KR20170060677A - Apparatus for reactor neutron activation analysis - Google Patents

Apparatus for reactor neutron activation analysis Download PDF

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KR20170060677A
KR20170060677A KR1020150165117A KR20150165117A KR20170060677A KR 20170060677 A KR20170060677 A KR 20170060677A KR 1020150165117 A KR1020150165117 A KR 1020150165117A KR 20150165117 A KR20150165117 A KR 20150165117A KR 20170060677 A KR20170060677 A KR 20170060677A
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sample
compressed nitrogen
reactor
pipe
nitrogen tank
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KR1020150165117A
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김영주
김영철
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(주) 에이치와이엔지니어링
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Publication of KR20170060677A publication Critical patent/KR20170060677A/en

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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/22—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material
    • 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
    • G01J—MEASUREMENT OF INTENSITY, VELOCITY, SPECTRAL CONTENT, POLARISATION, PHASE OR PULSE CHARACTERISTICS OF INFRARED, VISIBLE OR ULTRAVIOLET LIGHT; COLORIMETRY; RADIATION PYROMETRY
    • G01J1/00—Photometry, e.g. photographic exposure meter
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/22—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material
    • G01N23/2204—Specimen supports therefor; Sample conveying means therefore
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/22—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material
    • G01N23/223—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material by irradiating the sample with X-rays or gamma-rays and by measuring X-ray fluorescence
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/07—Investigating materials by wave or particle radiation secondary emission
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/10—Different kinds of radiation or particles
    • G01N2223/101—Different kinds of radiation or particles electromagnetic radiation
    • G01N2223/1013—Different kinds of radiation or particles electromagnetic radiation gamma
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/10—Different kinds of radiation or particles
    • G01N2223/106—Different kinds of radiation or particles neutrons
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/30—Accessories, mechanical or electrical features
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2223/00—Investigating materials by wave or particle radiation
    • G01N2223/50—Detectors

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Abstract

The present invention relates to a radioactive decay analysis apparatus, and more particularly, to a radioactive decay analysis apparatus that includes a loader on which a sample put into a reactor is placed, a receiver in which a sample discharged from the atom is accommodated, A sample feed pipe connected to the loader and a sample feed pipe connected to the receiver are connected to each other, and a diverter for controlling opening and closing of the sample feed pipe and the common pipe, opening and closing of the sample extraction pipe and the common pipe, A movement detection sensor provided in the common pipe for detecting the supply of the sample to the reactor, and a sensor for detecting the arrival of the sample in the neutron irradiation tube of the reactor, Wherein the neutron irradiation time of the sample in the neutron irradiation (start time) By being preset with the arrival time of the sample detected by the sound detector, it provides the advantage to improve the accuracy of analysis.

Figure P1020150165117

Description

[0001] APPARATUS FOR REACTOR NEUTRON ACTIVATION ANALYSIS [0002]

BACKGROUND OF THE INVENTION 1. Field of the Invention [0002] The present invention relates to a radioactivity analyzer, and more particularly, to a radioactivity analyzer capable of accurately measuring neutron irradiation time and improving the accuracy of analysis results.

In general, it is essential in all R & D and industrial fields to determine the composition of a sample or its content by applying analytical science and developed analytical methods that develop a methodology for observing a substance at the nuclear, atomic, and molecular levels. Various methods of analysis have been developed and applied for this purpose.

Neutron activation analysis technology is an elemental analysis technique introduced in 1936 when the presence and use of radiation and isotopes is known. Since it has a unique characteristic different from chemical analysis, it can be applied to materials, environment, health, industry and society It is applied to a wide range of fields such as cultural fields. Since the construction of TRIGA research reactor in Korea in 1962, it has been used for national research and development. After the construction of 'Hanaro' in 1995, a high accuracy analysis device and facility for securing maximum measurement capability and user utilization, Technology development.

Neutron activation analysis is a representative method of nuclear analysis technology. When an unknown sample is irradiated with a neutron of a reactor, radioactive nuclei are generated and gamma rays are emitted during the collapse process. During the irradiation of neutrons, the gamma rays emitted from the excited complex nuclei and the gamma rays emitted from the decay of the radioactive nuclei generated after the irradiation of the neutrons are measured are used to quantify the constituent elements. It is called INAA.

The number of gamma rays having a specific energy per unit time emitted from the target nuclide generated by the nuclear reaction is proportional to the content of the stable nuclide in the sample and the neutron flux, so that the element content of the unknown sample can be obtained from the determined analysis conditions.

The general procedure for such neutron activation analysis is to prepare a sample, irradiate neutrons, measure gamma rays, and analyze the spectrum to analyze and evaluate the data of the sample contents.

In this neutron activation analysis method, the instrument neutron activation analysis apparatus is provided with an investigation tube for radiating the sample to the neutron inside the reactor, and an entrance and exit port and a transfer device for drawing or withdrawing the sample to the investigation tube are formed.

Then, the worker draws the sample to be analyzed through the drawing inlet into the inside of the inspection tube, and when the sample is irradiated with neutrons, the operator takes out the sample from the inspection tube and continuously inputs a new sample.

However, in spite of the fact that it is very important to irradiate the sample with neutrons for such analysis, a manual measurement method using a stopwatch is currently used as a method of measuring the neutron irradiation time of the sample.

The manual measurement method of the operator generates a predetermined error according to the individual difference, and the error of the neutron irradiation time finally results in the deterioration of the accuracy of the analysis result.

SUMMARY OF THE INVENTION It is an object of the present invention to provide a radioactive decay analyzer with improved accuracy by measuring the neutron irradiation time more precisely.

A preferred embodiment of the apparatus for analyzing radioactivity according to the present invention comprises a loader on which a sample put in a reactor is placed, a receiver in which a sample discharged from the atom is accommodated, and a path through which the sample is supplied to or withdrawn from the reactor A common pipe, a sample supply pipe connected to the loader, and a sample discharge pipe connected to the receiver are connected to each other, and the sample supply pipe and the common pipe are opened and closed, and the sample withdrawal pipe and the common pipe are opened / A sensor for detecting the supply of the sample to the reactor, and a sensor for detecting the arrival of the sample in the neutron detector provided in the reactor of the reactor, And a time of neutron irradiation time for the sample in the neutron irradiation Is set as an arrival time point of the sample sensed by the sound sensing unit.

Here, the common pipe has a drop pipe bent to allow the sample to freely fall from the upper side of the reactor, and the movement detection sensor and the sound detection unit are disposed at a position before the sample is supplied and dropped through the fall pipe .

In addition, if the sample falls freely through the drop pipe, the stopper may be provided in the neutron irradiator to generate a predetermined impact sound through impact with the sample.

The sound sensing unit may include a pair of electrodes and a charge storage material positioned between the pair of electrodes and storing a predetermined charge. The pair of electrodes may be formed by a sound wave generated upon arrival of the sample, The arrival of the sample can be detected from a change in vibration capacity between the electrodes.

The sound sensing unit may further include a microphone for generating the vibration capacitance change as an electrical signal, and a sound sensor controller for receiving the electrical signal.

Also, the microphone may be an ICP type sensor.

The acoustic sensing unit may include an ICP amplifier for collecting and amplifying the electrical signal from the microphone, a low pass filter (Low pass filter) for filtering the signal amplified by the IC amplifier into a signal of 5 kHz band, And a bandpass filter and an amplifier for extracting only a signal in a band of 3 to 4 kHz by filtering the signal filtered through the low-pass filter.

A first compression gas supply line for supplying a compressed nitrogen gas to the loader; a first gas supply pipe for connecting the loader and the first compressed nitrogen tank; Further comprising a nitrogen tank and a second gas supply line connecting the neutron irradiator and the second compressed nitrogen tank, wherein the first compressed nitrogen tank is operative to supply the sample to the reactor, The nitrogen tank may operate to withdraw the sample from the reactor.

A first supply valve provided in the first gas supply pipe for opening and closing the supply of compressed nitrogen gas from the first compressed nitrogen tank and a second supply valve provided in the second gas supply pipe, And a second supply valve provided in the second gas supply pipe for discharging the compressed nitrogen gas supplied from the first compressed nitrogen tank when the sample is supplied to the reactor, And a second exhaust valve provided in the sample withdrawal pipe for interrupting exhaust of the compressed nitrogen gas supplied from the second compressed nitrogen tank when the sample is withdrawn from the reactor And when the sample is supplied from the loader to the reactor, the first compressed nitrogen tank is turned on, the first exhaust valve is controlled to open, The second compressed nitrogen tank may be turned off, and the second exhaust valve may be controlled to be closed.

Further, when the sample is taken out from the reactor to the receiver, the first compressed nitrogen tank is turned OFF, the first exhaust valve is controlled to be closed, and the second compressed nitrogen tank is operated ON ), And the second exhaust valve can be controlled to open.

Further, the second supply valve may be an electronically controlled solenoid valve.

In addition, the movement sensor may be an optical sensor for sensing a change in illuminance caused by a moving object.

Further, when the first supply valve supplies the sample from the loader to the reactor, when the sample is detected by the optical sensor, the first supply valve may be controlled to be closed.

According to a preferred embodiment of the activation analyzer according to the present invention, the accuracy of the analysis can be improved by precisely detecting the time (initial period) of the neutron irradiation time of the neutron irradiator.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a structural diagram showing a preferred embodiment of the activation analysis apparatus according to the present invention,
FIG. 2 is a detailed view showing an acoustic sensing unit and a neutron irradiation tube in the configuration of FIG. 1,
FIG. 3 is a waveform chart analyzing a sample arrival time through the sound sensing unit of FIG. 1,
FIG. 4 is an analysis chart for analyzing a sample arrival time through the sound sensing unit of FIG. 1,
FIG. 5 is a structural diagram showing a sample supply process of the activation analysis apparatus according to the present invention,
6 is a structural view showing a sample withdrawing process of the activation analyzer according to the present invention.

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

FIG. 1 is a structural view showing a preferred embodiment of the activation analyzer according to the present invention, FIG. 2 is a detailed view showing a constituent acoustic sensor and a neutron detector tube of FIG. 1, FIG. 3 is a cross- FIG. 4 is an analysis chart for analyzing the sample arrival time through the sound sensing unit of FIG. 1; FIG.

Referring to FIG. 1, the radiative analysis apparatus 1 according to an embodiment of the present invention includes a radiological analysis building I having a configuration in which a sample (not shown) is supplied, drawn, A reactor (30) for analyzing the sample can be placed in both buildings separated by a building (II).

The loader 10 is placed in the radioactivity analysis building I, and the sample put into the reactor 30 is settled.

The first compressed nitrogen tank 50 is disposed at one side of the loader 10 and supplies compressed nitrogen gas to the loader 10 through the first gas supply pipe 55. The compressed nitrogen gas compressed and stored in the first compressed nitrogen tank 50 is controlled to be supplied to and blocked from the loader 10 by the opening and closing operation of the first supply valve 51 provided in the first gas supply pipe 55 . When the compressed nitrogen gas is supplied from the first compressed nitrogen tank 50 to the loader 10, the sample placed on the loader 10 is transported toward the reactor 30.

The diverter 20 is connected to the loader 10 via a sample supply pipe 15 on one side and the sample discharge pipe 43 is connected to the sample supply pipe 15 adjacent thereto.

The receiver (40) is connected to the sample extraction pipe (43) to receive the drawn sample.

A second exhaust pipe (45) is formed at one side of the sample extraction pipe (43). A second exhaust valve 41 is provided in the second exhaust pipe 45 to interrupt the exhaust of the compressed nitrogen gas supplied for withdrawing the sample from the second compressed nitrogen tank 60 to be described later.

The diverter 20 is connected to the reactor 30 through a common pipe 35 common to the loader 10 and the receiver 40 as a path through which the sample is supplied to or withdrawn from the reactor 30. [

The common pipe 35 is formed with a drop pipe 37 bent at the upper side of the reactor 30 so that the sample supplied through the diverter 20 and dropped freely toward the reactor 30.

When the compressed nitrogen gas compressed and stored in the first compressed nitrogen tank 50 is supplied to the loader 10 through the first gas supply pipe 55, the sample is supplied to the diverter 20 through the sample supply pipe 15 And is then introduced into the reactor 30 through the common pipe 35 again.

The reactor 30 to which the common pipe 35 is connected may include a reactor core 31 and a neutron irradiation tube 70 located inside the reactor core 31 as shown in FIG.

It is understood that the preferred embodiment of the activation analysis apparatus 1 according to the present invention is limited to the research reactor 30. Since the research reactor 30 is not a reactor 30 that produces electricity, the heat generated here is dissipated to the outside as much as possible. Therefore, it is generally preferable to have a shape of a pool type reactor 30, and the reactor core 31 is different depending on the mold shape, but is preferably located at a depth of about 7 to 13 meters of water.

2, the neutron irradiation pipe 70 is connected to a dropping pipe 37 of the common pipe 35 through a sample inlet pipe 71 and a second compressed nitrogen tank 60, A gas supply pipe 72 to which a gas is supplied is provided in parallel vertically and horizontally.

A second compressed nitrogen tank (60) for supplying compressed nitrogen gas through the second gas supply pipe is provided outside the reactor (30).

The second gas supply line 67 is provided with second supply valves 61A and 61B as shown in Figures 1 and 2 so that the compressed nitrogen gas from the second compressed nitrogen tank 60, (70). ≪ / RTI > The second gas supply pipe 67 may have a first exhaust pipe 65 as shown in Fig. The first exhaust pipe 65 is provided with a first exhaust valve 63 so as to intermit the exhaust of the compressed nitrogen gas supplied for the supply of the sample from the first compressed nitrogen tank 50.

The second supply valves 61A and 61B are preferably electronically controlled solenoid valves. This is because more accurate control can be performed by a control unit (not shown). The control unit is typically capable of controlling the operation of the controllable element to control the overall operation of the apparatus. Also, the control unit can perform the activation analysis using the values measured by the movement detection sensor, the sound sensing unit, and the like. Hereinafter, the control unit may be used in combination with the radiative analysis apparatus.

The common pipe 35 may include a movement detection sensor 80 for sensing the supply of the sample to the reactor 30. [ The common pipe 35 may further include an acoustic sensing unit 90 for sensing the arrival of the sample to the neutron irradiation pipe 70 provided in the reactor 30.

This is because the reactor core 31 described above has a neutron scattered by fission and various kinds of radiation, and thus it is difficult to directly install any measurement device due to strong radiation. Particularly, since the research reactor 30 is designed to produce a good thermal neutron, it is not desirable to install any metallic structures that inhibit it, and parts such as electrical devices, including sensors, This is because the insulated state can not be maintained due to damage of the wire covering material or the like.

It is preferable that the movement detection sensor 80 and the sound sensing portion 90 are provided at a position before the drop pipe 37 bent in the common pipe 35 so that the sample falls freely as described above.

The movement detection sensor 80 may be provided with an optical sensor for detecting a change in illuminance caused by a moving object (i.e., a sample). However, in a preferred embodiment of the activation analyzer 1 according to the present invention, the movement sensor 80 is not necessarily provided as an optical sensor, and any sensor capable of detecting the passage of the sample may be used. It will be appreciated that the present invention is not limited thereto.

The movement detection sensor 80 transmits a signal for shutting off the first supply valve 51 to the control unit so that the compressed nitrogen gas is not supplied from the first compressed nitrogen tank 50 when the movement of the sample is detected.

The sound sensing section 90 can provide a period of the neutron irradiation time for accurately detecting the neutron irradiation time of the sample supplied to the neutron irradiation pipe 70 of the reactor 30 .

More specifically, it is already well known that when a sample is irradiated with neutrons, all the chemical elements of the material are radiated, and the extra energy is converted into a stabilized element by releasing the specific radiation exclusively of the element to the outside . At this time, when the measured radiation is analyzed by energy, the chemical element can be known, and the amount of the element can be known by measuring the radiation amount.

The radioactivity of the sample irradiated with the neutron can be obtained by the following formula.

Equation 1

A = N * φ th * δ * (1 - ε - λΤ) * ε - λt

here,

N = number of atoms in the sample = (weight of the sample * abundance ratio * number of Avogadro) / number of atomic mass

A = radioactivity

φ th = Thermal Neutron Flux

δ = neutron absorption cross section

λ = decay constant

T = neutron irradiation time

t = radiation cooling time

When neutrons are irradiated with radioactivity using a multi-channel analyzer, neutrons emitted by the neutrons emit extra energy as their own energy. By finding the atom, we can know the weight by calculating the total amount of Peak by substituting it into the above formula.

Therefore, neutron irradiation time is a necessary factor because it is necessary to know the amount of radioactivity irradiated to the neutron, and it is natural that the neutron irradiation time affects the analysis result. Particularly, in the case of analyzing the sample in very small amount (PPm unit) The error may be large.

The sound sensing unit 90 can clearly reduce the error in the above-described sample analysis by clearly providing the period (initial period) of the neutron irradiation time.

More specifically, the sound sensing unit 90 senses the arrival of the sample in the neutron irradiation pipe 70 provided in the reactor 30 by sound.

2, when the sample supplied through the common pipe 35 is sensed by the movement detection sensor 80, the first supply valve 51 is closed by the compressed nitrogen gas from the first compressed nitrogen tank 50, The sample is slowly dropped to the bottom of the neutron irradiation pipe 70 by its own weight through the drop pipe 37 of the supply pipe.

Here, a stopper 73 is provided at the bottom of the neutron irradiation pipe 70. When a sample is dropped on the stopper 73 of the neutron irradiation pipe 70, a predetermined impact sound is generated, and the impact sound is detected by the sound detection unit 90 This point can be obtained at the beginning of neutron irradiation time (beginning).

4, the sound sensing unit 90 includes a pair of electrodes 91A and 91B and a charge storage material 92 (hereinafter, referred to as " electrode ") that is located between the pair of electrodes 91A and 91B and stores a predetermined charge. , And the arrival of the sample can be detected from a change in vibration capacity between the pair of electrodes 91A and 91B due to the sound waves of the predetermined impact sound to the stopper 73 of the sample.

The sound sensing unit 90 may further include a microphone 93 for generating an electrical signal by changing the vibration capacity and a sound sensor controller 94 for receiving an electrical signal.

The microphone 93 is preferably adopted as an ICP-type microphone 93 having stability of long-distance signal transmission in order to transmit the collected signal to a remote acoustic sensor controller 94.

An electric signal of the microphone 93 is input to an ICP amplifier (Integrated Circuit Piezoelectric Amplifier) 95 for driving an ICP type sensor and collecting an electric signal, and an IC amplifier 95 The electrical signal of the microphone 93 outputted through the microphone 93 is removed through the low pass filter 96 of the 5 kHz band and the band pass filter 97 of 3-4 kHz. And an amplifier 97 (Amp) are used to extract only signals in the 3 to 4 kHz band.

The presence or absence of actual sound waves in the extracted signal is determined by using a comparator as shown in FIG. 3. The signal output through the comparator drives a relay to generate a contact signal PTS (Pneumatic Transfer System) is transferred to the PLC of the control panel and applied to the entire sequence.

In this way, the precise period of the neutron irradiation time obtained through the sound sensing unit 90 can be greatly reduced by manually measuring the stopwatch or the like.

FIG. 5 is a structural view illustrating a sample supply process of the activation analysis apparatus 1 according to the present invention, and FIG. 6 is a structural diagram illustrating a sample withdrawal process of the activation analysis apparatus 1 according to the present invention.

The process of supplying and withdrawing the sample through the activation analyzer 1 according to the present invention will be briefly described below.

First, a process of supplying a sample from the loader 10 to the reactor 30 will be described with reference to FIG.

5, a control unit (not shown) controls the flow of the compressed nitrogen gas from the first compressed nitrogen tank 50 through the first gas supply pipe 55 in order to transfer the sample from the loader 10 to the reactor 30. [ And the supplied compressed nitrogen gas is controlled to open the first exhaust valve 63 so as to be exhausted through the first exhaust pipe 65.

Hereinafter, the second supply valves 61A and 61B are provided with one (hereinafter, referred to as 'one second supply valve 61A') at one side of the second gas supply pipe 55 with the first exhaust pipe 65 branched, (Hereinafter referred to as the "second supply valve 61B"). When the sample is supplied from the loader 10 to the reactor 30, the other second supply valve 61B is provided on the other side The valve 61A is controlled to be opened and the other second supply valve 61B is controlled to be closed.

In this state, the sample moves from the loader 10 to the diverter 20 through the sample supply pipe 15 by the driving force of the compressed nitrogen gas, and the diverter 20 moves the sample to the reactor 30 .

When the sample passes through the divertor 20 and passes through the common pipe 35 and is detected by the movement detection sensor 80, the first supply valve 51 is shut off controlled so as to stop the supply of the further compressed nitrogen gas, The sample drops freely from the drop pipe 37 of the supply pipe by its own weight and falls freely into the sample injection pipe 71 of the neutron irradiation pipe 70 and impacts with the stopper 73 to generate a predetermined sound wave (impact sound). At this time, the time (start) of the neutron irradiation time is measured by the sound sensing unit 90, and the analysis of the accurate sample can be completed.

Next, the process of withdrawing the sample from the reactor (30) will be described.

The control unit controls the supply of the compressed nitrogen gas from the second compressed nitrogen tank 60 through the second gas supply pipe in order to transfer the sample from the inside of the neutron irradiation pipe 70 to the receiver 40. [ The valves 61A and 61B are opened and the supplied compressed nitrogen gas is controlled to open the second exhaust valve 41 so as to be exhausted through the second exhaust pipe 45. [ At this time, it is preferable that the first supply valve 51 and the first exhaust valve 63 are controlled to be closed, and both the one second supply valve 61A and the other second supply valve 61B are controlled to open.

In this state, the sample is reversely propelled to the diverter 20 through the common pipe 35 by the propulsion force of the compressed nitrogen gas from the inside of the neutron investigating tube 70, and the diverter 20 moves the receiver 40, So as to move the sample.

The sample passes through the diverter 20 and then flows to the receiver 40 via the sample withdrawal pipe 43. The sample falls freely from the upper side of the receiver 40 by its own weight and is received in the receiver 40, The compressed nitrogen gas is exhausted through the second exhaust pipe (45).

According to a preferred embodiment of the present invention, the arrival time of a sample dropped freely into the neutron irradiation pipe 70 is accurately detected through the sound sensing unit 90, By adopting the sensing time of the sensing unit 90 as the neutron irradiation time, the analyzing accuracy of the sample can be improved.

Hereinafter, a preferred embodiment of the present invention will be described in detail with reference to the accompanying drawings. However, it should be understood that the embodiments of the present invention are not necessarily limited to the above-described preferred embodiments, and that various modifications and equivalents may be made by those skilled in the art something to do. Therefore, it is to be understood that the true scope of the present invention is defined by the appended claims.

1: Radioactivity analysis apparatus 10: Loader
20: diverter 30: reactor
40: Receiver 50: First compressed nitrogen tank
60: Second Compression Nitrogen Tank 70: Neutron Investigation Tube
80: movement detection sensor 90: sound detection unit

Claims (10)

A loader on which a sample put into the reactor is seated;
A receiver for receiving a sample discharged from the atom;
Wherein the sample piping is connected to a common pipeline that is a path through which the sample is supplied to or withdrawn from the reactor, a sample supply piping connected to the loader, and a sample withdrawal piping connected to the receiver, A diverter controlling the opening and closing of the pipe and the common pipe;
A movement detection sensor provided in the common pipe and sensing a supply of the sample to the reactor; And
And an acoustical sensing unit provided in the common pipeline for acoustically sensing arrival of the sample on a neutron irradiation pipe provided in the reactor,
Wherein the neutron irradiation time of the sample in the neutron irradiation is set to an arrival time of the sample sensed by the sound sensing unit. The method according to claim 1,
Wherein the common piping has a drop pipe bent to allow the sample to freely fall from above the reactor,
Wherein the movement detection sensor and the sound sensing unit are disposed at a position before the sample is supplied and dropped through the fall pipe. 3. The method of claim 2,
And a stopper disposed in the neutron irradiating tube to generate a predetermined impact sound through impact with the sample when the sample drops freely through the drop pipe. 4. The method according to any one of claims 1 to 3,
The sound-
A pair of electrodes;
A charge storage material positioned between the pair of electrodes and storing a predetermined charge;
A microphone for generating the vibration capacity change as an electrical signal; And
And an acoustic sensor controller for receiving the electrical signal,
And detecting the arrival of the sample from a change in vibration capacitance between the pair of electrodes due to a sound wave generated upon arrival of the sample. 5. The method of claim 4,
The microphone is an ICP type sensor,
The sound-
An ICP amplifier for collecting and amplifying the electrical signal from the microphone;
A low pass filter for filtering the signal amplified by the IC amplifier with a signal of a 5 kHz band;
Further comprising a bandpass filter and an amplifier for extracting only a signal in a band of 3 to 4 kHz by filtering the signal filtered through the low-pass filter. The method according to claim 1,
A first compressed nitrogen tank for supplying compressed nitrogen gas to the loader;
A first gas supply pipe connecting the loader and the first compressed nitrogen tank;
A second compressed nitrogen tank for supplying a compressed nitrogen gas to the neutron irradiation pipe; And
Further comprising a second gas supply line connecting the neutron irradiator and the second compressed nitrogen tank,
The first compressed nitrogen tank being operative to supply the sample to the reactor,
And the second compressed nitrogen tank is operative to withdraw the sample from the reactor. The method according to claim 6,
A first supply valve provided in the first gas supply pipe for opening and closing supply of compressed nitrogen gas from the first compressed nitrogen tank;
A second supply valve provided in the second gas supply pipe for opening and closing the supply of the compressed nitrogen gas from the second compressed nitrogen tank;
A first exhaust valve provided in the second gas supply pipe for interrupting exhaust of the compressed nitrogen gas supplied from the first compressed nitrogen tank when the sample is supplied to the reactor; And
Further comprising a second exhaust valve provided in the sample extracting pipe for interrupting the exhaust of the compressed nitrogen gas supplied from the second compressed nitrogen tank when the sample is withdrawn from the reactor,
When the sample is supplied from the loader to the reactor, the first compressed nitrogen tank is turned ON, the first exhaust valve is opened, and the second compressed nitrogen tank is turned OFF And the second exhaust valve is controlled to be closed. 8. The method of claim 7,
When the sample is withdrawn from the reactor to the receiver, the first compressed nitrogen tank is turned OFF, the first exhaust valve is controlled to be closed, the second compressed nitrogen tank is turned ON And the second exhaust valve is open-controlled. 8. The method of claim 7,
Wherein the movement detecting sensor is a photosensor for detecting a change in illuminance caused by a moving object. 10. The method of claim 9,
Wherein when the sample is supplied from the loader to the reactor and the sample is detected by the optical sensor, the first supply valve is controlled to be closed.
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CN111504446A (en) * 2020-04-03 2020-08-07 武汉理工大学 Test system for surface sound intensity distribution on automatic scanning equipment
RU203146U1 (en) * 2021-01-25 2021-03-23 Общество с ограниченной ответственностью "Научно-производственное предприятие "Корад" GAMMA ACTIVATION ANALYSIS DEVICE
FR3142548A1 (en) * 2022-11-24 2024-05-31 Psa Automobiles Sa MOTOR VEHICLE COMPRISING A DIAGNOSTIC SYSTEM FOR ABNORMAL NOISES AND VIBRATIONS, METHOD AND PROGRAM BASED ON SUCH A VEHICLE

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111504446A (en) * 2020-04-03 2020-08-07 武汉理工大学 Test system for surface sound intensity distribution on automatic scanning equipment
RU203146U1 (en) * 2021-01-25 2021-03-23 Общество с ограниченной ответственностью "Научно-производственное предприятие "Корад" GAMMA ACTIVATION ANALYSIS DEVICE
FR3142548A1 (en) * 2022-11-24 2024-05-31 Psa Automobiles Sa MOTOR VEHICLE COMPRISING A DIAGNOSTIC SYSTEM FOR ABNORMAL NOISES AND VIBRATIONS, METHOD AND PROGRAM BASED ON SUCH A VEHICLE

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