CN113436768A - Method for determining water level setting value of nuclear power plant voltage stabilizer - Google Patents
Method for determining water level setting value of nuclear power plant voltage stabilizer Download PDFInfo
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- CN113436768A CN113436768A CN202110697102.3A CN202110697102A CN113436768A CN 113436768 A CN113436768 A CN 113436768A CN 202110697102 A CN202110697102 A CN 202110697102A CN 113436768 A CN113436768 A CN 113436768A
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- voltage stabilizer
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
- G21D3/002—Core design; core simulations; core optimisation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention relates to the technical field of nuclear power plant operation technology and nuclear safety evaluation, in particular to a method for determining a water level setting value of a nuclear power plant voltage stabilizer, which comprises the following steps: acquiring geometric parameters of a reactor coolant system for determining a water level setting value of a voltage stabilizer; determining the minimum value of the water content of the voltage stabilizer before the steam cavity eliminating operation; determining a water level reference setting value of the voltage stabilizer; determining an error in the process of determining the water level reference setting value of the voltage stabilizer and calculating the water level setting value of the voltage stabilizer; and (4) analyzing and verifying the conformity of the water level setting value of the voltage stabilizer. The method determines the water level setting value of the voltage stabilizer involved in the upper head steam cavity elimination operation procedure based on the geometric parameters of the reactor coolant system and the instrument error, is simple, reasonable and accurate, guides an operator to correctly adjust and maintain the water level of the voltage stabilizer, and solves the technical problem that the electric heater of the voltage stabilizer is exposed and burnt in the existing upper head steam cavity elimination procedure of the nuclear power plant.
Description
Technical Field
The invention relates to the technical field of nuclear power plant operation technology and nuclear safety evaluation, in particular to a method for determining a water level setting value of a voltage stabilizer of a nuclear power plant.
Background
After the reactor of the pressurized water reactor nuclear power plant is stopped in an accident, if a main pump cannot run or start, a primary loop coolant system of the reactor is in a natural circulation cooling state. In the process of implementing natural circulation cooling depressurization according to an accident regulation instruction, if the temperature reduction rate of the coolant in the upper end enclosure area of the pressure vessel in the coolant system is lower than the corresponding pressure reduction rate, the supercooling degree of the coolant is reduced or even lost, and then the coolant is vaporized to form a vapor cavity, so that the liquid level of the pressure vessel is reduced. In order to prevent the liquid level of the pressure container from dropping below the upper surface of the heat pipe section due to continuous accumulation of steam in the upper head, an operator needs to perform an upper head steam cavity eliminating operation to ensure natural circulation cooling of the reactor.
As a closed loop system, in the process of eliminating the upper head steam cavity, fluid in the pressure stabilizer enters the pressure container through the fluctuation pipe to fill the disappeared steam cavity space. If the water level in the pressure stabilizer is low before the operation of eliminating the upper end enclosure steam cavity is executed, after the fluid of the pressure stabilizer flows into a loop, the disadvantage that an electric heater arranged in the pressure stabilizer is burnt due to exposure can occur. Therefore, an appropriate regulator initial water level setting must be given in the operating protocol involving header vapor chamber elimination in order to guide the operator in adjusting and maintaining the water level in the regulator in a timely manner to prevent this from occurring.
Disclosure of Invention
The invention aims to provide a method for determining a water level setting value of a nuclear power plant voltage stabilizer, which is used for determining the setting value of the initial water level of the voltage stabilizer in an upper end enclosure steam cavity elimination operation procedure and preventing the occurrence of severe conditions such as exposed burning of an electric heater arranged in the voltage stabilizer in the upper end enclosure steam cavity elimination process.
The invention is realized by the following technical scheme: the method comprises the following steps:
acquiring geometric parameters of a reactor coolant system for determining a water level setting value of a voltage stabilizer;
according to the geometric parameters of a reactor coolant system, determining the minimum value of the water content of a voltage stabilizer before the steam cavity eliminating operation, which corresponds to the state that an electric heater of the voltage stabilizer is buried by water after the steam cavity in an upper head of a nuclear power plant is eliminated;
determining a reference setting value of the corresponding water level of the pressure stabilizer according to the minimum value of the water filling amount of the pressure stabilizer before the steam cavity eliminating operation;
determining an error delta s in the process of determining the water level reference setting value of the voltage stabilizer, and calculating the water level setting value of the voltage stabilizer:
S＝Sn+Δs；
the conformity analysis of the water level setting value of the voltage stabilizer determines whether the water level setting value of the voltage stabilizer meets the standard that an electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation; and if the water level setting value of the voltage stabilizer does not meet the standard that the electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation, adjusting the water level reference setting value of the voltage stabilizer and continuing to perform conformance analysis until the water level setting value of the voltage stabilizer meets the standard.
Preferably, the geometric parameters are geometric parameters of a pressure vessel and a pressure stabilizer in a reactor coolant system.
Preferably, the method for obtaining the minimum value of the water content of the corresponding voltage stabilizer before the steam cavity eliminating operation after the electric heater of the voltage stabilizer is in a water-submerged state after the steam cavity in the upper head of the nuclear power plant is eliminated according to the geometric parameters of the reactor coolant system comprises the following steps: calculating and obtaining the internal volume V of the upper end enclosure of the pressure vessel according to the geometric structure parameters of the pressure vessel and the pressure stabilizer in the reactor coolant system0Volume V of the upper chamber above the upper surface of the heat pipe section1Minimum water volume V of the voltage stabilizer submerging the electric heater2，V0、V1、V2The minimum value of the water content of the pressure stabilizer before the steam cavity eliminating operation is obtained through the calculation of the sum of the three.
Preferably, the errors include measurement errors and calculation errors, the measurement errors include measurement errors of geometric parameters of a meter in the reactor coolant system, calibration errors of a measurement tool, structural measurement errors caused by geometric changes due to environmental conditions of the meter, and measurement errors of a sensor for liquid level sensing in the meter, the calculation errors are calculation method errors used in each calculation process, and the meter is a pressure vessel and a voltage stabilizer in the reactor coolant system.
Preferably, the measurement error and the calculation error both adopt a positive maximum error.
Preferably, the regulating regulator water level setting value is an increasing regulator water level reference setting value.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention provides a method for determining the initial water level setting value of a voltage stabilizer for eliminating an upper head steam cavity of a nuclear power plant, which is used for determining the water level setting value of the voltage stabilizer involved in an upper head steam cavity eliminating operation procedure based on the geometric parameters of a reactor coolant system and instrument errors. The method simply, reasonably and accurately determines the initial water level setting fixed value of the voltage stabilizer in the operation procedure related to the elimination of the upper end enclosure steam cavity, guides an operator to correctly adjust and maintain the water level of the voltage stabilizer, avoids the technical problem of exposed burning of an electric heater of the voltage stabilizer, and is successfully applied to the accident procedure set value development process of the China third-generation autonomous pressurized water reactor 'Hualong I'.
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 diagram of a pressure vessel and a pressure stabilizer;
FIG. 2 is a flow chart of a determination 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 the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not used as limitations of the present invention.
The water level setting value of a voltage stabilizer for eliminating an upper head steam cavity is taken as an example in the ' natural circulation cooling accident operation procedure with steam on the upper head ' of the China third-generation autonomous pressurized water reactor nuclear power plant (Hualong I) '.
As shown in figure 1, the connection relation between the pressure vessel of 'Hualong I' and the pressurizer is schematically shown, a reactor core is arranged in the pressure vessel, a heat pipe section of the pressure vessel is communicated with an outlet pipeline of the pressurizer, a cold pipe section is arranged on the pressure vessel and opposite to the heat pipe section, and an upper seal head and an upper cavity of the pressure vessel are arranged above the upper surface of the heat pipe section. In order to ensure that the finally determined water level setting value of the pressure stabilizer can meet the standard, the area above the upper surface of the heat pipe section of the pressure container is considered to be a steam cavity, and after the steam cavity is eliminated, the coolant in the pressure stabilizer flows into the pressure container through the fluctuation pipe to supplement the space where the steam in the steam cavity disappears through condensation. In order to ensure that the electric heater of the voltage stabilizer is always buried by water, the water content V of the voltage stabilizer before the steam cavity eliminating operation is more than or equal to the volume V of the upper end enclosure of the pressure container0Upper chamber volume V above upper surface of heat pipe section1And the minimum volume of water V required to submerge the electric heater in the pressurizer2The sum of three terms, i.e. V is more than or equal to V0+V1+V2. Therefore, the above V is calculated according to the geometric parameters of the reactor coolant system0、V1And V2The value is obtained.
In one embodiment, the first step of the method for determining the water level setting value of the voltage stabilizer is to determine and obtain the geometric parameters of the reactor coolant system for determining the water level setting value of the voltage stabilizer, wherein the geometric parameters are geometric parameters of the pressure vessel and the voltage stabilizer, such as length, width, height, wall thickness, arc length and the like, and can be obtained by combining conventional calculation by using measuring tools used in the field.
Secondly, calculating the volume V of the upper end enclosure of the pressure vessel according to the geometric parameters of the reactor coolant system0Volume V of the upper chamber above the upper surface of the heat pipe section1And the minimum volume of water V required to submerge the electric heater in the pressurizer2Calculating V0、V1、V2Adding to obtain V of 38.41m3V is the pressure stabilizer in the steam cavityWhen the water content in the voltage stabilizer is V, the electric heater of the voltage stabilizer is still in a state of being buried by water after the steam cavity is eliminated correspondingly.
And thirdly, calculating a reference setting value Sn of the water level of the voltage stabilizer corresponding to the moment according to the minimum value V of the water filling amount of the voltage stabilizer before the steam cavity eliminating operation, wherein Sn is the percentage of the water filling amount in the voltage stabilizer accounting for the full range of the water level of the voltage stabilizer when V is the water filling amount in the voltage stabilizer. For the 'Hualong I' nuclear power plant, under the thermal state calibration condition, the minimum value V of the water content of the pressure stabilizer before the steam cavity eliminating operation accounts for 79% of the full range of the water level of the pressure stabilizer, namely Sn is 79%.
And fourthly, because measurement errors, calibration errors of measurement tools and errors introduced by selection of a calculation method exist in the parameter measurement, calculation and other processes, in order to ensure that the finally obtained water level setting value of the voltage stabilizer meets the standard requirement that the electric heater can be buried after the steam chamber is eliminated, the influence of error factors on the water level setting value of the voltage stabilizer needs to be considered. The accident condition applied by the natural circulation cooling accident operation rule with steam on the upper end enclosure does not include the accident condition that high-energy fluid of a primary loop or a secondary loop system of a nuclear power plant is discharged to a containment, so that the instrument error delta s under the normal condition of the containment only needs to be considered. The instrument errors comprise a geometric structure parameter measurement error of an instrument in a reactor coolant system, a measurement tool calibration error, a structure measurement error caused by geometric structure change due to the environment condition of the instrument, and a sensor measurement error for liquid level induction in the instrument, and also comprise a calculation method error, wherein the instrument is a pressure container and a voltage stabilizer in the reactor coolant system, the errors are comprehensively considered, the instrument error of a water level setting value of the voltage stabilizer is equal to deltas plus 1.7%, and when the error value is obtained, the forward maximum value is preferably obtained.
Calculating the water level setting value S of the voltage stabilizer to Sn+ Δ s, i.e., 80.7% to 79% of the regulator water level setting value + 1.7%.
Fifthly, analyzing the conformity of the water level setting value of the voltage stabilizer to determine whether the water level setting value of the voltage stabilizer meets the standard that an electric heater of the voltage stabilizer is not exposed after the steam cavity eliminating operation; and if the water level setting value of the voltage stabilizer does not meet the standard that the electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation, increasing the water level reference setting value of the voltage stabilizer, repeating the fourth part and the fifth part until the water level setting value of the voltage stabilizer meets the standard, and if the water level setting value of the voltage stabilizer meets the standard that the electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation, determining the value as a set value of the initial water level of the voltage stabilizer, and adjusting and maintaining the water level in the voltage stabilizer by an operator according to the value.
In one embodiment, a computer transient system analysis program is adopted, a nuclear power plant calculation model is established through the transient system analysis program, the transient change process of the thermal parameters such as pressure and temperature of a loop system when an upper end enclosure steam cavity is eliminated is simulated, and the conformity of the determined water level setting value of the voltage stabilizer is verified and evaluated. Specifically, the transient system analysis program is the prior art, and the applicant has applied for and obtained registration the software copyright, which is named as: thermal hydraulic transient analysis software (TRANTH for short) V1.0, registration number 2015SR206402, registration date 2015, 10 months and 26 days, which is not detailed herein.
It will be understood by those skilled in the art that all or part of the steps of the above facts and methods can be implemented by hardware related to instructions of a program, and the related program or the program can be stored in a computer readable storage medium, and when executed, the program includes the following steps: corresponding method steps are introduced here, and the storage medium may be a ROM/RAM, a magnetic disk, an optical disk, etc.
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 (6)
1. A method for determining a water level setting value of a nuclear power plant voltage stabilizer is characterized by comprising the following steps:
acquiring geometric parameters of a reactor coolant system for determining a water level setting value of a voltage stabilizer;
according to the geometric parameters of a reactor coolant system, determining the minimum value of the water content of a voltage stabilizer before the steam cavity eliminating operation, which corresponds to the state that an electric heater of the voltage stabilizer is buried by water after the steam cavity in an upper head of a nuclear power plant is eliminated;
determining a reference setting value of the corresponding water level of the pressure stabilizer according to the minimum value of the water filling amount of the pressure stabilizer before the steam cavity eliminating operation;
determining an error delta s in the process of determining the water level reference setting value of the voltage stabilizer, and calculating the water level setting value of the voltage stabilizer: s ═ Sn+Δs；
The conformity analysis of the water level setting value of the voltage stabilizer determines whether the water level setting value of the voltage stabilizer meets the standard that an electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation; and if the water level setting value of the voltage stabilizer does not meet the standard that the electric heater of the voltage stabilizer is not exposed after the steam cavity elimination operation, adjusting the water level reference setting value of the voltage stabilizer and continuing to perform conformance analysis until the water level setting value of the voltage stabilizer meets the standard.
2. The method for determining the water level reference setting value of the nuclear power plant voltage stabilizer according to claim 1, characterized in that: the geometric parameters are geometric parameters of a pressure vessel and a voltage stabilizer in a reactor coolant system.
3. The method for determining the water level reference setting value of the nuclear power plant voltage stabilizer according to claim 1, characterized in that: according to the geometric parameters of a reactor coolant system, the method for acquiring the minimum value of the water content of the corresponding voltage stabilizer before the steam cavity eliminating operation when the electric heater of the voltage stabilizer is in a water-submerged state after the steam cavity in the upper head of the nuclear power plant is eliminated comprises the following steps: calculating and obtaining the internal volume V of the upper end enclosure of the pressure vessel according to the geometric structure parameters of the pressure vessel and the pressure stabilizer in the reactor coolant system0Volume V of the upper chamber above the upper surface of the heat pipe section1Is stableMinimum water volume V of the pressure vessel submerging the electric heater2，V0、V1、V2The minimum value of the water content of the pressure stabilizer before the steam cavity eliminating operation is obtained through the calculation of the sum of the three.
4. The method for determining the water level reference setting value of the nuclear power plant voltage stabilizer according to claim 1, characterized in that: the errors comprise measurement errors and calculation errors, the measurement errors comprise geometric structure parameter measurement errors of an instrument in a reactor coolant system, measurement tool calibration errors, structural measurement errors caused by geometric structure change due to environmental conditions where the instrument is located, and measurement errors of a sensor used for liquid level induction in the instrument, the calculation errors are calculation method errors used in each calculation process, and the instrument is a pressure container and a voltage stabilizer in the reactor coolant system.
5. The method for determining the water level reference setting value of the nuclear power plant voltage stabilizer according to claim 4, characterized in that: the measurement error and the calculation error both adopt the positive maximum error.
6. The method for determining the water level reference setting value of the nuclear power plant voltage stabilizer according to claim 1, characterized in that: and adjusting the water level setting value of the voltage stabilizer to increase the water level reference setting value of the voltage stabilizer.
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