KR100424330B1 - In-pile creep test system - Google Patents

Abstract

In order to enable remote control by developing a creep test apparatus for performing irradiated creep test, which is a mechanical property test under irradiated reactor conditions:

Creep test means installed vertically in the reactor tank;

A detector electrically connected to the creep test means to measure temperature and clip deformation of the specimen;

A gas supply device connected to the creep test means and a gas supply pipe to control the supply of helium gas in the helium gas reservoir tank with air pressure of an air compressor;

It is to provide a creep test apparatus for a nuclear reactor, characterized in that consisting of the detector and a control device for reading the input data while being controlled by the input information is electrically connected to the gas supply device.

Description

Reactor Creep Testing Equipment {IN-PILE CREEP TEST SYSTEM}

The present invention relates to a creep test apparatus for a nuclear reactor, and more particularly to a creep test apparatus for remote control with a creep test apparatus for performing an irradiated creep test which is a mechanical property test under the reactor reactor irradiation conditions. It is about.

In general, various research tests have been carried out in research reactors in order to evaluate the health of reactor materials and develop new materials.

In particular, for structural materials such as fuel cladding and pressure vessel materials, creep tests are essential.

The device for conducting the irradiation creep test in a research reactor is loaded in a tank filled with distilled water in the reactor, which places great emphasis on stability and reliability.

In addition, it should be applicable to materials with various size shapes, and should be easy to handle in structures and reactors in which the desired constant dose of the specimen is effectively irradiated.

After the irradiation test, it is possible to remotely disassemble the hot cell, which is a shielding facility of the creep test device, into a manipulator and to reduce the amount of nuclear waste after the irradiation test by reducing the total amount of material.

In general, the capsule type test apparatus used for irradiating materials is a simple non-instrumental (without measuring instrument) capsule without any measuring device in the capsule, and an instrumentation device with various measuring devices and mechanical properties under irradiation conditions. It is classified as a special capsule type test device capable of carrying out the test.

The capsule test device as described above is assembled by inserting the material for the irradiation test directly into the capsule, and some parts are welded and fixed together with the capsule.

In particular, the special encapsulated test apparatus measures the amount of irradiation strain while applying load to the specimen under irradiation conditions, such as creep deformation, for the purpose of mechanical testing.

For this reason, there is a problem in that the conventional instrument-free capsule or instrumentation capsule cannot be used directly because an auxiliary device such as a measuring instrument device must be installed inside the capsule test device.

Ancillary devices, such as measuring instruments as described above, should be designed and manufactured so as not to affect the amount of irradiation applied to the specimen as much as possible, and should be designed and manufactured in such a way as to minimize the amount of waste as it becomes nuclear waste after the irradiation test. There is a difficulty.

In addition, it should be borne in mind that some parts of the capsule type tester are mounted as a welding process to facilitate the task of disassembling and cutting the special capsule from the hot cell after the irradiation test.

Bellows, LVDT, etc. are difficult to reuse because they are radiated, but they must be disassembled to prevent possible damage to the specimen.

It is also important to keep in mind that it must be designed and manufactured so as not to damage major components required during the process of separating the specimens tested in a capsule test device.

As a special capsule test device is installed in the reactor, structural stability and reliability must be ensured, and at the same time, a proposal for a device capable of testing various materials is required.

An object of the present invention devised to solve the problems of the prior art made as described above is a reactor that enables remote control with a creep test apparatus for performing irradiated creep test, which is a mechanical property test under irradiated reactor conditions. To provide a creep testing device for

Figure 1 schematically shows that the creep test apparatus according to the present invention is applied.

Figure 2 is a partially cut perspective view showing a creep test apparatus of the present invention.

Figure 3 is a side cross-sectional view showing a creep tester of the present invention.

4 is a view showing a pressing member applied to the present invention.

5 is a view showing a tension member applied to the present invention.

6 is a view showing a measuring member applied to the present invention.

7 is a view showing a heating member applied to the present invention.

8 is a view showing a guide stopper applied to the present invention.

9 is a diagram showing the load-strain amount of the nuclear fuel clad tube according to the test of the present invention.

* Description of the symbols for the main parts of the drawings *

4: water tank 6: creep tester

10: detector 12: gas supply line

14: helium gas reservoir tank 16: air compressor

18: gas supply device 20: control device

22: fixed base 24: mounting groove

26: fixing member 28: pressure member

30: tensile member 32: heating member

34: measuring member 36: capsule

38: base plate 40: fixed shaft

48: Chamber 50: First plate

52: wrinkle tube 54: push plate

56: push rod 62: push rod groove

66: first holder 68: first guide stopper

74: upper fixing pin hole 76: upper holder plate

78: lower fixing pin hole 80: lower holder plate

82: U-shaped rod 90: Holder tube

92: slide shaft 94: linear strain differential transducer LVDT (LINEAR VARIABLE DIFFERENTIAL TRANSDUCER or strain measuring device)

104: heater housing 108: heating element

110: second guide stopper 112: third guide stopper

124: seal plate 126: sealing capsule

The present invention for realizing this

Creep test means installed vertically in the reactor tank;

A detector electrically connected to the creep test means to measure temperature and clip deformation of the specimen;

A gas supply device connected to the creep test means and a gas supply pipe to control the supply of helium gas in the helium gas reservoir tank with air pressure of an air compressor;

It is to provide a creep test apparatus for a nuclear reactor, characterized in that consisting of the detector and a control device for reading the input data while being controlled by the input information is electrically connected to the gas supply device.

The creep test means described above

A fixing member assembled and fixed to the irradiation creep test tank,

A pressurizing member installed to pressurize by supplying pressurized gas to one chamber of the fixing member,

A tension member installed to tension the test material by the operation of the pressure member;

A heating member assembled to the tension member and installed to heat the test material;

A measuring member for detecting a retraction of the tension member and measuring a creep deformation amount;

The present invention provides a creep test apparatus for a nuclear reactor comprising a plurality of cylindrical capsules installed in the order of pressing member, tension member, heating member, and measuring member while forming the fixing member at one end.

The fixing member includes a base plate provided at the lower end of the capsule, a fixed shaft protruding from the center of the base plate, a detent portion slidably assembled to the fixed shaft, and interposed between the detent portion and the base plate to support the detent portion. An object of the present invention is to provide a creep test apparatus for a nuclear reactor composed of an elastic member.

The pressing member includes a first plate fixed in the capsule at regular intervals while forming a chamber on one side from the base plate, a corrugated pipe attached to one side of the first plate, and a push plate integrally mounted on one side of the corrugated pipe. The present invention provides a creep test apparatus for a nuclear reactor.

The first plate is to provide a creep test apparatus for a reactor formed by forming a slide ball to slide the push rod of the tension member.

The push plate is to provide a creep test apparatus for a reactor formed by forming a push rod groove in contact with the push rod of the tension member.

The tension member is formed on the other side of the first plate with a first holder part divided up and down at a predetermined interval on a horizontal line, and partly overlapped with the first holder part to be spaced apart from the first plate by a capsule. The present invention provides a creep test apparatus for a nuclear reactor consisting of a second holder portion assembled to slide a first guide stopper attached therein.

The first holder portion includes a guide groove formed on a horizontal line, an upper holder plate having a plurality of upper fixing pin holes formed on the upper side of the guide groove, and a plurality of lower fixing pin holes formed to face the lower side of the upper holder plate. The present invention provides a creep test apparatus for a nuclear reactor including a lower holder plate.

The second holder portion includes a push rod formed and assembled in a slide hole of the first plate with a predetermined length, a U-shaped rod formed so that one end of the push rod is provided with a test material interposed therebetween, and It is formed by forming a cylindrical holder tube having a plurality of upper and fixed pin holes formed at one end thereof so that the test material is fixed by the fixing pins, and a slide shaft protruding axially to slide the first guide stopper on one side of the holder tube. The present invention provides a creep test apparatus for a nuclear reactor.

The slide shaft provides a creep test apparatus for a nuclear reactor, in which a measuring needle of a linear strain differential transducer is formed at an end thereof so as to form a measuring needle groove located on an axis line.

The first guide stopper is to provide a creep test apparatus for a nuclear reactor through a bearing member in order to reduce friction with the slide shaft.

The heating member is provided with a circular heater housing having an insertion hole formed to be inserted into the U-shaped rod from the side, a groove having a plurality of grooves formed with a gas supply line interposed on the outer circumferential surface of the heater, and electrically connected to a detector in the heater housing. The present invention provides a creep test apparatus for a nuclear reactor including a heating element.

The measuring member is electrically connected with the detector and is a linear strain differential transducer which is located in the axis line with respect to the slide axis of the tension member assembled to the first guide stopper and penetrates the center of the second guide stopper attached to the capsule; The present invention provides a creep test apparatus for a nuclear reactor including a cap assembled to one end of the lead-type differential transducer and attached to one side of a third guide stopper attached to the capsule.

The capsule is circumferentially formed by the attachment of the fixing member and the welding of the first plate, and the first capsule having a chamber formed thereon, and the first capsule attached to the first capsule to allow the interior of the tension member to be assembled and assembled. As the guide stopper is welded, the second capsule is vacuum-formed to be cooled by accelerating soft delivery by blocking heat transfer to the outside due to heat generation of the heating element and by adding helium gas, and attached to the second capsule. A third capsule formed by welding the second guide stopper to be installed on the center line, and a third guide stopper attached to the third capsule and having a fixed cap to which the linear strain differential transducer is assembled. Through the fourth capsule and the third guide stopper of the fourth capsule, a porous seal plate is provided to maintain the airtightness when the wires and the gas supply line of the heating or measuring member are drawn out. It is to form a groping sealed capsule provide creep test apparatus for the reactor made.

The detector is to provide a creep test apparatus for a nuclear reactor that is electrically connected to an electronic control device, a heating element of a heating element, and a line strain transducer to detect temperature and deformation.

The gas supply device is electrically connected to and controlled by the electronic control device, and communicates with the air compressor connected to the pipeline, the helium gas reservoir tank filled with the helium gas through the pipeline, and is disposed in the capsule in communication with the chamber in which the pressure member is installed. The present invention provides a creep test apparatus for a reactor connected to a gas supply line.

The present invention is carried out by installing a special capsule-type creep test apparatus in a tank filled with distilled water for the test creep test of the material used in the reactor.

In other words, by installing the fixing member of the creep test device vertically on the fixed base in the tank, the control device controls the detector according to the inputted information and controls the gas supply device while supplying the gas while heating the heating member. The pressing member is moved forward to expand the tension member to deform the interposed test piece.

At this time, the measuring member in contact with the tension member measures the creep deformation amount of the test material, and the control device recognizes the information through the detector and recognizes the information, and processes the data while the gas supply device controls the supply and discharge of the gas. You will be able to finish the test.

Hereinafter, with reference to the accompanying drawings a preferred embodiment of the present invention will be described in more detail.

1 is a view schematically showing the creep test apparatus according to the present invention, Figure 2 is a partially cut perspective view showing a creep test apparatus of the present invention.

And Figure 3 is a side cross-sectional view showing a creep test apparatus of the present invention, Figure 4 is a view showing a pressing member applied to the present invention.

5 is a view showing a tension member applied to the present invention, Figure 6 is a view showing a measuring member applied to the present invention.

7 is a view showing a heating member applied to the present invention, Figure 8 is a view showing a guide stopper applied to the present invention.

9 is a diagram showing the load-strain amount of the nuclear fuel cladding tube by the creep test apparatus of the present invention.

The reactor creep test apparatus (2) is a creep tester (6), which is a creep test means installed vertically in the reactor tank (4), and is electrically connected to the creep tester (6) to adjust the temperature and the amount of clip deformation of the test material. A gas supply device connected to the detector 10 to measure, the creep tester 6, and the gas supply line 12 to control the helium gas supply of the helium gas reservoir tank 14 to the air pressure of the air compressor 16. And a control device 20 which is electrically connected to the detector 10 and the gas supply device 18 and reads the input data while controlling by the previously inputted information.

The tank 4 is a part constituting a normal research reactor, filled with distilled water, and irradiated creep test of the reactor material is carried out, and the bottom surface is mounted on the fixed base 22 so that the creep tester 6 is installed on the bottom surface. Many grooves 24 are formed.

The creep tester 6 is composed of a holding member 26, a pressing member 28, a tension member 30, a heating member 32, a measuring member 34, a cylindrical capsule (36).

The fixing member 26 is a fixing means fixed by being assembled to the mounting groove 24 on the fixing base 22 provided in the irradiation creep test tank 4, and the base plate 38 provided at one end of the capsule 36. The fixed shaft 40 is protruded from the center of the base plate 38.

And a locking plate 42 slidably assembled to the fixed shaft 40, and a locking rod 44 which is divided in three directions from the locking plate 42 in a bending direction, and stops the locking plate 42. The elastic shaft 46 is firmly interposed between the fixed shaft 40.

The pressing member 28 is installed to be pressurized by the helium gas supplied to the chamber 48 provided on one side of the fixing member 26, and is fixed in the capsule 36 at regular intervals from the base plate 38. The corrugated pipe 52 is attached to the first plate 50 and the chamber 48 side of the first plate 50, and the corrugated pipe 52 pushes the tension member 30 integrally with the push plate ( 54).

The push rod 56 of the tension member 30 is assembled to the first plate 50 to form a slide hole 60 in the bush 58 interposed therebetween.

In addition, a push rod groove 62 is formed in the push plate 54 so that an accurate pressure is transmitted to the push rod 56 of the tension member 30.

Tensile member 30 is to tension the test material 64 by the operation of the pressing member 28, the first plate 50 is separated on the other side of the first plate 50 at a predetermined interval based on the horizontal line The first holder portion 66 and the second holder portion which is assembled to be slidably assembled to the first guide stopper 68 spaced apart from the first plate 50 while being partially assembled to the first holder portion 66. It is comprised by 70.

The first holder portion 66 includes a guide groove 72 formed on a horizontal line, an upper holder plate 76 having a plurality of upper fixing pin holes 74 formed on the upper side of the guide groove 72, and the upper portion thereof. The lower holder plate 80 is formed so as to face the lower side of the holder plate 76 and has a plurality of lower fixing pin holes 78 formed therein.

The second holder part 70 has a push rod 56 formed and assembled in a slide hole 60 of the first plate 50 with a predetermined length, and one end of the push rod 56 of the test material 64. The upper and lower fixed pin holes 86 and 88 to be fixed by the fixing pin 84 while the end of the U-shaped rod 82 and the one end of the U-shaped rod 82 are connected to each other is formed A cylindrical holder tube 90 having a plurality of poles) and a slide shaft 92 which protrudes on the axis line to slide the first guide stopper 68 on one side of the holder tube 90.

On the slide shaft 92, a measuring needle groove 98 is formed so that the measuring needle 96 of the linearly-strained differential transducer 94 is positioned in line with the axis line.

The first guide stopper 68 is interposed between an o-ring bearing 100 made of a carbon plate in order to reduce friction with the slide shaft 92.

The heating member 32 is installed in the tension member 30 to be installed to heat the material 64, the cylindrical heater housing 104 and the insertion hole 102 formed to be inserted into the U-shaped rod 82 from the side and In addition, the groove 106 formed with the gas supply line 12 interposed on the outer circumferential surface of the heater housing 104 and the silicon carbide embedded in the heater housing 104 and electrically connected to the detector 10 to generate heat. It consists of the heating element 108 of.

The measuring member 34 is installed to measure the amount of deformation of the material by detecting the retraction of the tension member 30, and with respect to the slide shaft 92 of the tension member 30 assembled to the first guide stopper 68. The linearly-strained differential transducer 94 is installed through the center of the second guide stopper 110 so as to coincide with the axis line, and is assembled to one end of the linearly-strained differential transducer 94 in contact with the slide shaft 92. It is made to include a fixed cap 114 is attached to the third guide stopper 112 to be installed.

The capsule 36 is formed in a chamber 48 in the first capsule 116 while the pressing member 28 is built in by the attachment of the fixing member 26 and the welding of the first plate 50. While the first guide stopper 68 is attached to the first capsule 116 to allow the interior and assembly of the tension member 30 to be welded, the heat transfer is blocked by the heat generation of the heating element and the helium gas is filled. The second capsule 118 is formed to be vacuum-formed to accelerate cooling by addition.

The third capsule 120 is welded to the second guide stopper 110 so that the measuring member 34 embedded in the second capsule 118 is installed on the center line. The fourth capsule 122 is welded to the third guide stopper 112 to which the fixed cap 114 to which the linear strain differential transducer 94 is assembled is attached.

In addition, the third guide stopper 112 of the fourth capsule 122 has a porous shape to maintain airtightness when the wires of the heating member 32 or the measuring member 34 and the gas supply line 12 are drawn out. It consists of the sealing capsule 126 which installed the seal plate 124 in double.

The detector 10 is a conventional technique, and is electrically connected to the control device 20, the silicon carbide heating element 108 of the heating member 32, and the linear strain differential transducer 94 to detect temperature and deformation amount. It is a device.

In addition, since the detector 10 is electrically connected to the silicon carbide heating element 108 and the linear strain differential transducer 94, the wires 128 are disposed in the capsule 36.

The gas supply device 18 is applied to the conventional technology, and is electrically connected to the control device 20, the air compressor 16 is connected to the pipeline 130 and the helium gas filled helium gas reservoir tank In communication with (14), the pressure member 28 is connected to the gas supply line 12 disposed in the capsule 36 to communicate with the chamber 48 is provided.

A plurality of gas supply lines 12 are installed so that all of the first and second pipes 132 and 134 are used to supply helium gas, and one of the first and second pipes 132 and 134 is discharged. The air is supplied through the conduit and the helium gas is returned to the helium gas reservoir tank 14 through the other conduit.

The first plate 50 is attached to the first capsule 116 by welding, and a plurality of gas supply lines 12 are connected to each other.

The first guide stopper 68 is installed in the second capsule 118, and extends in four directions between the first rib 136 welded to the inner circumferential surface of the capsule 36, and between the first rib 136. A first space portion 138 is formed, and an electric wire connected to the gas supply line 12 and the heating member 32 is disposed through the first space portion 138.

And in order to prevent the separation of the bearing 100 interposed in order to reduce the friction with the slide shaft 92 assembled to the first guide stopper 68, a fixing plate 140 is provided.

The second guide stopper 110 is installed in the third capsule 120, and extends in four directions, between the second rib 142 welded to the inner circumferential surface of the capsule 36, and between the second rib 142. The second space portion 144 is formed, and the wires connected to the gas supply line 12 and the heating member 32 are arranged through the second space portion 144.

The third guide stopper 112 is installed in the fourth capsule 122 and extends in four directions between the third rib 146 welded to the inner circumferential surface of the capsule 36, and between the third rib 146. A third space portion 148 is formed, and an electric wire connected to the gas supply line 12 and the heating member 32 is disposed through the third space portion 148.

The test material 64 shown in the present invention only illustrates the material for the reactor, and the material fixing holes 150 are formed on both sides to be fixed by the fixing pin 84, and various shapes and types of materials Adoptable.

The operation of the present invention made as described above is briefly described first, and is carried out by installing a special capsule type creep tester 6 in a tank 4 filled with distilled water for irradiation creep test.

That is, the fixing device 26 of the creep test apparatus 2 is installed vertically on the fixed base 22 in the water tank 4 so that the controller 20 controls the detector 10 by the previously inputted information. When the heating member 32 generates heat, and the gas supply device 18 is controlled to supply helium gas, the press member 28 moves forward by the gas pressure to expand the tension member 30, thereby interposing the test material. Deform by applying load to (8).

At this time, the measuring member 34 in contact with the tension member 30 measures the creep deformation amount of the test material 8, and the control device 20 recognizes the information of the detector 10 and doubles it and processes it as data. While the gas supply device 18 controls the supply and discharge of the gas can be completed the test.

In more detail, the operation of the creep test apparatus 2 will be described in detail. The first holder part may be interposed between the U-shaped rods 82 of the tension member 30 before completion of the creep tester 6. 66) and the holder tube 90 and then the fixing pin 84 is inserted and fixed through the upper and lower fixing pin holes 74 and 78 to pass through the fixing hole 150 of the material.

Then, after assembling through the insertion hole 102 of the heater housing 104 to the U-shaped rod 82 between the first holder portion 66 and the holder tube 90, the fixing member 26, the pressing member 28 ), The tension member 30, the measuring member 34 in the first, 2, 3, 4 capsules 116, 118, 120, 122 using the built-in, on one side of the fourth capsule (122) The sealing capsule 126 is formed and attached and formed by welding or the like to complete the creep tester 6.

Accordingly, when the creep test device 2 is operated, the control device 20 controls the gas supply device 18 according to the previously inputted information, so that the first and second pipes 132, which are the plurality of gas supply pipes 12, are formed. Through 134, helium gas of the helium gas reservoir tank 14 is supplied to the chamber 48 at high pressure.

The high-pressure helium gas supplied to the chamber 48 provided in the first capsule 116 pushes the push plate 54 to push the push rod 56 of the tension member 30, and thus the first holder part 66 and the first holder part 66. The test material 64 fixed to the holder tube 90 by the fixing pin 84 is subjected to a tensile force.

At the same time, power is applied to the silicon carbide heating element 108 of the heating member 32 through the detector 10 as a control signal of the control device 20 to generate heat, and the gas supply device 18 generates helium gas at high pressure. In order to be supplied to the chamber 48 through the first and second pipes 132 and 134 of the gas supply pipe 12.

At this time, the high-pressure helium gas is supplied to form a low temperature gas supply line 12 and the heater housing 104 of the heating member 32 is inserted into the groove 106 of the outer circumferential surface of the heating member ( The function of preventing the overheat of the 32 is electrically connected to the detector 10 to display the temperature of the heating member 32, the temperature data is input to the control device 20.

The temperature sensor (T) can be installed on the surface of the specimen, and the temperature sensor (T) measures the temperature of the specimen.

It is connected to the temperature sensor control device 20 to adjust the output of the heating member 32, and repeatedly adjust the temperature sensor measurement temperature and the output of the heating member 32 to adjust the desired experimental temperature.

Increasing the helium gas pressure increases the heat transfer to lower the temperature, and lowering the helium gas pressure decreases the heat transfer to increase the temperature.

In other words, helium gas is supplied through the gas supply line 12 when the test material 64 is tensioned, and at the same time, the heating element 108 of the silicon carbide material of the heating member 32 is also supplied through the detector 10. Therefore, the operation to maintain the heating state is made continuously at about the same time.

In addition, before or after the creep test, the gas supply device 14 and the detector 10 are controlled by the control device 20 to switch to the initial state before the creep test.

On the other hand, when the test material 64 is tensioned by the operation of the tension member 30 to generate a deformation amount, the slide shaft 92 of the tension member 30 is moved to the right by the first guide stopper 68 and measured. The measuring needle 96 of the linearly strained differential transducer 94 constituting the member 34 is pushed.

If both ends of the capsule 36 are cut, the creep test portion is separated.

Therefore, the test material 64 is fixed to the holder portion 66, 70 by the fixing pin 84, so that the separation is easy.

Accordingly, the linear deformation transducer 94 is in a state of being electrically connected to the detector 10, so that the detector 10 recognizes the deformation amount of the test material, and the data of the deformation amount is input to the control device 20. The creep test results can then be read.

In addition, it is also possible to measure the deformation amount of the test material having various lengths and shapes by adjusting the length of only the slide shaft 92 formed on the tension member 30.

Through the creep test apparatus 2 made as described above, it can be seen that the load-strain curve obtained by the creep test of the fuel cladding tube in addition to the creep test of the test material can be obtained exactly as shown in FIG. 9. Will be.

When developing materials for reactors, it is possible to test materials of various shapes.

The present invention has the effect that the irradiation is effectively carried out uniformly to the GAUGE LENGTH of the test material during the irradiation test.

In addition, there is an effect to facilitate the mechanical fabrication of the components to apply the load to the specimen during the irradiation test and measure the amount of deformation is made of a minimum number of parts to minimize the nuclear waste after the irradiation test.

It is easy to separate and cut the test material in the hot cell and the test material is not damaged in the separation process by cutting.

The mechanical structure that loads the test material has the effect of achieving stability without being affected by the irradiation.

The test effect of the specimen is maximized.

It is effective to test tension specimens of various sizes and shapes.

There is an effect that can control the heating and cooling of the specimen.

The capsules are divided into pieces to maintain airtightness, thereby increasing safety as shielding is maintained when breakage due to decomposition cutting occurs.

The present invention is not limited to the first embodiment, and various design changes are possible in accordance with the technical idea of the present invention.

Claims (13)

delete A fixing member assembled and fixed to the irradiation creep test tank, A pressurizing member installed to pressurize by supplying pressurized gas to one chamber of the fixing member, A tension member installed to tension the test material by the operation of the pressure member; A heating member assembled to the tension member and installed to heat the test material; A measuring member for detecting a retraction of the tension member and measuring a creep deformation amount; A creep test means formed of a plurality of columnar capsules installed in the order of the pressing member, the tension member, the heating member, and the measuring member while the fixing member is formed at one end thereof; A detector electrically connected to the creep test means for measuring temperature and clip deformation amount of the specimen; A gas supply device connected to the creep test means and a gas supply line to control the supply of helium gas in the helium gas reservoir tank by the air pressure of an air compressor; And a control device electrically connected to the detector and a gas supply device to read the input data while controlling by the previously inputted information. 3. The fixing member according to claim 2, wherein the fixing member includes a base plate provided at the lower end of the capsule, a fixing shaft protruding from the center of the base plate, a latch portion slidably assembled to the fixing shaft, and between the latch portion and the base plate. A creep test apparatus for a nuclear reactor, characterized in that consisting of an elastic member interposed therebetween. 3. The pressure member according to claim 2, wherein the pressing member is integrally formed with a first plate fixed to the capsule at regular intervals while forming a chamber on one side from the base plate, a corrugated pipe attached to one side of the first plate, and one side of the corrugated pipe. A creep test apparatus for a nuclear reactor characterized in that it comprises a push plate mounted. 5. The creep test apparatus of claim 4, wherein the push plate is formed by forming a push rod groove in contact with the push rod of the tension member. The first plate part of claim 2, wherein the tension member is formed on the other side of the first plate with a first holder part divided up and down at regular intervals on a horizontal line, and the first plate part is partially overlapped with the first plate part. Creep test apparatus for a nuclear reactor, characterized in that consisting of a second holder portion which is assembled to slide the first guide stopper attached to the capsule spaced apart from a predetermined interval. 8. The lower portion of the first holder portion comprises: a guide groove formed on a horizontal line, an upper holder plate having a plurality of upper fixing pin holes formed on an upper side thereof based on the guide groove, and a lower portion formed facing the lower side of the upper holder plate. Reactor creep test apparatus comprising a lower holder plate formed with a plurality of pin pin holes. The method of claim 7, wherein the second holder portion is a push rod which is formed and assembled in a slide hole of the first plate to a certain length, and a U-shaped rod formed so that one end of the push rod is interposed of the test material, One end of the rod is connected to the cylindrical holder tube to form a plurality of upper and lower fixed pin holes so that the test material is fixed by the fixing pins, and a slide shaft that protrudes in an axial line to slide the first guide stopper on one side of the holder tube. Creep test apparatus for the reactor, characterized in that formed by. 9. The reactor creep test apparatus according to claim 8, wherein a measuring needle groove of the linearly-strained differential transducer is formed on the slide shaft so that the measuring needle groove is positioned on the axis line. The reactor creep test apparatus according to claim 8, wherein the first guide stopper is formed via a bearing member to reduce friction with the slide shaft. 3. The heater according to claim 2, wherein the heating member includes a circular heater housing having an insertion hole formed to be inserted into the U-shaped rod from the side, a plurality of grooves having a gas supply line interposed on the outer circumferential surface of the heater housing, and a detector in the heater housing. A creep test apparatus for a nuclear reactor characterized in that it comprises a heating element which is installed while being electrically connected. The straight line of claim 2, wherein the measuring member is installed in an axis line with respect to the slide axis of the tension member which is electrically connected to the detector and penetrates the center of the second guide stopper attached to the capsule and is assembled to the first guide stopper. And a cap which is attached to one side of the third guide stopper attached to the capsule while being assembled at one end of the linear differential differential transducer. 3. The capsule of claim 2, wherein the capsule is circumferentially formed with a first capsule having a chamber formed by attaching the fixing member and welding the first plate, and forming a chamber, and assembling with the interior of the tension member while attaching to the first capsule. The second guide capsule is vacuum-formed by the first guide stopper which enables this to be welded to accelerate heat transfer by blocking the heat transfer to the outside due to the heat generation of the heating element and the addition of the filling by the helium gas, and the second capsule. The third guide stopper is formed by welding the second guide stopper to be attached to the capsule is installed on the center line, and the third guide stopper attached to the third capsule attached to the fixed cap assembled with the laser measuring device The fourth capsule formed by welding, and the third guide stopper of the fourth capsule, a porous seal plate for maintaining airtightness when the wires of the heating member or the measuring member and the gas supply pipe are drawn out. Creep test device for reactor, characterized by yirueojim to form a sealed capsule by installing the tree.