the mistaken opening and clamping of a single-row valve, the final number of the safety valve, the upstream and downstream pipelines and the design of the isolation valve are determined on the basis, and therefore the consequence of the clamping of the safety valve is reduced, even if the safety valve is clamped, the loss of a coolant can be avoided, and the safety of the nuclear power plant is guaranteed.
In this embodiment, the specific process of the determinism analysis method is as follows:
the design method is a new safety design method of primary circuit overpressure protection, which combines probability theory and determinism, and combines estimation and system demonstration, so that the number of design iterations among professions is reduced, and the working efficiency is improved; meanwhile, the minimum discharge capacity requirement of the safety valve of the voltage stabilizer is better quantified, the design of equipment and parts is optimized, and the comprehensive performance of the nuclear power system is improved.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.

Claims (10)

1. The design method for the primary circuit system overpressure protection in the pressurized water reactor operation state is characterized by comprising the following steps of:
s1, constructing a pressurized water reactor model of the overpressure protection system to be designed;
s2, obtaining the initial total discharge of the safety valve according to the change rule of the coolant volume along with time after the reactor and the primary circuit system are shut down due to an accident;
s3, substituting the initial total displacement obtained in the step S2 into the pressurized water reactor model constructed in the step S1, and calculating the total displacement of the safety valve based on a deterministic analysis method;
s4, substituting the initial total discharge volume into a pressurized water reactor model, judging whether an overpressure criterion is met or not after the valve discharge volume is larger than or equal to the maximum fluctuation flow volume, directly carrying out the next step if the overpressure criterion is met, and optimizing a protection signal, a voltage stabilizer capacity and a fluctuation pipe diameter corresponding to an overpressure protection system based on a deterministic analysis method if the overpressure criterion is not met;
s5, determining the number of safety valves in the overpressure protection system based on probability theory, and designing the upstream pipeline, the downstream pipeline and the isolation valve, wherein the probability theory takes the principle of reducing the probability and the consequence of overpressure as much as possible.
2. The design method for the primary circuit system overpressure protection under the pressurized water reactor operating condition as claimed in claim 1, wherein the obtaining of the initial total displacement in step S2 includes a first overpressure analysis and a detailed demonstration analysis after the overpressure analysis.
3. The design method for primary circuit system overpressure protection in pressurized water reactor operating state as claimed in claim 2, wherein in the first overpressure analysis, if the steam generator adopted by the pressurized water reactor nuclear power is a saturated steam generator, the heat carrying capacity of the secondary side of the evaporator needs to be considered in the process of obtaining the initial total displacement, and if the steam generator adopted by the pressurized water reactor nuclear power is a direct current steam generator, the heat carrying capacity of the secondary side of the evaporator does not need to be considered.
4. The design method for protection of the primary circuit system against overpressure in operating condition of pressurized water reactor as claimed in claim 2, wherein the initial total displacement of the pressurizer safety valve in the detailed demonstration analysis after overpressure analysis is directly taken from the maximum fluctuation flow of the pressurizer in the analysis.
5. The design method for the primary circuit system overpressure protection under pressurized water reactor operating condition as set forth in claim 1, wherein the process of accounting for the total displacement of the safety valve based on the deterministic analysis method in step S3 is as follows:
if the initial total displacement is substituted into the pressurized water reactor model, the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is met, the next step is carried out, if the requirement that the valve displacement is larger than or equal to the maximum fluctuation flow is not met, the change rule of the coolant volume of the reactor and the loop system along with the time after the reactor is shut down due to an accident is re-analyzed and obtained, and the change rule is substituted into the pressurized water reactor model to carry out overpressure analysis and valve volume analysis until the requirement that the valve displacement is larger than or equal to the.
6. The design method for protection of loop system against overpressure in operating condition of pressurized water reactor as claimed in claim 1, wherein in step S4, the protection signal and capacity of the pressurizer are obtained based on the principle of triggering reactor shutdown before the pressurizer is full of water, and the caliber of the surge pipe is obtained based on the principle of avoiding loop overpressure by ensuring timely expansion of the liquid in the loop.
7. The design method for protection of the primary circuit system against overpressure in a pressurized water reactor operating state as claimed in claim 6, wherein the specific process of obtaining the protection signal is as follows:
and when the overpressure criterion is not met, judging whether the pressure stabilizer is full of water before shutdown, if the overpressure criterion is not met, directly optimizing the pipe diameter of the fluctuation pipe, if the overpressure criterion is not met, indicating that the protection signal can be optimized, judging whether the optimization is carried out, if the optimization is required, substituting the protection signal into a pressurized water reactor model, determining the protection signal based on a determinacy analysis method, and if the optimization is not required, directly judging whether the capacity of the pressure stabilizer is optimized.
8. The design method for protection of the primary circuit system against overpressure in a pressurized water reactor operating state as claimed in claim 6, wherein the specific process of acquiring the capacity of the pressurizer is as follows:
and after judging that the protection signal does not need to be optimized, judging whether the capacity of the voltage stabilizer is optimized or not, if so, substituting the capacity of the voltage stabilizer into a pressurized water reactor model, determining the capacity of the voltage stabilizer based on a determinacy analysis method, and if not, directly optimizing the pipe diameter of the fluctuation pipe.
9. The design method for the primary circuit system overpressure protection in the pressurized water reactor operating state as claimed in claim 6, wherein the specific process of acquiring the pipe diameter of the surge pipe is as follows:
and substituting the pipe diameter of the surge pipe into the pressurized water reactor model, and determining the pipe diameter of the surge pipe based on a determinacy analysis method.
10. The design method for the primary circuit system overpressure protection under the pressurized water reactor operating condition as claimed in claim 1, wherein the specific process of step S5 is as follows:
on the premise that the safety valve meets single fault, probability theory analysis technology is adopted to analyze the probability and consequence of mistaken opening and blocking of the single-row valves, and the final number, upstream pipelines, downstream pipelines and isolation valve design of the safety valves are determined based on the probability theory analysis technology.
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