JP2003315289A - Inspection and analysis equipment using neutron generator - Google Patents

Abstract

(57) [Problem] To provide a small and simple inspection / analysis device using neutrons. A neutron source for generating fast neutrons using a nuclear fusion reaction, a neutron moderator for decelerating fast neutrons generated by the neutron source into cold neutrons, and for reflecting the cold neutrons A neutron reflector, a neutron conduit for guiding thermal neutrons from the neutron reflector, a neutron wavelength selector for extracting a specific wavelength of the thermal neutron, and irradiating the sample or material with the extracted specific neutron wavelength. Through the sample or material,
An inspection / analysis apparatus using a neutron generator, comprising a two-dimensional neutron detector for detecting scattered or reflected neutrons.

Description

Detailed Description of the Invention

[0001]

The present invention relates to neutron scattering and neutron radiography, neutron activation analysis and neutron prompt γ.
The present invention relates to an inspection / analysis apparatus for inspecting / analyzing a sample or a material by using line analysis and neutron reflection surface analysis.

[0002]

2. Description of the Related Art Neutron scattering and neutron radiography, neutron prompt gamma-ray analysis, neutron activation analysis and neutron reflection surface analysis require powerful neutron sources, and are currently used in facilities with nuclear reactors or large accelerators. If not, it cannot be implemented.

In Japan, a neutron scattering research facility is installed at the Japan Atomic Energy Research Institute, and neutron scattering research, neutron radiography research, neutron prompt gamma ray analysis, neutron activation analysis and neutron surface reflection analysis are conducted. ing. In addition, the Institute for High Energy Research also has a neutron scattering facility for neutron scattering and neutron reflection surface analysis.

The neutrons generated in the fission reaction of uranium in the nuclear reactor are neutrons which are constantly generated and have an average energy of about 2 MeV. On the other hand, neutrons generated by the spallation reaction caused by colliding protons accelerated by a large accelerator with a target such as mercury, tungsten, and tantalum are neutrons that are usually emitted in a pulsed manner, and the maximum energy of the emitted neutrons is The energy is almost the same as that of accelerated protons, and about 500 MeV in the case of the High Energy Research Organization.

A typical neutron scattering device conventionally used in a nuclear reactor is shown in FIG. In FIG. 12, a nuclear reactor is used as a neutron source 1, and fast neutrons generated from the neutron source 1 are decelerated by a neutron moderator 2 to be converted into cold neutrons.

The cold neutrons floating in the neutron moderator 2 are guided to the neutron conduit 8 with a certain probability. Only the specific wavelength of the cold neutrons introduced into the neutron conduit 8 is selected by the neutron wavelength selection device 9, and the neutrons of this specific wavelength are introduced into the neutron conduit 8 and the sample 11 or the material 12
Is irradiated. Neutron wavelength selection device 9 in conventional device
, Usually, a neutron reflecting material such as silicon or highly oriented pyrolytic carbon or germanium is used, the reflection angle is θ, the reflecting surface spacing of the reflecting material is d, the wavelength of reflected neutrons is λ, and n is an integer. Then, the reflection angle θ determined by 2dsinθ = nλ
The Bragg reflection condition that neutrons of wavelength λ are reflected is used.

The neutrons scattered by the sample 11 or the material 12 are detected by the two-dimensional neutron detector 13 installed so as to surround the sample 11 or the material 12 and counted as the number of neutrons with respect to the scattering angle.

FIG. 13 shows an example of a typical neutron scattering device conventionally used in an accelerator facility. In FIG. 13, the neutron source 1 is a neutron source 1, and the neutron source 1 is a neutron generated by a spallation reaction caused by colliding the high-energy proton beam 30 accelerated by the accelerator with a target such as mercury, tungsten, and tantalum. The fast neutrons are decelerated by the neutron moderator 2 to be converted into cold neutrons and guided to the neutron conduit 8. Usually, the neutrons in the accelerator facility are pulsed neutrons and also contain neutrons of various energies. Sample 11 or material 1 placed at a certain distance from the target
The neutrons scattered by 2 are the two-dimensional neutron detector 1
3 detected. The higher the energy and therefore the faster the neutron, the shorter the time it takes to reach the two-dimensional neutron detector 13 from the target,
From the time when the neutron is detected and the distance to the detector, the velocity of the neutron and thus the energy and wavelength of the neutron can be determined. As described above, as the two-dimensional neutron detector 13 in the accelerator facility, a differential type detector that can obtain time information is used.

Further, in a measuring instrument such as a moisture meter or a densitometer which does not require a strong neutron flux, ²⁵² C is used as a neutron source.
Radioisotopes such as f are used, and they are used as neutron sources in neutron scattering equipment and neutron radiography.
It is contemplated to use ²⁵² Cf.

[0010]

In the above-mentioned conventional techniques, neutron scattering and neutron radiography, neutron-induced γ-ray analysis, neutron activation analysis, and neutron reflection surface analysis, which are inspection / analysis means for materials or samples, are simple. Therefore, it is necessary to make the inspection and analysis equipment using neutrons small and simple.

When a nuclear reactor is used as a neutron source, a large-scale facility is required, and an inspection / analysis apparatus using neutron cannot be made compact and simple.

When an accelerator facility is used, the accelerator itself is large. In addition, the neutrons generated by the spallation reaction using an accelerator generate high-energy neutrons with almost the same energy as the accelerated protons, so a very thick shielding material is required, so the entire device is large-scale. It becomes a thing. Further, when the accelerator facility is used, the distance from the target to the detector needs to be increased to some extent in order to improve the accuracy of neutron energy measurement, so that the entire apparatus becomes large-scale. Furthermore, as a two-dimensional neutron detector, since only a differential type detector that can obtain time information can be used, at present, an integral type photostimulable fluorescence detector showing the highest performance as position resolution is used. This is not possible, and the two-dimensional neutron detector is large compared to the case where a stimulable fluorescence detector is used.

When a radioisotope such as ²⁵² Cf is used as a neutron source, a large amount of radioisotope is required in order to obtain a neutron flux with sufficient intensity for an inspection / analysis apparatus using neutrons. Since neutrons are constantly generated,
A high degree of specialization is required for its handling, and it is difficult to use it for a small and simple inspection / analysis device using neutrons.

An object of the present invention is to provide a small and simple inspection / analysis apparatus using neutrons.

[0015]

The above-mentioned problems can be solved by using a neutron source that generates neutrons by a nuclear fusion reaction. The problem can be solved by optimizing the number and arrangement of the neutron moderator, the neutron reflecting device, the neutron wavelength selecting device, the neutron conduit, and the like.

More specifically, a beam type neutron source using a fusion reaction has a weaker neutron source than a nuclear reactor or an accelerator facility, but can be miniaturized.

Therefore, the installation of the neutron moderator, the neutron reflector, the neutron wavelength selecting device, the neutron conduit, etc. can be optimized by increasing the degree of freedom in their arrangement. A neutron flux of sufficient intensity can be provided on the sample and material. Beam type neutron source using fusion reaction is monochromatic fast neutron, for example, neutrons generated by fusion reaction between deuterium ions are neutrons with relatively low energy of 2.45 MeV, accelerator facility At hundreds of Me
The neutron moderator and the neutron reflector can be made smaller than in the case where neutrons having a high energy of V or higher are included. Therefore, since the neutron wavelength selection device can be installed in the vicinity of the neutron source, the wavelength-selected cold thermal neutrons can be efficiently extracted.

Further, since an inlet of a neutron conduit capable of efficiently transporting cold neutrons can be installed near the neutron wavelength selection device, it becomes possible to efficiently transport neutrons onto a material or a sample. , It is possible to obtain neutrons of sufficient intensity necessary for inspection and measurement. For example, when a fusion reaction of deuterium ions is used as a neutron source using a fusion reaction, the acceleration voltage of deuterium ions is
At 250keV and current of 400mA, 2.45Me of about 10 ¹² pieces / sec.
V neutrons are generated, and the neutron flux on the sample is 1 × 10
⁴ pieces / sec / cm ² or more are expected, and the intensity required for neutron inspection and measurement such as neutron scattering and neutron radiography, neutron prompt gamma ray analysis, neutron activation analysis, and neutron reflection surface analysis can be satisfied. .

Further, since the on / off control of the neutron generation can be easily performed by turning on / off the ion generating power source or the ion accelerating power source used for the beam type neutron source, the neutrons are quasi-steadily generated. It is also possible to easily generate a pulse or pulse. Therefore, it is also possible to use a photostimulable fluorescence detector having the highest position resolution at present as a two-dimensional neutron detector, and the two-dimensional neutron detector can be downsized. From the above, a small and simple inspection / analysis device can be provided.

Further, as compared with the case where a radioactive element such as ²⁵² Cf that continuously generates neutrons is used as the neutron source, the beam type neutron source using the fusion reaction is It is possible to turn on and off the generation of neutrons by turning on and off the power source for ion generation or the ion acceleration power source used for the neutron source, and by changing the ion acceleration power source voltage or the ion generation amount. Since the generation amount can be controlled, it is possible to provide a device that is easy to handle.

From the above, it is possible to provide a small-sized and easy-to-handle inspection / analysis apparatus using neutrons.

[0022]

BEST MODE FOR CARRYING OUT THE INVENTION Embodiments of the present invention will be described below with reference to the drawings.

FIG. 1 shows an example of a neutron scattering apparatus using a beam type neutron source utilizing a fusion reaction according to the present invention. A neutron moderator 2 is installed so as to surround a neutron source 1 which is a beam type neutron source utilizing a fusion reaction, and a plurality of neutron reflecting devices 4 are installed so as to surround the neutron moderator 2.

As the neutron moderator 2, for thermal neutrons,
Water or polyethylene is used, and liquid methane or liquid hydrogen is used for cold neutrons. As the neutron reflecting device 4, as shown in the example of FIG. 2, a neutron reflecting material fixing device 5 for fixing the neutron reflecting material 3 such as carbon material or beryllium and a neutron reflecting device rotating device for rotating the neutron reflecting device 4. Since 6 has a mechanism for adjusting the installation angle, the installation angles of the plurality of neutron reflecting devices 4 can be individually adjusted so that the neutron flux incident on the neutron conduit 8 is maximized.

The neutrons that have entered the neutron conduit 8 are wavelength-selected by the neutron wavelength selecting device 9,
The sample 11 or the material 12 is irradiated therethrough. Silicon, highly oriented pyrolytic carbon, germanium, or the like is used as the neutron reflecting material 3 in the neutron wavelength selecting device 9, and the divided neutron reflecting material 3 and the neutron reflecting material 3 are individually fixed as shown in the example of FIG. Each neutron reflection / selection device is composed of a neutron wavelength selection device rotating device 10 that allows the neutron reflection material fixing device 5 and the neutron wavelength selection device 9 to rotate, and maximizes the neutron flux with which the sample 11 or material 12 is irradiated. The installation angle of 9 can be adjusted.

The neutrons scattered by the sample 11 or the material 12 are detected by the two-dimensional neutron detector 13. For the two-dimensional neutron detector 13, a photostimulable fluorescence detector or the like is used. As described above, according to the present embodiment, the neutrons generated by the beam type neutron source utilizing the fusion reaction can be efficiently irradiated to the sample or material, and also scattered by the sample or material. Since it is possible to detect neutrons with high accuracy, it is possible to provide a small-sized and easy-to-use inspection / analysis device using neutrons.

FIG. 4 shows another example of the neutron scattering apparatus using the beam type neutron source utilizing the fusion reaction according to the present invention. A neutron moderator 2 is installed so as to surround a neutron source 1 which is a beam type neutron source utilizing a fusion reaction,
A plurality of neutron reflectors 4 are installed so as to surround the neutron moderator 2. A plurality of neutron conduits 8 are installed near the neutron moderator 2, and a neutron wavelength selection device 9 is installed near the neutron outlet 8a of each neutron conduit 8.

In the neutron reflecting device 4, similar to the example shown in FIG. 1, the neutron reflecting material fixing device 5 for fixing the neutron reflecting material 3 and the neutron reflecting device 4 for rotating the neutron reflecting device 4 as shown in the example in FIG. A mechanism for adjusting the installation angle is provided by having the device rotating device 6, and the installation angles of the plurality of neutron reflecting devices 4 are individually adjusted so that the sum of the neutron fluxes incident on the individual neutron conduits 8 is maximized. Can be adjusted.

Neutron outlet 8'of each neutron conduit 8
Similarly to the example shown in FIG. 1, the neutron wavelength selection device 9 installed in the vicinity also has the neutron reflecting material 3 divided as shown in the example of FIG. The neutron wavelength selection device rotating tool 10 rotates the wavelength selection device 9, and the installation angle of each neutron wavelength selection device 9 can be adjusted so that the neutron flux with which the sample 11 or the material 12 is irradiated is maximized. The neutrons scattered by the sample 11 or the material 12 are detected by the two-dimensional neutron detector 13 as in the example shown in FIG.

As shown above, according to this embodiment,
Neutrons generated by a beam-type neutron source utilizing a fusion reaction can be efficiently irradiated to a sample or material, and
Since the neutrons scattered by the sample or the material can be accurately detected, it is possible to provide a small-sized and easy-to-use inspection / analysis apparatus using neutrons.

FIG. 5 shows another example of the neutron scattering apparatus using the beam type neutron source utilizing the fusion reaction according to the present invention. A neutron moderator 2 is installed so as to surround a neutron source 1 which is a beam type neutron source utilizing a fusion reaction, and a plurality of neutron reflecting devices 4 are installed so as to surround the neutron moderator 2.

A plurality of neutron wavelength selection devices 9 are installed near the neutron moderator 2, and each neutron wavelength selection device 9 is installed.
The neutron conduit 8 is installed at a position where neutrons having a single wavelength selected by (1) are combined. Similar to the example shown in FIG. 1, each neutron wavelength selecting device 9 has a neutron reflector 3 divided as shown in the example of FIG. 3, a neutron reflector fixing device 5 for individually fixing it, and a neutron wavelength. The neutron wavelength selecting device rotating tool 10 rotates the selecting device 9, and the installation angle of each neutron wavelength selecting device 9 can be adjusted so that the neutron flux entering the neutron conduit 8 is maximized.

The neutrons passing through the neutron conduit 8 are sample 11
Alternatively, the neutrons scattered by the material 12 and scattered are detected by the two-dimensional neutron detector 13. As described above, according to the present embodiment, the neutrons generated by the beam type neutron source utilizing the fusion reaction, the sample or material can be efficiently irradiated, and also the neutrons scattered by the sample or material Since it is possible to detect with high accuracy, it is possible to provide a small-sized and easy-to-use inspection / analysis device using neutrons.

FIG. 6 shows an example of a neutron radiography apparatus using a beam type neutron source utilizing a fusion reaction according to the present invention. A neutron shielding / absorbing material 7 is installed so as to surround the neutron source 1 which is a beam type neutron source utilizing a fusion reaction. A neutron conduit 8 is installed near the neutron source 1, and a sample 11 is installed near the neutron outlet 8a. The monochromatic fast neutrons generated from the neutron source 1 are irradiated onto the sample 11 through the neutron conduit 8. The neutrons that have passed through the sample 11 are detected by the two-dimensional neutron detector 13 installed behind the sample 11.

The energy of monochromatic fast neutrons can be changed by the kind of hydrogen isotope gas supplied to the beam type neutron source utilizing the fusion reaction shown in FIG. When deuterium is used as the hydrogen isotope gas, 2.45 MeV monochromatic fast neutrons are obtained, and when deuterium and tritium are used, 2.45 MeV monochromatic fast neutrons and 14.
Neutrons obtained by mixing 67 MeV monochromatic fast neutrons can be obtained, and can be easily selected according to the thickness of the sample 11 to be used.

As described above, according to this embodiment,
The energy of neutrons generated by a beam-type neutron source utilizing a fusion reaction can be easily changed according to the thickness of the sample, and the neutrons can be efficiently irradiated to the sample or material, and the sample can pass through the sample. Since the detected neutrons can be detected with high accuracy, it is possible to provide a small-sized and easy-to-use inspection / analysis device using neutrons.

FIG. 7 shows another example of the neutron radiography apparatus using the beam type neutron source utilizing the fusion reaction according to the present invention. A neutron moderator 2 surrounding a neutron source 1 which is a beam type neutron source utilizing a fusion reaction
Set up. A neutron conduit 8 is installed in the vicinity of the neutron moderator 2, and thermal neutrons decelerated by the neutron moderator 2 pass through the neutron conduit 5 and are applied to a sample 11 installed near the neutron outlet 8a.

The neutrons that have passed through the sample 11 are detected by the two-dimensional neutron detector 13 installed behind the sample 11. Since γ-rays are mixed with the neutrons decelerated by the neutron moderator 2, when the two-dimensional neutron detector 13 is arranged so as to directly look into the neutron source 1, the two-dimensional neutrons are caused by the background of the γ-rays. It is difficult to use a weak stimulable fluorescence detector for the background of γ rays as the detector 13, and a detector strong for the background of γ rays such as a wire-type fission ionization chamber is used as a two-dimensional neutron detector.

As shown above, according to this embodiment,
Since the sample or material can be efficiently irradiated with the neutrons generated by the beam type neutron source utilizing the fusion reaction, it is possible to provide a small-sized and easy-to-use inspection / analysis device using neutrons.

FIG. 8 shows an example of a neutron activation analyzer using a beam type neutron source utilizing the fusion reaction according to the present invention. A neutron moderator 2 is installed so as to surround a neutron source 1 that is a beam type neutron source utilizing a fusion reaction, and a plurality of neutron reflecting devices 3 are installed so as to surround the neutron moderator 2.

Similar to the example shown in FIG. 1, the neutron reflecting device 4
As for the installation angle by installing a neutron reflector fixing tool 5 for fixing the neutron reflecting material 3 such as a carbon material or beryllium as shown in the example of FIG. An adjustable mechanism is provided, and the installation angles of the plurality of neutron reflecting devices 4 can be individually adjusted so that the thermal neutron flux irradiated to the sample 11 installed near the neutron moderator 2 is maximized. The sample 11 on the sample stage 16 irradiated with thermal neutrons is transferred by the sample transfer device 17 to the γ-ray measurement chamber 19 surrounded by the γ-ray shielding material 15 provided next to the neutron irradiation chamber 18.

Γ-ray detector 1 installed in γ-ray measuring chamber 19
4, the γ-ray emitted from the sample 11 is measured. According to the present embodiment, the sample can be efficiently irradiated with the neutrons generated by the beam type neutron source utilizing the fusion reaction, so that it is possible to provide a small-sized and easy-to-use inspection / analysis apparatus using neutrons.

A neutron prompt gamma ray analyzer using a beam type neutron source utilizing a fusion reaction according to the present invention has the same system structure as neutron scattering and has the neutron scattering device shown in FIG. 1 or FIG. 4 or FIG. In this apparatus, a γ-ray detector 14 is installed instead of the two-dimensional neutron detector 12 in FIG. In the neutron irradiation chamber 18, irradiation of the thermal neutron to the sample 11 and measurement of γ-ray generated from the irradiated sample 11 are performed at the same time. According to the present embodiment, the sample can be efficiently irradiated with the neutrons generated by the beam type neutron source utilizing the fusion reaction, so that it is possible to provide a small-sized and easy-to-use inspection / analysis apparatus using neutrons.

The neutron reflection surface analysis apparatus using the beam type neutron source utilizing the fusion reaction according to the present invention has the same system structure as the neutron scattering, and is the same as the neutron scattering apparatus shown in FIG. 1 or 4 or 5. The sample 11 or the material 12 and the two-dimensional neutron detector 13 in the neutron irradiation chamber 18 are shown in FIG.
The device is installed as shown in FIG. Neutrons reflected on the surface of the sample 11 or the material 12 are measured by the two-dimensional detector 13. According to this embodiment, a neutron generated by a beam type neutron source utilizing a fusion reaction can be efficiently irradiated to a sample or a material, and thus a small-sized and easy-to-use inspection / analysis device using neutrons is provided. it can.

FIG. 10 shows an example of the structure of the beam type neutron source using the fusion reaction according to the present invention. A hydrogen isotope gas 26 is supplied into the ion source 20, and a hydrogen isotope ion 21 is supplied.
Generate. The generated hydrogen isotope ions 21 are extracted into the vacuum container 24 adjacent to the ion source 20 using the hydrogen isotope ion extraction electrode 23. The inside of the vacuum container 24 is maintained at a certain degree of vacuum by exhausting the hydrogen isotope gas by the vacuum exhaust device 25.

The extracted hydrogen isotope ions 21 are supplied to a hydrogen storage alloy 27, which is installed by applying a negative high voltage to the tip portion of the high voltage current introduction terminal 28, and a vacuum container 24 which is normally grounded and used. The hydrogen isotope ion beam 22 is accelerated by the electrostatic potential created and collides with the hydrogen storage alloy 27. A part of the hydrogen isotope ions 21 that collide is stored in the hydrogen storage alloy 27, and the stored hydrogen isotope collides with the accelerated hydrogen isotope ion 21 to cause a nuclear fusion reaction and generate neutrons. .

When deuterium gas is used as the gas to be supplied to the ion source 20, a D (deuterium) + D (deuterium) → ³ He (helium 3) + n (neutron) reaction occurs, and the hydrogen storage alloy 2
2.45 MeV monochromatic fast neutrons are generated from 7 in all outward directions (4π direction). After using tritium as a gas to be supplied to the ion source to cause the hydrogen storage alloy 27 to store the tritium first, the gas in the ion source is replaced with deuterium to cause the deuterium ions to collide with the hydrogen storage alloy 27, Collision of deuterium ions with tritium stored in the hydrogen storage alloy 27 causes T (tritium) + D (deuterium) → ⁴ He
(Helium 4) + n (neutron) reaction occurs, and 14.6 from the hydrogen storage alloy 27 toward all outside (4π direction).
7 MeV monochromatic fast neutrons are generated.

In this case, in the process of causing deuterium ions to collide with the hydrogen storage alloy, a process in which deuterium is stored in the hydrogen storage alloy also occurs, so D (deuterium) + D (deuterium) →
2.45 MeV monochromatic fast neutrons are also generated by ³ He (helium 3) + n (neutron) reaction. According to the present embodiment, it is possible to provide a small beam type neutron generator that is easy to handle.

FIG. 11 shows another structural example of the beam type neutron source using the fusion reaction according to the present invention. For a spherical vacuum container 24 for confining hydrogen isotope gas and ions,
A cathode grid 29 on a concentric sphere and a vacuum container 24 installed by applying a negative high voltage are provided at the tip of the high-voltage current introduction terminal 28. The vacuum vessel 24 is normally grounded and used, and a spherically symmetric potential is formed by the vacuum vessel 24 and the cathode grid 29.

Here, the vacuum container 24 and the cathode grid 2
A discharge is caused between 9 and the hydrogen isotope ions 21 generated by the discharge are accelerated toward the cathode grid 29, pass through the cathode grid 29, and are concentrated from all directions to the center. On the other hand, the electrons generated by the discharge are affected by the potential created by the hydrogen isotope ions 21 in the central portion of the cathode, and are concentrated more in the central portion to lower the potential in the central portion.

Thus, the hydrogen isotope ion 21 and the
In the center, the child is trapped in the self-electrostatic field.
A nuclear fusion reaction occurs due to the increase in ion density.
Neutrons are generated. The inside of the vacuum container 24 is a vacuum exhaust device.
By exhausting the hydrogen isotope gas with
The degree of vacuum is maintained. As in the case shown in FIG.
When deuterium gas is used as the gas supplied to the vessel 24, D
(Deuterium) + D (deuterium) → ³He (helium 3) + n (medium
Sexual reaction occurs, and all directions outside from the vacuum container 24
2.45 MeV monochromatic fast neutrons are emitted toward (4π direction)
To live.

When a mixed gas of deuterium gas and tritium gas is used as the gas supplied to the vacuum container 24, the collision of tritium and deuterium causes T (tritium) + D (deuterium). → ⁴ He (helium 4) + n (neutron) reaction occurs, and monochromatic fast neutrons of 14.67 MeV are generated from the vacuum container 24 in all the outside directions (4π direction), and deuterium collides with each other to cause D ( Deuterium) + D (deuterium) → ³ He
(Helium 3) + n (neutron) reaction also occurs, 2.45MeV
Also produces monochromatic fast neutrons. According to the present embodiment, it is possible to provide a small beam type neutron generator that is easy to handle.

[0053]

According to the present invention, neutron inspection /
As an neutron source for analysis, by using a neutron source utilizing a fusion reaction, by optimizing the number and arrangement of neutron moderator and neutron shielding device and neutron wavelength selection device and neutron conduit, neutron scattering and The neutron radiography, neutron activation analysis, neutron prompt gamma ray analysis, neutron reflection surface analysis, and other inspection and analysis apparatus for samples and materials using neutrons can be made small and easy to handle.

[Brief description of drawings]

FIG. 1 is a diagram showing a neutron scattering device using a beam type neutron source according to an embodiment of the present invention.

FIG. 2 is a diagram showing a neutron reflector according to an embodiment of the present invention.

FIG. 3 is a diagram showing a neutron wavelength selection device according to an embodiment of the present invention.

FIG. 4 is a diagram showing a neutron scattering device according to another embodiment of the present invention.

FIG. 5 is a diagram showing a neutron scattering device according to another embodiment of the present invention.

FIG. 6 is a diagram showing a neutron radiography apparatus according to an embodiment of the present invention.

FIG. 7 is a view showing a neutron radiography apparatus according to another embodiment of the present invention.

FIG. 8 is a diagram showing a neutron activation analyzer according to an embodiment of the present invention.

FIG. 9 is a view showing a neutron irradiation chamber of a neutron reflection surface analyzer according to an embodiment of the present invention.

FIG. 10 is a view showing a structure of a beam type neutron source utilizing a nuclear fusion reaction according to an embodiment of the present invention.

FIG. 11 is a diagram relating to another embodiment of the present invention and showing a structure of a beam type neutron source utilizing a fusion reaction.

FIG. 12 is a diagram showing a conventional typical neutron scattering device using neutrons generated in a nuclear reactor.

FIG. 13 is a view showing a conventional typical neutron scattering device using neutrons generated by using an accelerator.

[Explanation of symbols]

1 ... Neutron source, 2 ... Neutron moderator, 3 ... Neutron reflector,
4 ... Neutron reflector, 5 ... Neutron reflector fixing fixture, 6 ...
Neutron reflector rotating device, 7 ... Neutron shielding / absorbing material, 8
... neutron conduit, 8a ... neutron outlet, 9 ... neutron wavelength selector, 10 ... neutron wavelength selector rotating tool, 11 ... sample, 12 ... material, 13 ... two-dimensional neutron detector, 14 ... γ
Ray detector, 15 ... γ-ray shield, 16 ... Sample stage, 17 ... Sample transport device, 18 ... Neutron irradiation chamber, 19 ... γ-ray measurement chamber,
20 ... Ion source, 21 ... Hydrogen isotope ion, 22 ... Hydrogen isotope ion beam, 23 ... Hydrogen isotope ion extraction electrode, 24 ... Vacuum container, 25 ... Vacuum exhaust device, 26 ... Hydrogen isotope gas, 27 ... Hydrogen Storage alloy, 28 ... High voltage current introducing terminal, 29 ... Cathode grid, 30 ... High energy proton beam.

─────────────────────────────────────────────────── ─── Continuation of front page (51) Int.Cl. ⁷ Identification code FI theme code (reference) G01T 3/08 G01T 3/08 G21K 1/00 G21K 1/00 N 1/06 1/06 C K 1 / 10 1/10 5/02 5/02 N 5/08 5/08 N H05H 3/06 H05H 3/06 (72) Inventor Kazuhiro Takeuchi 7-2-1, Omika-cho, Hitachi-shi, Ibaraki Hitachi, Ltd. Electric Power and Electric Machinery Development Laboratory (72) Inventor Sadao Uchikawa 7-2-1 Omika-cho, Hitachi-shi, Ibaraki Hitachi Ltd. Electric Power and Electric Machinery Development Laboratory (72) Inventor Nobuo Niimura Tokaimura Shira, Naka-gun, Ibaraki Prefecture No. 4 in Shirahone F-term in Japan Atomic Energy Research Institute Tokai Research Institute (reference) 2G001 AA04 BA01 BA11 BA14 CA02 CA04 DA09 DA10 EA09 2G085 AA20 BA02 BE10 2G088 EE27 EE30 FF04 FF09 GG06 GG21 GG30 JJ01 JJ05 JJ29 LL02 LL06

Claims (20)

[Claims] 1. A neutron source for generating fast neutrons using a fusion reaction, a neutron reflector for reflecting the fast neutrons, a neutron conduit for guiding the fast neutrons from the neutron reflector, and a neutron conduit for the neutrons. Neutron generator characterized by having a two-dimensional neutron detector for irradiating a sample or material with the fast neutrons guided by the above, and detecting neutrons that penetrate, scatter or reflect this sample or material. Inspection / analysis device using 2. A neutron source for generating fast neutrons using a fusion reaction, a neutron moderator for decelerating the fast neutrons generated by the neutron source to turn them into cold neutrons, and reflecting the cold neutrons For neutron reflecting device, a neutron conduit that guides cold neutrons from the neutron reflecting device, a neutron wavelength selection device for extracting a specific wavelength of the cold neutrons, a sample or material neutrons of the specific wavelength extracted An inspection / analysis apparatus using a neutron generator, which has a two-dimensional neutron detector for detecting neutrons that are irradiated and that are transmitted through this sample or material or scattered or reflected. 3. The inspection / analysis apparatus according to claim 1 or 2, wherein a beam-type neutron generation source is used as the neutron generation source. 4. The inspection / analysis apparatus according to any one of claims 1 to 3, wherein the neutron reflector is a neutron shielding / absorbing material for shielding fast neutrons including the cold neutrons. An inspection / analysis device using a neutron generator characterized by being surrounded. 5. The inspection / analysis apparatus according to claim 1, wherein the two-dimensional neutral detector is a detector for γ-rays generated from a sample or material by irradiation of the fast neutrons. Inspection / analysis equipment using the characteristic neutron generator. 6. The inspection / analysis apparatus according to any one of claims 1 to 5, wherein the neutron source is configured to preliminarily detect hydrogen isotope ions extracted from an ion source. An inspection / analysis apparatus using a neutron generator, which is a neutron source that causes a nuclear fusion reaction by colliding with a stored hydrogen storage alloy. 7. The inspection / analysis apparatus according to any one of claims 1 to 5, wherein the neutron source is concentric with a spherical container for confining hydrogen isotope gas and ions. Neutron characterized by providing a cathode grid to form a spherically symmetric potential, causing a discharge between the container and the cathode grid, and increasing the ion density in the center to cause a fusion reaction. Inspection / analysis device using a generator. 8. The inspection / analysis apparatus according to any one of claims 1 to 5, wherein the neutron source has a function of turning on / off power supplied for ion generation or ion acceleration. An inspection and analysis apparatus using a neutron generator characterized in that. 9. The inspection / analysis device according to claim 1, wherein the neutron source has a function of changing a voltage supplied for ion generation or ion acceleration. An inspection and analysis apparatus using a neutron generator characterized in that. 10. The inspection / analysis apparatus according to any one of claims 1 to 5, wherein the neutron source has a function of changing the amount of ions generated in the ion source. Inspection and analysis device using neutron generator. 11. The inspection / analysis apparatus according to claim 2, wherein the neutron moderator is water or polyethylene, or
A neutron inspection / analysis apparatus using a neutron generator characterized by using liquid hydrogen or liquid methane. 12. The inspection / analysis apparatus according to any one of claims 1 to 11, wherein a neutron reflector such as carbon material or beryllium and its neutron reflector are fixed to the neutron reflector. An inspection / analysis apparatus using a neutron generator, comprising a fixture and a turntable for rotating the fixed neutron reflector. 13. The inspection / analysis apparatus according to claim 12, wherein a plurality of the neutron reflecting devices are installed around the neutron generating source. Analysis equipment. 14. The inspection / analysis device according to any one of claims 1 to 13, wherein the neutron wavelength selection device is a neutron reflecting material such as silicon, highly oriented pyrolytic carbon, or germanium, and An inspection / analysis apparatus using a neutron generator, which has a fixture for fixing the neutron reflector and a turntable for rotating the fixed neutron reflector. 15. The inspection / analysis apparatus according to claim 14, wherein a plurality of the neutron selection devices are installed around the neutron source, and the inspection / analysis using the neutron generator is performed. apparatus. 16. The inspection / analysis apparatus according to any one of claims 1 to 15, wherein the neutron conduit has a Ni film or Ni and Ti on an inner surface of the conduit.
An inspection / analysis apparatus using a neutron generator, which has a film in which the above thin films are alternately laminated. 17. The inspection / analysis apparatus according to any one of claims 1 to 16, wherein the two-dimensional neutral detector is a wire-type fission ionization chamber or a photostimulable fluorescence detector. An inspection / analysis device using a neutron generator characterized by having. 18. The inspection / analysis apparatus according to claim 17, wherein the two-dimensional neutral detector is formed so as to correspond to a spherical surface of a neutron detection tank having a cylindrical or hemispherical shape. An inspection / analysis apparatus using a neutron generator characterized in that the neutron conduit is arranged at the center of the spherical surface of the neutron scattering tank or on the central axis of a cylinder. 19. An inspection / analysis apparatus according to any one of claims 1 to 16, wherein a means for moving the inspection / analysis apparatus is provided. Inspection / analysis device. 20. The inspection / analysis device according to claim 5, wherein the γ-ray detector is a germanium detector or a cadmium-tellurium detector, or a semiconductor such as a mercury iodide or gallium-arsenic detector. An inspection / analysis apparatus using a neutron generator characterized by having a detector.