CN107644133B - Method for calculating vibration scale factor of nuclear reactor core hanging basket - Google Patents
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Abstract
The invention discloses a method for calculating a vibration scale factor of a nuclear reactor core hanging basket, which comprises the following steps: establishing a three-dimensional physical calculation model of a nuclear reactor core; simulating first-order beam type vibration and second-order shell type vibration of a reactor core basket and first-order beam type vibration of a pressure vessel based on the established three-dimensional physical calculation model of the nuclear reactor core; based on a three-dimensional physical calculation model of the nuclear reactor core and a simulated vibration process, vibration scale factors of the reactor core basket and the pressure vessel under the vibration type are comprehensively obtained through combination of calculation, and a calculation method is provided for quantitative monitoring of the nuclear reactor core basket vibration.
Description
Technical Field
The invention relates to the field of nuclear reactor core research, in particular to a method for calculating a nuclear reactor core basket vibration scale factor.
Background
Under the thermal state full power running state of the reactor, a loop is in a high-temperature high-pressure strong radiation state, a vibration sensor cannot be directly installed on a hanging basket, and the vibration behavior of the reactor core hanging basket is difficult to directly monitor. The neutron fluence rate at the out-of-reactor detector can change along with the vibration of the core barrel, so that the vibration of the core barrel can be monitored through the neutron noise of the out-of-reactor detector. By analyzing neutron noise signals measured by the out-of-core detector of the nuclear measurement system, the vibration behavior of the reactor core hanging basket can be reduced.
To describe the vibration of the core barrel, a scale factor between the amplitude of the neutron noise in the reactor and the amplitude of the core barrel is introduced, which represents the influence of the unit amplitude of the vibration of the core barrel on the amplitude of the neutron noise. And (4) obtaining scale factors through calculation, and obtaining the amplitude of the reactor core hanging basket by combining with actually measured neutron noise signals.
The change in water layer thickness x when the basket beam vibrates is expressed by the differential dx. For a single beam type vibration effect, the result is a relative change in neutron flux:
dΦ/Φ＝-hdx (1)
since the current of the detector is proportional to the neutron flux Φ, so:
dΦ/Φ＝di/i＝-hdx (2)
in the formula:
di-the minute fluctuation value of the current caused by the fluctuation d Φ in the neutron flux;
i-the total current due to the neutron fluence rate at the detector, Φ (approximately proportional to the core nuclear power).
For other vibration modes, such as: the same applies to the first order beam-type vibration of the fuel assembly or the second and third order shell-type vibration of the basket.
From equation (1), a change in water layer thickness dx will cause a change in neutron flux d Φ to the outer detector. Then when the core barrel vibration displacement is deltax, the thickness of the water layer is changed deltax, and further the neutron flux is changed deltaphi, and the two physical quantities can be related by h, which is called the core barrel vibration scale factor. Setting the amplitude of the reactor core hanging basket as delta x, and calculating the neutron flux phi of the neutron detector outside the reactor before and after vibration0And phi1Is calculated by [ Delta ] [ phi ]/phi ] (phi)1-Φ0)/Φ0And obtaining the neutron flux change rate, and calculating the scale factor h according to the following formula.
h＝-ΔΦ/(Φ×Δx)
After the scale factor h is obtained, the vibration amplitude delta x of the reactor core hanging basket can be correspondingly calculated according to the variation value of the neutron fluence rate actually measured outside the reactor, so that the vibration condition of the reactor core hanging basket can be monitored in real time in the reactor operation process. Therefore, the vibration scale factor h needs to be calculated, and the calculation work is a key technology for quantitatively monitoring the vibration of the core barrel.
At present, no other unit develops the reactor core basket vibration scale factor calculation technology development based on neutron signal analysis or reports of related patent technologies in China. Therefore, an autonomy scale factor calculation method needs to be mastered according to the difference between the autonomous reactor core such as Hualong and the foreign reactor core, and capability is provided for quantitative monitoring of the Hualong reactor core hanging basket.
Disclosure of Invention
The invention aims to provide a method for calculating scale factors of the vibration amplitude of a nuclear reactor hanging basket along with the change of the signal value of an out-of-reactor neutron detector based on a probability theory algorithm, and provides a calculation method for the quantitative monitoring of the vibration of the nuclear reactor hanging basket.
In order to achieve the purpose, the application provides a nuclear reactor core basket vibration scale factor calculation method based on a probability theory algorithm, and the method comprises the following steps:
(1) physical model for inducing out-of-reactor neutron fluence rate change by reactor core hanging basket vibration
The vibration mode of the nuclear reactor core hanging basket is divided into first-order beam type vibration and second-order shell type vibration, and the first-order beam type vibration is mainly considered in the pressure vessel vibration mode. Through a high-precision three-dimensional physical model, a hanging basket flange is used as a swing fulcrum, and the hanging basket and an internal structure thereof swing towards the direction of a detector (or the direction opposite to the detector), so that first-order beam type vibration of the reactor core hanging basket is simulated; the pressure container swings towards the direction of the detector by taking the supporting point of the pressure container as a fulcrum, and first-order beam-shaped vibration of the pressure container is simulated; the flange and the bottom end of the reactor core hanging basket are used as fixed endpoints, the middle part of the hanging basket (only the hanging basket itself, not including the internal structure) vibrates towards the direction of the detector, and the second-order shell type vibration of the reactor core hanging basket is simulated.
By the simulation mode, the simulation of the vibration process under different vibration types and different vibration amplitudes is completed, and the vibration scale factors of the reactor core hanging basket and the pressure vessel under the vibration types are comprehensively obtained by combining calculation.
(2) Calculation model for out-of-reactor neutron fluence rate change caused by reactor core hanging basket vibration
Based on a probability theory calculation program, the nuclear reactor core is accurately modeled in three dimensions according to the design sizes and material parameters of fuel rods, control rods, burnable poison rods, control rod guide tubes, reactor core coamings and the like. And performing simplified modeling on related components at the upper part and the lower part of the reactor core in a modeling mode of uniformly mixing materials according to the design size. And performing accurate three-dimensional modeling according to design values of a reactor core radial plate, a hanging basket and a pressure vessel. And accurately modeling the neutron ionization chamber according to the actual position and the design size of the neutron ionization chamber in the out-of-pile power region. The modeling is mainly carried out aiming at the thermal state full power operation state of the reactor, and the moderator temperature close to the actual operation state is respectively adopted in the descending section and the reactor core of the reactor pressure vessel.
(3) Reactor core basket vibration scale factor calculation
Based on the calculation model and the vibration simulation method, a forward neutron transport calculation method based on a probability theory algorithm is adopted, and a probability theory calculation program is used for calculating neutron fluence rate values of the reactor core at the position of the out-of-reactor neutron detector under thermal state critical state and different amplitudes of the hanging basket. For each vibration mode, the neutron fluence rate calculated at 0 vibration amplitude is taken as phi0Taking the neutron fluence rate calculated at a plurality of specific vibration amplitudes Deltax as phi1And obtaining scale factor values of a plurality of vibration amplitudes, and averaging to obtain the final scale factor in the vibration mode. The distance between the out-of-pile detector and the reactor core is far, so that the counting convergence speed is low, and the calculation efficiency is low. Therefore, the variance is reduced by adopting the skill of geometric splitting, and the calculation efficiency is improved.
The calculation time and the statistical error of the calculation result are comprehensively considered, and the amplitude of the simulated vibration is set as small as possible, so that the calculation result meeting the required statistical error can be obtained in reasonable calculation time.
And calculating numerical values through the neutron fluence rates of the detectors with a plurality of vibration amplitudes to obtain vibration scale factors. And obtaining the theoretical deviation range of the vibration scale factor according to the statistical error of the neutron fluence rate calculation result.
One or more technical solutions provided by the present application have at least the following technical effects or advantages:
the calculation method provided by the invention is used for establishing a method for calculating the nuclear reactor hanging basket vibration scale factor by combining the calculation of the reactor hanging basket vibration scale factor through a physical model and a calculation model of reactor core hanging basket vibration-induced extrareactor neutron fluence rate change in the reactor core hanging basket vibration monitoring process of the conventional reactor, and provides capability for quantitative monitoring of the nuclear reactor hanging basket vibration of the nuclear power station reactor.
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 embodiments of the invention and together with the description serve to explain the principles of the invention;
FIG. 1 is a schematic diagram of a core barrel beam type vibration;
FIG. 2 is a schematic diagram of second order shell vibration of a core barrel;
FIG. 3 is a schematic diagram of the core barrel before vibration;
FIG. 4 is a schematic diagram showing the vibration state of the core barrel beam;
FIG. 5 is a schematic diagram showing the vibration state of the core barrel type;
the reactor comprises a pressure vessel 1, a reactor core upper component 2, a reactor core lower component 3, a reactor core upper component 4, a reactor core barrel 5, a reactor core upper component 6, a reactor core upper component 3, a reactor core lower component 4, a reactor core barrel 3, a reactor core barrel 6 and a reactor core lower component 6.
Detailed Description
The invention aims to provide a method for calculating scale factors of the vibration amplitude of a nuclear reactor hanging basket along with the change of the signal value of an out-of-reactor neutron detector based on a probability theory algorithm, and provides a calculation method for the quantitative monitoring of the vibration of the nuclear reactor hanging basket.
In order that the above objects, features and advantages of the present invention can be more clearly understood, a more particular description of the invention will be rendered by reference to the appended drawings. It should be noted that the embodiments and features of the embodiments of the present application may be combined with each other without conflicting with each other.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, however, the present invention may be practiced in other ways than those specifically described and thus the scope of the present invention is not limited by the specific embodiments disclosed below.
Referring to fig. 1-5, the calculation method of the present invention is implemented by the following steps:
1. modeling and verification of three-dimensional physical computation model
Based on a probability theory calculation program, the nuclear reactor core is accurately modeled in three dimensions according to the design sizes and material parameters of fuel rods, control rods, burnable poison rods, control rod guide tubes, reactor core coamings and the like. Firstly, unit modeling is completed according to the design size and material parameters of a fuel rod, a control rod, a burnable poison rod, a control rod guide tube and the like, the control rod is described as a cylinder, and the streamline shape at the bottom is omitted. On the basis, various fuel assembly modeling is completed according to specific size parameters of the fuel assemblies. The pressure and temperature of the moderator in the reactor core adopt the rated working pressure and the average inlet and outlet temperature when the reactor is in hot full-power operation (or according to the result of thermal coupling analysis, the pressure and temperature of the moderator are accurately described in a partition mode).
The moderator temperature pressure value in the reactor core hanging basket adopts the rated working pressure and the average inlet and outlet temperature when the reactor is in the hot full-power operation, and the moderator temperature pressure outside the reactor core hanging basket adopts the rated working pressure and the reactor core inlet temperature when the reactor is in the hot full-power operation. And accurately modeling the neutron ionization chamber according to the actual position and the design size of the neutron ionization chamber in the out-of-pile power region, setting a neutron fluence rate statistical card in the volume of the ionization chamber, and calculating the neutron fluence rate at the neutron ionization chamber.
Based on the three-dimensional modeling, k is carried out according to the actually measured critical rod position and boron concentration of the reactoreffAnd (4) calculating, namely verifying the accuracy of the model, wherein the deviation of the calculation result and 1 is within 5 per mill.
2. Reactor core basket and pressure vessel vibration simulation
The vibration mode of the nuclear reactor core hanging basket is divided into first-order beam type vibration and second-order shell type vibration, and the first-order beam type vibration is mainly considered in the pressure vessel vibration mode. Through a high-precision three-dimensional physical model, a hanging basket flange is used as a swing fulcrum, and the hanging basket and an internal structure thereof swing towards the direction of a detector (or the direction opposite to the detector), so that first-order beam type vibration of the reactor core hanging basket is simulated; the pressure container swings towards the direction of the detector by taking the supporting point of the pressure container as a fulcrum, and first-order beam-shaped vibration of the pressure container is simulated; the flange and the bottom end of the reactor core hanging basket are used as fixed endpoints, the middle part of the hanging basket (only the hanging basket itself, not including the internal structure) vibrates towards the direction of the detector, and the second-order shell type vibration of the reactor core hanging basket is simulated.
By the simulation mode, the simulation of the vibration process under different vibration types and different vibration amplitudes is completed, and the vibration scale factors of the reactor core hanging basket and the pressure vessel under the vibration types are comprehensively obtained by combining calculation.
3. Scale factor calculation based on probability theory algorithm
When the core barrel vibration displacement is delta x, the thickness of a water layer is changed by delta x, and then the neutron flux is changed by delta phi, the two physical quantities can be related by h, and the h is called a core barrel vibration scale factor. Setting the amplitude of the reactor core hanging basket as delta x, and calculating the neutron flux phi of the neutron detector outside the reactor before and after vibration0And phi1Is calculated by [ Delta ] [ phi ]/phi ] (phi)1-Φ0)/Φ0And obtaining the neutron flux change rate, and calculating the scale factor h according to the following formula.
h＝-ΔΦ/(Φ×Δx)
Based on the accurate three-dimensional reactor physical calculation model and the vibration simulation method, a forward neutron transport calculation method based on a probability theory algorithm is adopted, and a probability theory calculation program is used for calculating neutron fluence rate values of the reactor core at the position of the out-of-reactor neutron detector under a thermal state critical state and when hanging baskets have different amplitudes.
The distance between the out-of-pile detector and the reactor core is far, so that the counting convergence speed is low, and the calculation efficiency is low. Therefore, the variance is reduced by adopting the skill of geometric splitting, and the calculation efficiency is improved. From the core, the neutron importance in adjacent cells is increased outwards layer by a suitable factor (the factor between each adjacent cell may be different) until inside the external detector volume. And performing critical calculation, wherein the statistical error of the neutron fluence rate calculation result at the detector is lower than 1% by reasonably setting the neutron number and the total algebra of each generation.
The calculation time and the statistical error of the calculation result are comprehensively considered, and the amplitude of the simulated vibration is set as small as possible, so that the calculation result meeting the required statistical error can be obtained in reasonable calculation time.
And calculating numerical values through the neutron fluence rates of the detectors with a plurality of vibration amplitudes to obtain vibration scale factors. And obtaining the theoretical deviation range of the vibration scale factor according to the statistical error of the neutron fluence rate calculation result.
While preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. Therefore, it is intended that the appended claims be interpreted as including preferred embodiments and all such alterations and modifications as fall within the scope of the invention.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (7)
1. A nuclear reactor core basket vibration scale factor calculation method is characterized by comprising the following steps:
establishing a three-dimensional physical calculation model of a nuclear reactor core;
simulating first-order beam type vibration and second-order shell type vibration of a reactor core basket and first-order beam type vibration of a pressure vessel based on the established three-dimensional physical calculation model of the nuclear reactor core;
based on a three-dimensional physical calculation model of the nuclear reactor core and a simulated vibration process, comprehensively obtaining vibration scale factors of the reactor core hanging basket and the pressure vessel under the vibration type by combining calculation;
based on a three-dimensional physical calculation model of a nuclear reactor core and a simulated vibration process, a forward neutron transport calculation method based on a probability theory method is adopted, a probability theory calculation program is used for calculating neutron fluence rate values of the reactor core at a neutron detector outside the reactor in a thermal critical state and under different amplitudes of a hanging basket, and then scale factor values of a plurality of vibration amplitudes are obtained and then the scale factors under the vibration mode are averagely calculated;
the scale factor calculation based on the probability theory algorithm specifically comprises the following steps:
when the vibration displacement of the reactor core hanging basket is delta x, the thickness change delta x of the water layer is caused, and further the neutron flux change delta phi is caused, wherein h is a reactor core hanging basket vibration scale factor; setting the amplitude of the reactor core hanging basket as delta x, and calculating the neutron flux phi of the neutron detector outside the reactor before and after vibration0And phi1Is calculated by [ Delta ] [ phi ]/phi ] (phi)1-Φ0)/Φ0Obtaining the neutron flux change rate, and calculating the scale factor h according to the following formula:
h＝-ΔΦ/(Φ×Δx)。
2. the method for calculating the scale factor of the nuclear reactor core basket vibration according to claim 1, wherein the establishing of the three-dimensional physical calculation model of the nuclear reactor core specifically comprises:
based on a probability theory calculation program, performing three-dimensional modeling on the nuclear reactor core according to the design size and material parameters of the nuclear reactor core components;
modeling related components on the upper part and the lower part of the reactor core in a modeling mode of uniformly mixing materials according to the design size;
performing three-dimensional modeling according to design values of a reactor core radial plate, a hanging basket and a pressure vessel;
modeling the neutron ionization chamber according to the actual position and the design size of the neutron ionization chamber in the out-of-pile power region;
modeling is carried out aiming at the thermal state full power operation state of the reactor, and moderator temperatures in actual operation states are respectively adopted in the descending section and the reactor core of the reactor pressure vessel.
3. The method for calculating the scale factor of the vibration of the nuclear reactor core basket according to claim 1, wherein the basket and the internal structure swing towards the direction of a detector or the opposite direction of the detector by taking a basket flange as a swing fulcrum through a three-dimensional physical calculation model of the nuclear reactor core, so as to simulate the first-order beam type vibration of the core basket; the pressure container swings towards the direction of the detector by taking the supporting point of the pressure container as a fulcrum, and first-order beam-shaped vibration of the pressure container is simulated; the flange and the bottom end of the reactor core hanging basket are used as fixed endpoints, and the middle part of the hanging basket vibrates towards the direction of the detector to simulate the vibration of the second-order shell of the reactor core hanging basket.
4. The method of calculating the nuclear reactor core barrel vibration scale factor according to claim 1, wherein the neutron fluence rate calculated at a vibration amplitude of 0 is regarded as Φ for each vibration mode0Taking the neutron fluence rate calculated at a plurality of specific vibration amplitudes Deltax as phi1And obtaining scale factor values of a plurality of vibration amplitudes, and averaging to obtain the final scale factor in the vibration mode.
5. The method for calculating the scale factor of the nuclear reactor core basket vibration of claim 1, wherein k is performed according to the actually measured critical rod position and boron concentration of the reactor after the three-dimensional physical calculation model of the nuclear reactor core is establishedeffAnd calculating and verifying the accuracy of the model.
6. The method for calculating the vibration scale factor of the core barrel of the nuclear reactor as claimed in claim 2, wherein the temperature and pressure values of the moderator inside the core barrel adopt the rated working pressure and the average inlet-outlet temperature when the reactor is in the hot full power operation, and the temperature and pressure values of the moderator outside the core barrel adopt the rated working pressure and the inlet-outlet temperature when the reactor is in the hot full power operation.
7. The method for calculating the vibration scale factor of the nuclear reactor core barrel according to claim 1, wherein the method comprises the steps of starting from the core, increasing the importance of neutrons in adjacent grid elements layer by layer outwards by preset times until a detector outside the core, performing critical calculation, and reducing the statistical error of the calculation result of the neutron fluence rate at the detector by setting the neutron number and the total algebra of each generation.
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| CN1153573A (en) * | 1994-07-21 | 1997-07-02 | 西屋电气公司 | Method and system for accurately calculating PWR power from excore detector currents |
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