KR20170030823A - Apparatus for reliability test of pumps in nuclear power plant and its method - Google Patents

Apparatus for reliability test of pumps in nuclear power plant and its method Download PDF

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Publication number
KR20170030823A
KR20170030823A KR1020150128230A KR20150128230A KR20170030823A KR 20170030823 A KR20170030823 A KR 20170030823A KR 1020150128230 A KR1020150128230 A KR 1020150128230A KR 20150128230 A KR20150128230 A KR 20150128230A KR 20170030823 A KR20170030823 A KR 20170030823A
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South Korea
Prior art keywords
pump
flow rate
test
pressure
control valve
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KR1020150128230A
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Korean (ko)
Inventor
이선기
이상국
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한국수력원자력 주식회사
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Publication of KR20170030823A publication Critical patent/KR20170030823A/en

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    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
    • F04B—POSITIVE-DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS
    • F04B51/00—Testing machines, pumps, or pumping installations
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01D—MEASURING NOT SPECIALLY ADAPTED FOR A SPECIFIC VARIABLE; ARRANGEMENTS FOR MEASURING TWO OR MORE VARIABLES NOT COVERED IN A SINGLE OTHER SUBCLASS; TARIFF METERING APPARATUS; MEASURING OR TESTING NOT OTHERWISE PROVIDED FOR
    • G01D5/00—Mechanical means for transferring the output of a sensing member; Means for converting the output of a sensing member to another variable where the form or nature of the sensing member does not constrain the means for converting; Transducers not specially adapted for a specific variable
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01F—MEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
    • G01F1/00—Measuring the volume flow or mass flow of fluid or fluent solid material wherein the fluid passes through a meter in a continuous flow
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01H—MEASUREMENT OF MECHANICAL VIBRATIONS OR ULTRASONIC, SONIC OR INFRASONIC WAVES
    • G01H17/00—Measuring mechanical vibrations or ultrasonic, sonic or infrasonic waves, not provided for in the preceding groups
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K13/00—Thermometers specially adapted for specific purposes
    • G01K13/02—Thermometers specially adapted for specific purposes for measuring temperature of moving fluids or granular materials capable of flow
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01L—MEASURING FORCE, STRESS, TORQUE, WORK, MECHANICAL POWER, MECHANICAL EFFICIENCY, OR FLUID PRESSURE
    • G01L19/00—Details of, or accessories for, apparatus for measuring steady or quasi-steady pressure of a fluent medium insofar as such details or accessories are not special to particular types of pressure gauges
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01L—MEASURING FORCE, STRESS, TORQUE, WORK, MECHANICAL POWER, MECHANICAL EFFICIENCY, OR FLUID PRESSURE
    • G01L3/00—Measuring torque, work, mechanical power, or mechanical efficiency, in general
    • G—PHYSICS
    • G05—CONTROLLING; REGULATING
    • G05D—SYSTEMS FOR CONTROLLING OR REGULATING NON-ELECTRIC VARIABLES
    • G05D7/00—Control of flow
    • G—PHYSICS
    • G06—COMPUTING; CALCULATING OR COUNTING
    • G06F—ELECTRIC DIGITAL DATA PROCESSING
    • G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
    • G06F17/10—Complex mathematical operations

Abstract

The present invention relates to an apparatus for testing nuclear pump reliability. More specifically, the present invention has a closed loop, comprising: a pump to be tested; a flowmeter; a flow control valve; and a water tank. Pump rotation water and a torque measurement device are connected to a motor in the pump to be tested, and each pressure gauge is installed in an inlet and an outlet of the pump.

Description

FIELD OF THE INVENTION [0001] The present invention relates to a nuclear power plant,

The present invention relates to a nuclear pump reliability evaluation test apparatus, specifically comprising a closed loop composed of a pump to be tested, a flow meter, a flow rate control valve, and a water tank. The pump to be tested includes a pump rotation speed and torque meter, And a pressure gauge is provided on the outlet side and the outlet side, respectively,

Numerous pumps installed in nuclear power plants are operated under severe conditions such as high temperature, high pressure, and radioactive environment, and high reliability is demanded in order to secure safety of nuclear power plants.

However, deterioration of equipment due to aged deterioration of the power plant and transient phenomena due to sudden load change operation are obstacles to the reliability of the pump.

The present invention proposes a test apparatus and a test method designed to evaluate the reliability of a pump used in a nuclear power plant. The proposed method changes the flow rate of the pump at regular intervals to induce fluctuations in the load acting on the pump. The pump reliability is judged by the change of the efficiency and the vibration value.

The flow meter verification system disclosed in Korean Patent Publication No. 10-1154275 and a pump test system using the same and the technical configuration and operation effects of the lifting oil pump inspection apparatus of a generator turbine disclosed in Korean Patent Registration No. 10-0742964 and the present invention The difference is remarkable.

Korean Patent Publication No. 10-1154275 Korean Patent Registration No. 10-0742964

The problem to be solved by the present invention is that the 'reliability evaluation test method and apparatus' of the nuclear pump continuously changes the pump flow rate from 100% of the design flow rate to 50% of the design flow rate at a constant cycle, Is compared with the initial value so as to be able to judge whether or not the target pump exerts its function during its lifetime.

In the nuclear pump reliability evaluation test apparatus, the rotational speed of the motor incorporated in the pump to be tested and the torque meter 140 of the motor are connected to the motor 150, and the flow rate of the pump to be tested is measured And a flow rate control valve 120 for controlling the flow rate based on the measured flow rate. Pressure gauges 160 and 170 for measuring the pressure of the fluid at the inlet and outlet sides of the pump, The present invention also provides a nuclear pump reliability evaluation test apparatus.

A further object of the present invention is to provide a nuclear pump reliability evaluation test method in which a reference performance test of a nuclear pump is performed by a) b) confirming whether the number of revolutions of the test pump is a set reference number of revolutions; c) slowly opening and closing the flow control valve and setting the system flow rate to 120% of the pump rated flow; d) In step c), the flow rate

Figure pat00001
), Pump inlet pressure (
Figure pat00002
), Pump outlet pressure (
Figure pat00003
), Pump rotation speed (
Figure pat00004
), Shaft power (
Figure pat00005
), Vibration (x, y, z directions in the pump casing), and water temperature; e) slowly closing the flow control valve again and setting the system flow rate to 100% of the pump rated flow rate; f) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature in step e); g) slowly closing the flow control valve again and setting the system flow rate to 80% of the pump rated flow; h) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature in step g); i) slowly closing the flow control valve again and setting the system flow rate to 60% of the pump rated flow rate; j) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in pump casing), and water temperature in step i); k) slowly closing the flow control valve again and setting the system flow rate to 40% of the pump rated flow rate; l) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature in step k); m) slowly closing the flow control valve again and setting the system flow rate to 20% of the pump rated flow rate; n) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature in step m); o) slowly closing the flow control valve again and setting the system flow rate to 0% of the pump rated flow rate; And p) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing) and water temperature in step o) Method.

A further object of the present invention is to provide a flow rate

Figure pat00006
) And the total head
Figure pat00007
) The pump outlet-side pressure (kg / cm 2) (gravitational acceleration minus the pump inlet pressure (kg / cm 2) (P 1) from the P 2) at the water density (kg / m 3) () (m / s 2 ) (g) (Formula (1)).

Figure pat00008
[m] - (1)

here,

Figure pat00009
: Pump outlet pressure (kg / cm 2 ),
Figure pat00010
: Pressure at the inlet of the pump (kg / cm 2 ),
Figure pat00011
: Density of water (kg / m 3 ),
Figure pat00012
: Gravitational acceleration (m / s 2 )

A further object of the present invention is to provide a flow rate

Figure pat00013
) A reference to the Efficiency () is the pump outlet-side pressure (kg / cm 2) (pump inlet pressure (kg / cm 2) from P 2) (density minus the P 1) of water (kg / m 3) ( ) Divided by the gravitational acceleration (m / s 2 ) (g) multiplied by the acceleration (m / s 2 ) (equation (1)).

Figure pat00014
[%] ---- (2)

here,

Figure pat00015
: Pump outlet pressure (kg / cm 2 ),
Figure pat00016
: Pressure at the inlet of the pump (kg / cm 2 ),
Figure pat00017
: Density of water (kg / m 3 ),
Figure pat00018
: Gravitational acceleration (m / s 2 ),
Figure pat00019
: Flow rate (m 3 / min),
Figure pat00020
: Total head (m)

A further object of the present invention is to provide a nuclear pump reliability evaluation test method, wherein the primary reliability test includes: a) starting a test pump; b) confirming whether the number of revolutions of the test pump is a set reference number of revolutions; c) operating the flow rate control valve at the rear end of the test pump for a total of 144 hours while adjusting it as shown in FIG. 2; d) stopping the pump; e) maintaining a rest state at room temperature for 24 hours; f) Perform the reference performance test described above and compare the test results with the flow rate

Figure pat00021
) And the head
Figure pat00022
), efficiency(
Figure pat00023
), And comparing and recording the vibration values.

A further object of the present invention is to provide a method of operating a flow control valve comprising the steps of: a) adjusting the valve opening to reduce the flow rate from 100% to 50% for 10 seconds; b) maintaining a 50% flow rate for 10 seconds; c) adjusting the valve opening to increase the flow rate from 50% to 100% for 10 seconds; And

and d) maintaining the flow rate at 100% for 10 seconds.

The secondary reliability test or the tenth reliability test is performed by repeating the same test as the first reliability test from the second to the tenth tenth, And terminating the reliability test when the test is finished.

Another solution to the problem of the present invention is to provide a nuclear power plant including a step of judging that reliability of the pump to be tested is secured when the difference between the flow rate reference total head, the efficiency, and the vibration value is less than 5% And to provide a pump reliability evaluation test method.

The 'Reliability Evaluation Test Method and Apparatus of Nuclear Pump of the Present Invention' continuously changes the flow rate of the pump from 100% of the design flow rate to 50% of the design flow rate at a constant cycle, and compares the magnitude of the lift, efficiency and vibration of the pump with the initial value It is possible to judge whether or not the target pump exerts its function during its lifetime.

Fig. 1 shows the entire nuclear pump reliability evaluation test apparatus.
2 is an explanatory view of a flow control valve operation mode.
FIG. 3 shows a method of determining the pump reliability test result.

Hereinafter, the present invention will be described in detail.

The present invention is a closed loop composed of a pump to be tested, a flow meter, a flow control valve, and a water tank. The present invention relates to a test apparatus and method of a nuclear pump reliability evaluation test apparatus in which a motor for measuring the rotational speed of a motor incorporated in a pump and a motor torque meter are connected to a motor and a pressure gauge is provided at an inlet side and an outlet side of the pump, respectively. More specifically, a specific embodiment according to the present invention will be described.

<Examples>

A specific embodiment according to the present invention will be described with reference to the drawings.

1 is a nuclear pump reliability evaluation test apparatus according to the present invention, which is a closed loop composed of a pump 100 to be tested, a flow meter 110, a flow control valve 120 and a water tank 130. The pump to be tested is connected to the motor 150 and the pressure gauges 160 and 170 on the inlet side and the outlet side, respectively, of the number of revolutions of the motor built in the pump and the torque meter 140 of the motor.

Fig. 2 schematically shows the operation mode of the flow control valve 120 of Fig. 1, so that the load acting on the pump is varied by operating the opening degree of the valve.

The nuclear pump reliability evaluation test apparatus can automatically open and close the flow control valve at the rear end of the pump in a closed loop composed of the pump 100 to be tested, the flow meter 110, the flow control valve 120 and the water tank 130 .

That is, according to the present invention, control software is mounted in a memory so that a computer or a microprocessor that receives a signal from each sensor can automatically process a nuclear pump reliability evaluation test, and the measured signal from each sensor is stored in a memory And is used to determine whether the reliability of the pump to be tested is ensured.

The reliability evaluation test method of the nuclear pump using the nuclear pump reliability evaluation test apparatus according to the present invention will be described in detail.

The reference performance test of the nuclear pump will be described.

a) activating the pump under test.

b) confirming whether the number of revolutions of the test pump is a set reference revolving speed.

c) slowly opening and closing the flow control valve and setting the system flow rate to 120% of the pump rated flow rate.

d) The flow rate at this time

Figure pat00024
), Pump inlet pressure (
Figure pat00025
), Pump outlet pressure (
Figure pat00026
), Pump rotation speed (
Figure pat00027
), Shaft power (
Figure pat00028
), Vibration (x, y, z directions in the pump casing), and water temperature.

e) slowly closing the flow control valve again and setting the system flow rate to 100% of the pump rated flow rate.

f) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

g) slowly closing the flow control valve again and setting the system flow rate to 80% of the pump rated flow rate.

h) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

i) slowly closing the flow control valve again and setting the system flow rate to 60% of the pump rated flow rate.

j) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

k) slowly closing the flow control valve again and setting the system flow rate to 40% of the pump rated flow rate.

l) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

m) again slowly closing the flow control valve and setting the system flow rate to 20% of the pump rated flow rate.

n) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

o) slowly closing the flow control valve again and setting the system flow rate to 0% of the pump rated flow rate.

p) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature.

From the above experimental data,

Figure pat00029
) And the total head
Figure pat00030
) And efficiency
Figure pat00031
).

The total lift and efficiency of the pump is calculated by the following formula.

flux(

Figure pat00032
) And the total head
Figure pat00033
) Is the pump outlet-side pressure (kg / cm 2) (P 2) gravitational acceleration minus the pump inlet pressure (kg / cm 2) (P 1) at the water density (kg / m 3) () from (m / s 2 ) divided by the product of (g) (see equation (1)).

The dictionary meaning of the total head refers to the sum of the pressure (head) that the pump must give to the water when it is pumped from low to high.

flux(

Figure pat00034
) Based on the efficiency (
Figure pat00035
) Is the value obtained by multiplying the density of water (kg / m 3 ) (), the acceleration of gravity (m / s 2 ) (g), the flow rate (m 3 / min) and the total head (See Equation (2)).

From here

Figure pat00036
: Flow rate (m 3 / min)

Figure pat00037
: Total head (m)

Figure pat00038
: Pump outlet pressure (kg / cm 2 )

Figure pat00039
: Pump inlet pressure (kg / cm 2 )

L : Shaft power (KW)

Figure pat00040
: Pump Efficiency (%)

Figure pat00041
: Density of water (kg / m 3 )

Figure pat00042
: Gravitational acceleration (m / s 2 )

to be.

Figure pat00043
[m] - (1)

Figure pat00044
[%] ---- (2)

The following is the first reliability test.

a) activating the test pump.

b) confirming whether the number of revolutions of the test pump is a set reference revolving speed.

c) operating the flow rate control valve at the rear end of the test pump for a total of 144 hours while adjusting it as shown in FIG.

       Here, a flow control valve operation method will be described.

   And adjusting the valve opening to reduce the flow rate from 100% to 50% for 10 seconds.

   And maintaining a 50% flow rate for 10 seconds.

   And adjusting the valve opening degree to increase the flow rate from 50% to 100% for 10 seconds.

   And maintaining a 100% flow rate for 10 seconds.

     The above operation is performed for a total of 144 hours.

     d) stopping the pump.

     e) maintaining the stationary state at room temperature for 24 hours.

f) Perform the reference performance test described above and compare the test results with the flow rate

Figure pat00045
) And the head
Figure pat00046
), efficiency(
Figure pat00047
), And comparing and recording vibration values.

The following are the secondary reliability test or the 10th reliability test.

     a) Perform the same tests as the first reliability test from the second to the tenth, and end the reliability test when the tenth test is completed.

The results of the above experiments are summarized as shown in FIG. 3, and include the step of judging that the target pump is reliable when the difference between the flow rate reference head, efficiency, and vibration value is less than 5% from the basic performance test result.

The present invention relates to a nuclear pump reliability evaluation test apparatus, specifically comprising a closed loop composed of a pump to be tested, a flow meter, a flow rate control valve, and a water tank. The pump to be tested includes a pump rotation speed and torque meter, The reliability of nuclear pump reliability can be efficiently evaluated by applying a nuclear pump reliability evaluation test apparatus and method with a pressure gauge on the side and outlet side,

100 ----- Pump to be tested
110 ----- Flowmeter
120 ----- Flow control valve
130 ----- Tank
140 ----- Pump motor speed measuring instrument
150 ----- Pump Motor Torque Meter
160 ----- Pressure gauge on the inlet side of the pump
170 ----- Pump outlet side pressure gauge

Claims (9)

A nuclear pump reliability evaluation test apparatus comprising:
The number of rotations of the motor incorporated in the pump to be tested and the torque meter 140 of the motor are connected to the motor 150,
A flow meter 110 for measuring the flow rate of the pump to be tested and a flow rate control valve 120 for controlling the flow rate based on the measured flow rate,
And a pressure gauge (160, 170) for measuring the pressure of fluid at the inlet side and the outlet side of the pump, respectively. The method according to claim 1,
The nuclear pump reliability evaluation test apparatus includes a control program and is configured to automatically evaluate the reliability of the nuclear pump based on a signal input from each sensor. In the nuclear pump reliability evaluation test method,
The reference performance test of the nuclear pump
a) activating the pump under test;
b) confirming whether the number of revolutions of the test pump is a set reference number of revolutions;
c) slowly opening and closing the flow control valve and setting the system flow rate to 120% of the pump rated flow;
d) In step c), the flow rate
Figure pat00048
), Pump inlet pressure (
Figure pat00049
), Pump outlet pressure (
Figure pat00050
), Pump rotation speed (
Figure pat00051
), Shaft power (
Figure pat00052
), Vibration (x, y, z directions in the pump casing), and water temperature;
e) slowly closing the flow control valve again and setting the system flow rate to 100% of the pump rated flow rate;
f) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing) and water temperature in step e);
g) slowly closing the flow control valve again and setting the system flow rate to 80% of the pump rated flow;
h) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing), and water temperature in step g);
i) slowly closing the flow control valve again and setting the system flow rate to 60% of the pump rated flow rate;
j) recording the flow rate, pump inlet pressure, pump outlet pressure, pump rotation speed, shaft power, vibration (x, y, z directions in the pump casing) and water temperature in step i);
k) slowly closing the flow control valve again and setting the system flow rate to 40% of the pump rated flow rate;
l) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing) and water temperature in step k);
m) slowly closing the flow control valve again and setting the system flow rate to 20% of the pump rated flow rate;
n) recording the flow rate, pump inlet pressure, pump outlet pressure, pump speed, shaft power, vibration (x, y, z directions in the pump casing) and water temperature in step m);
o) slowly closing the flow control valve again and setting the system flow rate to 0% of the pump rated flow rate; And
p) recording the nuclear reactor pump reliability evaluation method (step a), including the flow rate, the pump inlet pressure, the pump outlet pressure, the pump rotation speed, the shaft power, the vibration (x, y, z directions in the pump casing) . The method of claim 3,
flux(
Figure pat00053
) And the total head
Figure pat00054
) Is the pump outlet-side pressure (kg / cm 2) (P 2) gravitational acceleration minus the pump inlet pressure (kg / cm 2) (P 1) at the water density (kg / m 3) () from (m / s 2 ) (g) (Formula (1)).
{
Figure pat00055
[m] - (1)
here,
Figure pat00056
: Pump outlet pressure (kg / cm 2 ),
Figure pat00057
: Pressure at the inlet of the pump (kg / cm 2 ),
Figure pat00058
: Density of water (kg / m 3 ),
Figure pat00059
: Gravitational acceleration (m / s 2 )} The method of claim 3,
flux(
Figure pat00060
) And the total head
Figure pat00061
) Is the pump outlet-side pressure (kg / cm 2) (P 2) gravitational acceleration minus the pump inlet pressure (kg / cm 2) (P 1) at the water density (kg / m 3) () from (m / s 2 ) (g) (Formula (2)).
{
Figure pat00062
[%] ---- (2)
here,
Figure pat00063
: Pump outlet pressure (kg / cm 2 ),
Figure pat00064
: Pressure at the inlet of the pump (kg / cm 2 ),
Figure pat00065
: Density of water (kg / m 3 ),
Figure pat00066
: Gravitational acceleration (m / s 2 ),
Figure pat00067
: Flow rate (m 3 / min),
Figure pat00068
: Total head (m)} In the nuclear pump reliability evaluation test method,
The primary reliability test
a) activating a test pump;
b) confirming whether the number of revolutions of the test pump is a set reference number of revolutions;
c) operating for a total of 144 hours while adjusting the flow control valve at the end of the test pump;
d) stopping the pump;
e) maintaining a rest state at room temperature for 24 hours;
f) Perform the reference performance test and compare the test results with the flow (
Figure pat00069
) And the head
Figure pat00070
), efficiency(
Figure pat00071
), And comparing and recording vibration values. The method of claim 6,
How to operate the flow control valve
a) adjusting the valve opening to reduce the flow rate from 100% to 50% for 10 seconds;
b) maintaining a 50% flow rate for 10 seconds;
c) adjusting the valve opening to increase the flow rate from 50% to 100% for 10 seconds; And
d) maintaining a 100% flow rate for 10 seconds. In the nuclear pump reliability evaluation test method,
Secondary reliability test or 10th reliability test
a) The nuclear pump reliability evaluation test method including repeating the same test as the first reliability test from the second to the tenth and ending the reliability test after the tenth test. The method of claim 8,
And a step of judging that the reliability of the pump to be tested is secured when the difference between the flow rate reference value, the efficiency and the vibration value is within 5% from the basic performance test result.
KR1020150128230A 2015-09-10 2015-09-10 Apparatus for reliability test of pumps in nuclear power plant and its method KR20170030823A (en)

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CN107269548A (en) * 2017-08-15 2017-10-20 上海电气凯士比核电泵阀有限公司 One seed nucleus level pump impurity tester and its test method
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