KR101403347B1 - Apparatus of steam generator tube plugging analysis using pressure drop and heat-transfer performance - Google Patents

Abstract

More particularly, the present invention relates to an apparatus and a method for converting a steam generator tubular sounding rate into consideration of pressure drop and heat transfer performance. More particularly, the present invention relates to an apparatus and method for converting a steam generator tubular sounding rate into a steam generator,
The steam generator kinetic energy conversion device 1 considering the pressure drop and the heat transfer performance of the present invention includes a steam generator inlet nozzle 180, a steam generator inside and a steam generator (not shown) for detecting at least one of temperature, pressure, A sensor unit 10 including at least one of a temperature, a pressure, and a flow rate sensor provided at a position on the side of the outlet nozzle 182; and a sensor unit 10 for receiving a measurement signal of the sensor unit 10, And a control unit (30) for calculating a diaphragm sound ratio conversion coefficient by using the descent and heat transfer performance and determining a diaphragm tone ratio, the apparatus comprising: The control unit (30) controls the temperature of the steam generator inlet nozzle side measured by the sensor unit (10), the pressure, the flow rate information, and the temperature information of the outlet nozzle side, The pressure drop ratio RP _S is calculated and the standard value R _P (Y) of the pressure drop of the tubular membrane as expressed by the set gaiter (Y) is calculated, and the slip rate X corresponding to the tubular tone Y ratio of calculated to sleeving ratio (X / Y), tube plugging by defining (S60) a quantity and sleeving quantity calculates the pressure drop ratio (RP _P (Y)) for the gwanmak swing (Y), gwanmak (SPR _{? P} ), which is a conversion coefficient for the reference gut feeling, is calculated using the pressure drop ratio (RP _P (Y)) to the tone Y and the overall heat transfer Q is calculated, the charge of soft transfer (Q) heat transfer performance (UA) blocking the calculations, by using the calculated heat transfer performance (UA) tube blocking tube before and after the heat transfer performance reference value (H _P) from total And, using the calculated the heat transfer performance (UA) calculating the sleeving heat transfer performance reference value (H _S) and after sleeving around, said pipe preventing heat transfer performance reference value (H _P) and said sleeving heat transfer performance reference value (H _S ) a, and calculating the sleeving gwanmak temperament scale factor (SPR _h before and after), the gwanmak temperament scale factor (SPR _h) a controller (37 for determining the sleeving gwanmak swing by using a heat transfer performance (UA) using ).

Description

BACKGROUND OF THE INVENTION 1. Field of the Invention [0001] The present invention relates to an apparatus for converting a steam generator to a steam turbine,

The present invention relates to a method for converting a tubular sound and a tubular sound into a steam generator of a nuclear reactor, and more particularly, to a steam generator tubular sound conversion apparatus considering pressure drop and heat transfer performance.

Generally, as shown in FIG. 1, a pressurized water type nuclear power generation system includes a reactor 200 for generating a chain reaction, a primary coolant system 300 for extracting heat generated in a core of the reactor 200, A steam generator 100 for vaporizing the cooling water of the secondary coolant system by the heat transmitted from the system 300, and a turbine 400 driven by receiving the generated steam. 1 and 2, the steam generator 100 is a heat exchanger made up of a heat transfer pipe 162. The steam generator 100 includes a high-temperature high-pressure primary cooling water containing radioactivity inside and a secondary cooling water outside the heat transfer pipe 162 It is a device that generates heat by causing heat exchange between cooling water. Specifically, the steam generator 100 includes a steam outlet 120, a moisture separator 140, a heat transfer pipe 162, a heat transfer pipe support 164, a heat transfer pipe sheet 166, an inlet water chamber 170, an outlet water chamber 172 And an outer cell 190 and the like.

According to the steam generator 100 configured as described above, the primary cooling water containing the radioactive material discharged from the reactor 200 of FIG. 1 during operation flows into the inlet water chamber 170 through the inlet nozzle 180, 166 through the heat transfer pipe 162 and returns to the outlet water chamber 172 through the heat transfer pipe 162 and enters the reactor 200 through the outlet nozzle 182. [ At this time, the pure secondary cooling water flows through the inflow nozzle 150 and generates steam by heat transferred from the outer surface of the heat transfer pipe 162 through the heat transfer pipe 162. The steam thus generated is sent to the turbine 400 through the steam outlet 120.

However, during the operation of the steam generator 100, leakage of heat may occur due to defects such as stress corrosion cracks during the operation of the steam generator 100. In such a case, serious problems such as radioactive leakage may occur. Therefore, The normal operation of the engine 100 is enabled.

Various techniques are being developed as a repair method for a heat transfer pipe. One of such techniques is a sleeving technique in which a sleeve having a smaller diameter and a proper length than a defect or a damaged heat transfer tube is attached to a damaged position in the heat transfer tube and then the sleeve is expanded to precisely weld the inner circumferential surface of the defective portion. Sleeve technology is divided into expansion expansion, roll expansion, and hydraulic expansion according to the sleeve expansion method.

Since the explosion expansion method is not easy to control the expansion rate and the explosion residue remains after the expansion, it requires a post-process such as cleaning.

In addition, the roll expanding method is a technique of mechanically expanding the sleeve, and there is a problem that residual stress remains in the expanded portion of the sleeve. On the other hand, the hydraulic expansion method has advantages such that the expansion ratio of the heat transfer tube can be easily controlled through precise control of the hydraulic pressure, and there is no residue after the expansion, so that there is almost no need for the post-processing.

In the case of performing the sleeving using the above-described pros and cons of the sleeving method, it is necessary to know the permissible gauge tone of the specific steam generator to determine the design basis safety analysis range according to the plugging.

In other words, if the correct tubular tone is not calculated by the sleeving, it is difficult to evaluate the performance degradation of the steam generator, and the influence of the steam generator sleeving is not recognized. There is a great possibility that the design basis accident safety analysis due to the influence of the steam generator is to be re-executed on the assumption of excessive conservatism.

However, the calculation method of the diaphragm sound ratio conversion applied to the mid-term generator of the nuclear power plant currently in use is a simple physical calculation comparing the pressure drop and the heat transfer performance of the complex and correctable steam generator considering the material and characteristic thermal conductivity of the steam generator tube. The analysis of the tonometry used, the conversion and the alternative calculation method are not presented.

Therefore, there is a need to convert the correct tubular temperament of a specific steam generator with the slew rate.

SUMMARY OF THE INVENTION Accordingly, the present invention has been made to solve the above problems of the prior art, and it is an object of the present invention to provide a heat transfer tube of a steam generator, It is an object of the present invention to provide a steam generator kinematic rate conversion apparatus which takes into consideration the pressure drop and the heat transfer performance that facilitate analysis and conversion of the tubular sounding rate according to the slinging performed by sleeve intubation so as to reflect performance, .

In order to accomplish the above object, the present invention provides a steam generator kinematic rate conversion apparatus (1) which takes into consideration the pressure drop and heat transfer performance of the present invention, a steam generator inlet nozzle (180) for detecting at least one of temperature, pressure, A sensor unit 10 including at least one of a temperature, a pressure, and a flow rate sensor installed at a position inside the steam generator and on the side of the steam generator outlet nozzle 182; And a control unit (30) for calculating a diaphragm sound ratio after calculating the diaphragm sound ratio conversion coefficient using the pressure drop before and after the sleeping and the heat transfer performance, and a control unit (30) ; The control unit (30) controls the temperature of the steam generator inlet nozzle side measured by the sensor unit (10), the pressure, the flow rate information, and the temperature information of the outlet nozzle side, The pressure drop ratio RP _S is calculated and the standard value R _P (Y) of the pressure drop of the tubular membrane as expressed by the set gaiter (Y) is calculated, and the slip rate X corresponding to the tubular tone Y ratio of calculated to sleeving ratio (X / Y), tube plugging by defining (S60) a quantity and sleeving quantity calculates the pressure drop ratio (RP _P (Y)) for the gwanmak swing (Y), gwanmak (SPR _{? P} ), which is a conversion coefficient for the reference gut feeling, is calculated using the pressure drop ratio (RP _P (Y)) to the tone Y and the overall heat transfer Q is calculated, the charge of soft transfer (Q) heat transfer performance (UA) blocking the calculations, by using the calculated heat transfer performance (UA) tube blocking tube before and after the heat transfer performance reference value (H _P) from total And, using the calculated the heat transfer performance (UA) calculating the sleeving heat transfer performance reference value (H _S) and after sleeving around, said pipe preventing heat transfer performance reference value (H _P) and said sleeving heat transfer performance reference value (H _S ) a, and calculating the sleeving gwanmak temperament scale factor (SPR _h before and after), the gwanmak temperament scale factor (SPR _h) a controller (37 for determining the sleeving gwanmak swing by using a heat transfer performance (UA) using ).

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As described above, the present invention can correct the heat conduction material and the heat conduction characteristics which are not calculated by the conversion of the diaphragm sound due to the simple pressure drop between the inlet and outlet of the steam generator due to the sleeving of the steam generator heat transfer tube, From the overall heat transfer coefficient, the calculation of standard values of heat transfer performance before and after sleeving provides the effect of correcting thermodynamically and effectively the simple pressure drop calculation.

In addition, the present invention can accurately evaluate the performance of a steam generator by precisely correcting the conversion efficiency of the steam generator tube in consideration of the heat transfer performance, It is possible to efficiently improve and confirm the secondary operation health by the sleeving.

In addition, the present invention reflects the pressure drop and heat transfer performance at the time of conversion of the diaphragm rate, thereby making it possible to utilize the design data used in the operation of the nuclear power plant to utilize the thermal hydraulic phenomenon related to the operation of the power plant as a whole, Thereby providing an effect of significantly improving power plant design and operation efficiency.

In addition, the present invention reflects the pressure drop and heat transfer performance at the time of conversion of the diaphragm tone, thereby enabling accurate calculation of the diaphragm sound before and after the sleeping, thereby correcting the slew rate to the diaphragm tone, It is possible to quickly determine whether or not the acceptance criterion satisfies the acceptance criterion.

Therefore, the present invention not only reduces the cost of design-basis accident safety analysis that must be performed unnecessarily, but also significantly improves the utilization rate of nuclear power plants by greatly reducing the time required for safety analysis review and license approval.

1 is a schematic view of a conventional light-water reactor type nuclear power plant,
FIG. 2 is a detailed sectional view of the steam generator of FIG. 1,
FIG. 3 is a schematic view showing a schematic installation state of a steam generator kinetic hunting converter 1 (hereinafter, referred to as a hunting hunter's ratio converter 1) in consideration of the pressure drop and the heat transfer performance according to the embodiment of the present invention,
4 is a view showing a pressure, a flow rate, and a temperature measurement position for conversion of a diaphragm tone in the steam generator 100,
FIG. 5 is a flowchart showing the processing procedure of the method for converting the steam generator's diaphragm rate considering the pressure drop and heat transfer performance of the present invention.

Hereinafter, the present invention will be described in more detail with reference to the accompanying drawings showing embodiments of the present invention.

FIG. 3 is a schematic installation state diagram of a steam generator kinetic energy conversion device 1 (hereinafter, referred to as a haptic sound ratio conversion device 1) taking into consideration the pressure drop and heat transfer performance according to the embodiment of the present invention. 100, the pressure, flow rate, and temperature measurement positions for conversion of the diathermic tone are shown in detail.

3, the apparatus 1 includes a pressure sensor for measuring the temperature and flow rate of the primary cooling water and the secondary cooling water of the steam generator 100 and the heat transfer performance of the heat transfer pipe 162 And a control unit (30) for receiving the measured temperature, flow rate, and pressure information of sensors provided in the sensor unit (10) and then determining the tone of the diaphragm by converting the diaphragm tone rate .

As shown in FIG. 3, the sensor unit 10 includes a pressure sensor for detecting heat transfer characteristics, a flow sensor for detecting flow rate fluctuation, and temperature sensors for temperature fluctuation detection.

Specifically, the temperature sensors include a first temperature sensor 11 installed in the reactor hot leg 310 to measure the initial temperature of the primary cooling water flowing into the steam generator 100, And a third flow rate sensor 21 installed at the outlet nozzle shrinkage portion f on the outlet nozzle 182 side for measuring the temperature of the primary cooling water.

The pressure sensor 13 is installed in the reactor hot leg 310 to measure the initial pressure of the primary cooling water flowing into the steam generator 100.

3 and 4 the flow sensors are connected to a first flow sensor (not shown) installed in the reactor hot leg 310 connected to the inlet pipe 320 to measure the initial pressure of the inlet nozzle 180 of the steam generator 100 A second flow rate sensor 19 installed at the heat transfer pipe inlet shrinkage portion b to measure the flow rate of the refrigerant in the refrigerating cycle of the steam generator 100, And a third flow sensor 21 provided at the portion f.

The control unit 30 includes a display unit 31 for outputting a process for converting the tone of a gut member, an interface unit 33 for providing a user interface, and sensors or external devices of the sensor units 10 And a controller 37 for converting and determining the gauge tone rate in consideration of the pressure change and the heat transfer performance using the temperature, pressure, and flow rate information collected from the sensors of the sensor units 10, do.

The display unit 31 is a display device such as a general LCD, a PDP, and an electroluminescent sheet, and is configured to visually display a process of converting the tone of a diaphragm, a result, and user control commands.

The interface unit 33 includes a key input unit and the like so that the user can set values and input control commands. The interface unit 33 may not be implemented when the display unit 31 is implemented by a touch pad method .

The communication unit 35 provides sensors of the sensor unit 10 or a communication interface for performing communication with the outside.

The control unit (37) (RP _S ) between the inlet and outlet nozzles using the temperature, pressure, and flow rate information on the steam generator inlet nozzle side measured by the sensor unit 10 and the temperature information on the outlet nozzle side, And calculates a standard value R _P (Y) of the pressure drop standardized as the set gut tone Y and calculates the slew rate X corresponding to the ratio of the sleeving rate X corresponding to the meniscus tone Y / Y), calculates the pressure drop ratio RP _P (Y) with respect to the tubular tone R (Y) by defining the amount of tubing sounding and the amount of slewing (S60) (Q) is calculated by calculating the reference gutta-tone conversion factor (SPR _{? P} ), which is a conversion coefficient for the reference gutta phoneme, using the descent ratio (RP _P (Y) from the calculated heat transfer performance (UA), and by using the calculated the heat transfer performance (UA) tube blocking calculate the blocking tube heat transfer performance reference value _(P H) before and after and calculates Using a group heat transfer performance (UA) sleeving heat transfer performance reference value (H _S) for calculation, and the pipe blocking the heat transfer performance reference value (H _P) and said sleeving heat transfer performance reference value (H _S) and after sleeving before using calculating the dew gwanmak temperament scale factor after the living former (SPR _h) and using the gwanmak temperament scale factor (SPR _h) and the heat transfer performance (UA) is configured to determine the gwanmak rhythms of sleeving.

Hereinafter, the features of each of the above-described configurations and the processing procedure of the controller 31 will be described in detail.

- Method of measuring pressure drop

As shown in FIG. 3, the hot leg 310 on the side of the inflow pipe 320 through the reactor core 200A is used to measure the pressure drop before and after the sleeving for the calculation of the diaphragm hue conversion factor (SPR _h ) The initial pressure is measured by the pressure sensor 13 provided in the pressure sensor. The pressure sensor 13 is a pressure-type pressure sensor that generates deformation of a sensor when a volume and a pressure fluctuation of the fluid occurs, generates a current according to the degree of deformation, converts the current into a pressure, .

The pressure measured by the pressure sensor 13 becomes the initial pressure of the piping flowing at the position A, that is, the primary cooling water at the inlet of the steam generator. The initial pressure measured here is the initial pressure of the primary cooling water flowing through the nozzle inlet expansion part (a) and the heat transfer pipe inlet expansion part (b) at the steam generator inlet side, and the initial pressure at this time is the D flow path, that is, (B), the heat transfer pipe friction loss portion (c), the bending portion friction loss portion (d), the heat transfer pipe outlet expanding portion (e), the outlet nozzle shrinking portion The initial pressure of the primary cooling water in the first cooling water.

These initial pressures correspond to the inlet nozzle expanding portion a, the heat transfer pipe inlet reducing portion b, the heat transfer tube friction loss portion c, the bending portion friction loss portion d, the heat transfer pipe outlet expanding portion e, As the flow passes through the reduced portion (f), it experiences an area change due to the sleeves. The flow rate variation in the sleeving can be calculated by dividing the initial flow rate (A) by the modified cross-sectional area of the sleeving. In other words, since Bernoulli's theorem gives rise to a pressure change proportional to the flow rate variation, the differential pressure difference is the pressure difference at this time. The final differential pressure is obtained by calculating the pressure at the flow rate (A) and the pressure at the flow rate (C), and then calculating the difference. The difference between the differential pressure calculated in this way before being sleeved and the differential pressure calculated in this way after being sleeved is the pressure drop before and after slewing.

The measurements and calculations used to calculate the pressure drop before and after steam generator slip using the Bernoulli equation (equation) and the pressure sensor are as follows.

The initial pressure for the basic calculation is measured by the pressure sensor 13 of the hot leg 310 of FIG.

When the initial pressure is measured, the Bernoulli equation (P _P + ΡV _P ^2/2 = constant, ρ: density of the fluid, V _P: the speed of fluid) was used with a flow rate (A), yuraeng (D), the flow rate (S) (flow rate of the sleeving area in Fig. 3), When calculating the flow rate for each area at the measuring point of the flow (C), since the Bernoulli equation ρV _P ^2/2 term variation at each point, and the respective points a pressure change of the accompanying accordingly, a, D, C of the angular position The pressures of the flow rate (A), the flow rate (D) and the flow rate (C) are obtained, and the total pressure drop of the steam generator to be obtained in FIG. In order to calculate the pressure drop before and after the sleeving, when the sleeving is not performed, the initial pressure is obtained from the pressure sensor 13 of the reactor hot leg 310 of FIG. 3, and the initial pressure is substituted into the Bernoulli equation , The pressure fluctuation is calculated from the flow rate per unit area at the point A, and the pressure fluctuation to the point C is added to obtain the total pressure drop of the steam generator inlet-outlet nozzles 180, 182 before the sleeving. As a result, the total pressure drop between the inlet and outlet nozzles 180, 182 before and after the sleeving is calculated to calculate the difference between the total pressure drop across the sleeve and the total pressure drop after the sleeving.

- Heat transfer performance standard value and method of measurement

4 and 5, a method for obtaining the standard values of the heat transfer performance including the standardized values of the slewing heat transfer performance H _S and the duct heat transfer performance standard values H _P is as shown in FIG. 3, Is performed by the second temperature sensor (23). 3, the first temperature sensor 11 measures the temperature of the primary cooling water from the hot leg 310 side and the second temperature sensor 23 measures the primary cooling water temperature of the cold leg 340. [

Therefore, in FIG. 4 before the sleeving, the inlet nozzle expanding portion (a), the heat transfer pipe inlet reducing portion (b), the heat cutting tube friction loss portion (c), the bending portion friction loss portion (d), the heat transfer pipe outlet expanding portion The heat transfer performance of the nozzle shrinkage portion f is determined such that the flow rate of each of the flow rate A, the flow rate B and the flow rate C at the points A, D, The heat transfer area at each flow rate point is calculated by dividing the coolant temperature by the temperature of the first temperature sensor 11 of the hot leg 310 of FIG. When the calculated heat transfer area is calculated by dividing the calculated heat transfer area by the cross sectional area of flow at each flow point with the temperature measured by the second temperature sensor 23 at the side of the cold leg 340, The heat transfer area between the outlet nozzle 180 and the outlet nozzle 182 is calculated. When the heat transfer area is calculated based on the pre-slewing condition and the post-sleeving condition, the heat transfer area before and after the slewing is calculated and the standard values of the heat transfer performance shown in FIG. 4 are calculated. This is because the calculated heat transfer performance standard values are changed only by the heat transfer area before and after the sleeving.

The first temperature sensor 11 and the second temperature sensor 23 used for calculating the heat transfer performance may be a thermometer temperature gauge. It is preferable to use a platinum-coated RTD having the highest accuracy among the existing temperature sensors and having the highest linearity of the resistance value according to the ordinary temperature, using the principle that the current resistance value of the metal varies according to the temperature.

- How to measure the flow rate

The flowmeter necessary for the calculation process of Figs. 4 and 5 is composed of the inlet nozzle expanding portion a, the heat transfer pipe inlet reducing portion b, the heat transfer pipe friction loss portion c, the bending portion friction loss portion d, 3 corresponding to the outlet expanding portion e, the outlet nozzle shrinking portion f, the sleeve inlet shrinkage portion g, the sleeve friction loss portion h, and the sleeve outlet swelling portion i, Measurements are made at the first position, point C, of the point. The first flow sensor 15 installed in the hot leg 310 initially measured is artificially installed in the pipe as an Oriffice type. The first flow sensor 15 detects a pressure change by detecting a change in a flow rate due to a cross-sectional area change of a flowing fluid according to Bernoulli's equation. Since the flow rate is measured by interpreting the Bernoulli equation, the flow rate is inversely proportional to the pressure change in the orifice.

FIG. 5 is a flowchart showing the processing procedure of the method for converting the steam generator's diaphragm rate considering the pressure drop and heat transfer performance of the present invention.

Hereinafter, a processing procedure of the method for converting the gauge tone of the present invention will be described with reference to FIGS. 3 to 5. FIG.

The method for converting a tone of a gauntlet according to the present invention includes calculating a standard sliping pressure drop value (S10), calculating a slipping pressure drop ratio (S20), calculating a standardized pressure drop value (S40) A ratio calculation step S50, a pressure drop ratio calculation step S70, a reference gut conversion factor calculation step S80, an overall heat transfer calculation step S90, a heat transfer performance calculation step S100, A heat transfer performance standard value calculation process S110, a slewing heat transfer performance standard value calculation process S120, a gauge hue conversion factor calculation process S130, and a gauge tone determination process S140.

The respective steps of the method for converting the temperament of the gutters of the present invention described above are carried out by the control unit 30 of Fig. 3 in such a manner that the first temperature sensor 11, the pressure sensor 13, the first flow sensor 15, The second flow sensor 19, the third flow sensor 21 and the second temperature sensor 23 to process each calculation process.

The formulas, constants and variables for carrying out the above-described processing are as follows.

A _P : Flow cross-sectional area after sleeving

_P0 : Flow passage area before sleeving

A: Heat transfer area

h _i : inner film thermal coefficient

h _{O :} outer film heat transfer coefficient

T _P : Reactor coolant temperature

T _W1 : Temperature inside the heat transfer pipe,

k is the heat transfer coefficient, A is the heat transfer area

Δx is the thickness of the sleeving pipe

T _W2 : Temperature outside the heat transfer pipe

R _i : Internal dura thermal resistance

R _W : Thermal pipe resistance

R _O : external dura thermal resistance

1 / (R _i + R _W + R _O ): total thermal resistance

H _P : Standard value of pipe heating heat transfer performance

H _P (0.01) = U _P A _P / U _{P 0} A _{P 0} = 0.99

H _S : standard value of heat transfer performance

_S H (0.01) = U _S A _S / A U _{S0 S0}

N: Heat pipe number

N ₀ : the number of conduit pipes that have been blocked

XN: Number of sleeves

YN: Pore volume

Q: Overall heat transfer

ΔP _S0 : Pressure drop between inlet and outlet nozzles before steaming

ΔP _S : Pressure drop between inlet and outlet nozzles of the steam generator after sleeving

△ P _P : Pressure drop rate when the diaphragm rate is Y (N ₀ / N)

△ P _P0 : Pressure drop when pipe is not blocked.

Overall heat transfer _{Q = h i A (T P} -T W1) = (kA / △ x) (T W1 -T W2) = h O A (T W2 -T S) = (T P -T S) / (1 / h A _i + △ x / kA + 1 / A h _O) = (T _P -T _S) / (R _i + _W R + R _O)

R _S = Sliding pressure drop standard value

R _P (Y): Pressure drop standard value

RP _S : Sliding pressure drop ratio

RP _P (Y): Pressure drop ratio

SPR _{△ P} : Reference gauge rate conversion factor

SPR _h : Conversion factor

UA: Heat transfer performance

X: slew rate

Y: Thrombosis rate

A _P V _P = A _P0 V _P0

A _P / A _P0 = V _P0 / V _P

R _S =? P _S0 /? P _S

RP _S = (? P _S -? P _S0 ) /? P _S = (1-R _S )

_{R P (Y) = △ P} P0 / △ P P = A P 2 / A P0 2 = (N - N 0) 2 / N 2 = (1 - Y) 2

_{RP P (Y) = (△} P P - △ P P0) / △ P P = 1 - RP (Y)

X = (1 - R _P (Y)) / (1 - R _S )

Samurai tone rate conversion factor SPR _h = ((1-H _P (0.01)) / (1-H _S )) * 100

Based gwanmak temperament scale factor _{SPR △ P = [(1-} R P (0.01)) / (1-R S)] * 100

△ P _P : Pressure drop rate when the diaphragm rate is Y (N ₀ / N)

ΔP _P0 : Pressure drop amount when no pipe is blocked.

N: heat transfer pipe quantity, XN: sleeving quantity, YN: pipe sealing quantity

Each processing procedure of the method for converting the gauge tone according to the present invention by the above-mentioned variable values will be described as follows.

The slip pressure drop standard value calculation step S10 is a step of calculating a slip pressure drop standard value R _S after the steam generator S1 performs the slipping operation. In this case, R _S = ΔP _S0 / ΔP _S . Here, △ P _S0 is sleeved prior to the entrance to the steam generator - is the pressure drop between the outlet nozzle, △ P _S is sleeving after the steam generator inlet - is the pressure drop between the outlet nozzle. The pressure drop before and after the sleeving is measured by the pressure sensor 11 provided on the reactor hot leg in Fig. 3, and the pressure on the inlet nozzle 180 side before the sleeving and the pressure on the inlet nozzle 180 side after the sleeving are respectively . The pressure of the inlet nozzle 180 before and after the sleeving, that is, the initial pressure value, and the flow rate changes at the points A, B, and C in FIG. 3 are described in detail After the measurement is made by one method of measuring the flow rate, the pressure of the outlet nozzle 182 is obtained by applying it to the Bernoulli equation. Dew by giving out a pressure of the outlet nozzle 182 at a pressure of the living around the inlet nozzle 180, and after, △ P _S0 and △ P _S has been computed, the sleeving pressure drop standard value (R _S) R _S = △ P _S0 / DELTA P _S.

In the slipping pressure drop ratio deriving step S20, a slipping pressure drop ratio RP _S between the inlet and outlet nozzles R _S is calculated using the standardized sliding pressure drop R _S obtained in the slipping pressure drop standard value calculation step _{S 10} . The sliding pressure drop ratio is RP _S = (ΔP _S - ΔP _S0 ) / ΔP _S = (1 - R _S ). R _S is the standard value of pressure drop and is obtained by the pressure drop ratio RP _S (X) = (1-R _S ) X when the sleeving rate in the tube is X.

In order to calculate the standard value R _P (Y) of the pipe blocking pressure, a tubular temperament setting process (S30) is performed to set the tubular temperament Y. The tubular temperament Y is represented by N ₀ / N, , N ₀ represents the number of heat transfer tubes subjected to the sleeving.

Next, in the blocking of the pipe pressure drop standard value calculation process (S40) and calculates the pressure drop tube blocking standard value (R _P (Y)). The standard value R _P (Y) of the pipe wall pressure drop R _P (Y) is calculated by the following equation: R _P (Y) = ΔP _P0 / ΔP _P = A _P ² / A _{P 0} ² = (N - N ₀ ) ² / N ² = Y) ² . Where A _P is the cross-sectional area of the flow path after sleeving, and A _P0 is the cross-sectional area of the flow path before sleeving. The pipe wall pressure drop standard value R _P (Y) = ΔP _P0 / ΔP _P = A _P ² / A _{P 0} ² = (N - N ₀ ) ² / N ² = (1-Y ² ) is the condition A _P V _P = A _P0 V _P0 of the continuity equation, A _P / A _P0 A _P / A _P0 calculated by applying A _P0 = NπR ² , A _P = (NN ₀ ) πR ² = V _P0 / V _P , = (N - N ₀ ) / N. Again describe the parameters, N is a heat transfer tube quantity, N ₀ is the pressure drop, △ P _P0 in the case of heat transfer tubes quantity performing a pipe blocking, △ P _P is gwanmak rhyme is Y = N ₀ / N is not the tube blocking R _s is the slip standard pressure drop value, A _p = cross-sectional area of flow path after sleeving, and A _P0 = cross-sectional area of flow path before sleeving.

Hereinafter, the process of calculating the ratio of the gutta-rhythm-related sleeving rate (S50) is a process for obtaining the ratio of the gutta rhythm slee- pering rate X / Y, which is the ratio of the sleeving rate X corresponding to the gut ratio Y. (1-R _P (Y)) / (1-R _S ) by the condition that the pressure drop ratio when the sleeving rate is X and the pressure drop ratio when the tubular tone is Y is calculated, R _P (Y) is the standard value of the pressure drop of the pipe, and R _S is the standard value of the sliding pressure drop.

Then, a process for the pressure drop ratio calculation process (S70) by using a pipe blocking quantity and sleeving quantity defined calculate a pressure drop ratio (RP _P (Y)), the pressure drop ratio of gwanmak swing Y (RP _P (Y) is calculated from RP _P (Y) = (ΔP _P - ΔP _P0 ) / ΔP _P = 1 - RP (Y). Here, △ P _P is the pressure drop in the case of the swing gwanmak _{Y = N O / N, △} P P0 is the pressure drop of when not blocking the tube.

Next, in the step S80 of calculating the reference gutta-tone-related-conversion coefficient, the reference gutta-tone conversion factor (SPR _{? P} ) is calculated after setting the reference guttaion tone to 1%. The reference gut conversion ratio SPR _{? P} = XN / YN = (1 - R _P (Y)) / (1 - R _S )) * (1 / Y). Here, the pipe yield is the product of the tubular tempera- ture (Y) and the heat pipe yield (N), where the slew yield is the product of the slew rate (X) and the heat transfer pipe quantity (N). Thus, as a sleeving the equivalent quantity of tube blocking considering the pressure drop available for the one standard gwanmak temperament scale factor SPR _△ according to sleeving _{P = [(1-R P} (0.01)) / (1-R S)] * Lt; / RTI > At this time, the reference gubral tone rate is 1% (Y = 0.01).

Next, the overall heat transfer calculation process S90 is a process of calculating an overall heat transfer coefficient for converting the tubular sounding rate by the heat transfer performance. This is a comparison between the standard value of heat transfer performance during pipe closure and the standard value of heat transfer performance during slewing using steam generator design data.

The overall annual delivery Q is calculated from _{Q = h i A (T P} -T W1) = (kA / △ x) (T W1 -T W2) = h O A (T W2 -T S). This relationship is summarized as _{(T P -T S) / (} 1 / h i A + △ x / kA + 1 / h O A) = (T P -T S) / (R i + R W + R O) do. The parameters and constants of the above equation are as follows: h _i is the inner film heat transfer coefficient, h _O is the outer film heat transfer coefficient, T _P is the reactor coolant temperature, k is the heat transfer coefficient, A is the heat transfer area, Δx is the thickness of the sleeving pipe, T _W1 is a heat transfer tube internal temperature, T _W2 is a heat transfer tube external temperature, R _i is the internal dura thermal resistance, R _W is the heat transfer tube heat resistance, R _O is the outer dural thermal _{resistance, 1 / (R i + R} W + R O) Is the total thermal resistance.

The heat transfer performance calculation step S100 is to calculate the heat transfer performance UA. The total heat transfer coefficient Q = (T _P -T _S ) / (R _i + R _W + R _O ) (W / m ² * K) and the heat transfer area A, respectively. In summary, Q = UA (T _P - T _S ), and heat conductivity is equivalent to the total thermal resistance 1 / (R _i + R _W + R _O ).

The process for calculating the standard value of the pipe heating heat transfer performance (S110) is a process for obtaining the standard value of the pipe heating heat transfer performance H _P. Since the heat transfer performance standard value H _P of the conduit performance changes only before and after the conduit, the standard value of the heat transfer performance before and after 1% of the conduit performance is calculated as H _P (0.01) = U _P A _P / U _{P 0} A _{P 0} = 0.99.

The sleeving heat transfer performance reference value calculation process (S120) is a process for calculating a heat transfer performance of the standard values before and after sleeving H _S. The standard values of the heat transfer performance before and after the sleeving are calculated by H _S = U _S A _S / U _S0 A _S0 .

(S130) is calculated as SPR _h = ((1-H _P (0.01)) / (1-H _S )) * 100, which is a conversion coefficient of the membrane before and after the sleeving.

In step S140, the tubular tonal conversion coefficient SPR _h is used to determine the tubular tonal sound according to the sleeving.

1: diaphragm sound ratio conversion device
10: Sensor unit
11: first temperature sensor, 13: pressure sensor, 15: first flow sensor, 19: second flow sensor
21: third flow rate sensor, 23: second temperature sensor
30: control unit
31: display unit, 33: interface unit, 35: communication unit, 37: control unit
100: steam generator
162: heat transfer tube, 180: inlet nozzle, 182: outlet nozzle
310: reactor hot leg, 330: effluent piping, 340: reactor cold leg
a: inlet nozzle expansion part b: heat transfer pipe inlet shrinkage part
c: section heat pipe friction loss part d: bending part friction loss part
e: expansion of the heat transfer pipe outlet f: exit nozzle reduction part
g: Sleeve inlet reduction part h: Sleeve friction loss part
i: Sleeve outlet swelling part
j: an enlarged cross-sectional view of one heat transfer pipe 162 in the sleeve region

Claims (16)

A steam generator inlet nozzle 180 for detecting at least one of temperature, pressure, and flow rate before and after the slipping, and at least one of temperature, pressure, or flow rate sensors installed in the steam generator and at the side of the steam generator outlet nozzle 182 And a sensor unit 10 for measuring the diaphragm sound rate after calculating the diaphragm sound conversion factor using the pressure drop before and after the slewing and the heat transfer performance, And a control unit (30), wherein the steam generator throttling ratio conversion unit considers the pressure drop and the heat transfer performance;
The control unit (30) controls the temperature of the steam generator inlet nozzle side measured by the sensor unit (10), the pressure, the flow rate information, and the temperature information of the outlet nozzle side, The pressure drop ratio RP _S is calculated and the standard value R _P (Y) of the pressure drop of the tubular membrane as expressed by the set gaiter (Y) is calculated, and the slip rate X corresponding to the tubular tone Y ratio of calculated to sleeving ratio (X / Y), tube plugging by defining (S60) a quantity and sleeving quantity calculates the pressure drop ratio (RP _P (Y)) for the gwanmak swing (Y), gwanmak (SPR _{? P} ), which is a conversion coefficient for the reference gut feeling, is calculated using the pressure drop ratio (RP _P (Y)) to the tone Y and the overall heat transfer Q is calculated, the charge of soft transfer (Q) heat transfer performance (UA) blocking the calculations, by using the calculated heat transfer performance (UA) tube blocking tube before and after the heat transfer performance reference value (H _P) from total And, using the calculated the heat transfer performance (UA) calculating the sleeving heat transfer performance reference value (H _S) and after sleeving around, said pipe preventing heat transfer performance reference value (H _P) and said sleeving heat transfer performance reference value (H _S ) a, and calculating the sleeving gwanmak temperament scale factor (SPR _h before and after), the gwanmak temperament scale factor (SPR _h) a controller (37 for determining the sleeving gwanmak swing by using a heat transfer performance (UA) using Wherein the steam generator is a steam generator.
The method according to claim 1,
The sensor unit (10)
A first temperature sensor 11 and a pressure sensor 13 installed in the inlet nozzle 180 of the steam generator for measuring the temperature, pressure and flow rate of the first cooling water flowing into the steam generator, a plurality of flow sensors 15, And a second temperature sensor (23) installed at an outlet nozzle (182) of the steam generator for measuring the temperature of the primary cooling water discharged from the steam generator. A Steam Generator Sampling Rate Conversion System Considering Performance.
delete The method according to claim 1,
The control unit (30)
A display section (31) for displaying a gauge tone conversion process, a result, and a user input command;
An interface unit 33 for inputting a set value of the user,
And a communication unit (35) for communicating with the sensors of the sensor units (10) or the outside. delete delete delete delete delete delete delete delete delete delete delete delete

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