KR101792556B1 - Materials Irradiation Test Capsule With Neutron Spectrum Tailoring Capability - Google Patents

Abstract

The present invention relates to an irradiation test capsule capable of tailoring a neutron energy spectrum. The irradiation test capsule of the present invention comprises a neutron tailoring device stored inside mini capsules loaded into the irradiation test capsule to perform an irradiation test inside a neutron reactor and tailoring the neutron energy spectrum irradiated inside the neutron reactor to realize a required irradiation test environment. The neutron tailoring device has a tube body and a neutron absorber, wherein the neutron absorber is accommodated and installed inside a wall surface of the tube body, and thus various irradiation conditions, especially, irradiation characteristics of a fast neutron which cannot be achieved by operation of a thermal neutron reactor can be emulated by blocking at least a portion of the thermal neutron or an epithermal neutron from the neutron energy spectrum irradiated to a sample accommodation space, so irradiation testes necessary for qualification of a material for development of a sodium-cooled fast reactor (SFR) can be performed. Moreover, the present invention can be variously applied to a medical and general industrial field.

Description

{Materials Irradiation Test Capsule with Neutron Spectrum Tailoring Capability}

The present invention relates to a test capsule, and more particularly, to a test capsule capable of conducting a test by changing the ratio between a fast neutron flux and a thermal neutron flux through a neutron energy spectrum cut in a thermal neutron flux.

As is well known, advanced nuclear power nations of the world are devoted to the development of a fourth generation reactor that dreams of technological innovation. Six types of nuclear power plants were selected to improve the sustainability, economic efficiency, safety and nuclear non- And is expected to be applied later in the year.

Therefore, the development of the 4th generation nuclear power system is being actively promoted globally, and the demonstration of the technology is being promoted until the 2020s. Especially, the safety improvement of the nuclear power plant due to the accident of Fukushima nuclear plant is expanding.

Meanwhile, Korea is also participating in the 4th Generation International Forum (GIF) centered on the Korea Atomic Energy Research Institute, participating in the Sodium Free Cooling High Speed (SFR) and Super High Temperature Gas (VHTR) programs.

Accordingly, the Korean government has deliberated and confirmed the "Long-term Nuclear Power System Development Plan" (Dec. 2008), which establishes the long-term basic direction of nuclear energy research and development by 2028. The nuclear nonproliferation pie (SFR) development in cooperation with the Pyro process and the development of a sodium-cooled high-speed furnace (SFR) in conjunction with this project. In 2007, the company began research on metal fuel fabrication for the fourth generation sodium-cooled fast reactor (SFR) And to develop core infrastructure technologies necessary for establishment of the system.

The development of innovative nuclear systems requires extensive research to find, document, and code materials that can withstand extreme environments in terms of temperature, neutron flux, corrosion environment, and life expectancy. In most cases, the development of new materials is necessary and the feasibility of these concepts depends on their ability to develop these materials.

These next-generation nuclear power systems have very high operating temperatures (about 500-1000 ° C) compared to existing reactors, and even higher neutron doses of up to 200dpa. Therefore, it is urgent to develop a material that can be used for a long period of time in such a harsh environment, and it is required to develop a technology capable of in-pile testing.

In Korea, however, there are 23 PWR and PHWR generators operating as a multi-purpose research reactor [Hanaro] and commercial PWR and PHWR, but these reactors are thermal neutron reactors and neutron spectra are also significantly different from high-speed reactors.

Therefore, it is necessary to develop a technology to simulate high - speed operation conditions in Korea without high - speed road, but such technology has not been developed yet.

The experimental ball used for neutrons in HANARO has 32 vertical test holes for injecting samples from the upper part of the reactor and 39 horizontal test holes for drawing the neutron beam outside the reactor. Here, there are three vertical test holes in the core of the reactor, four in the outer core, and 25 in the reflector area, all of which are in the reflector area. The CT, IR1 and IR2 inside the core are used for material testing using high-speed neutrons and for nuclear fuel tests requiring high power density.

Therefore, in Korea, the performance evaluation study of the next generation reactor material using the currently active neutron furnace [Hanaro] is planned, and related technology development is required. In particular, the qualification of materials for the development of the sodium cooling fast reactor (SFR) It is imperative to develop a research test capsule that can cut neutron spectra in a neutron-like condition similar to the core at high speed in a research furnace.

Korean Patent Laid-Open Publication No. 10-2009-0036336 (Patent Publication Date Apr. 14, 2009) Korean Registered Patent No. 10-0923081 (Registration date: Oct. 15, 2009) Japanese Unexamined Patent Application Publication No. 3951685 (registration dated 2007.05.11) Japanese Laid-Open Patent Publication No. 2011-075464 (Published date 2013.04.14)

It is an object of the present invention to solve the above-mentioned problems, and it is an object of the present invention to provide a neutron cutting apparatus capable of simulating various irradiation conditions, in particular irradiation conditions with a high-speed neutron that can not be achieved by operating with thermal neutrons, And to provide an irradiation test capsule capable of utilizing the same.

In order to accomplish the above object, the irradiation test capsule capable of cutting the neutron energy spectrum according to the present invention is provided with a plurality of mini capsule encapsulated in the irradiation test capsule so as to perform the irradiation test in the neutron beam, And a neutron cutting apparatus for cutting off a spectrum of neutron energy irradiated in the neutron furnace to implement the neutron cutting apparatus, wherein the neutron cutting apparatus comprises: a tubular body accommodated in the mini capsule and having a tubular shape for providing a sample storage space therein; And a neutron absorber disposed inside a wall surface of the tube body and cutting at least a part of thermal neutrals and / or non-neutron neutrons from the neutron energy spectrum irradiated to the sample receiving space to cut a neutron energy spectrum. .

Here, the tube body includes an accommodating cylinder having an opening formed at one end thereof and having an absorber receiving groove formed therein to provide an absorber receiving space along the longitudinal direction; And a receiving cylinder end cap which is connected to one side end of the receiving cylinder to block the opening to close the absorber receiving space accommodating the neutron absorber and to open the sample receiving space inside the receiving cylinder; .

In addition, the tube body may include an inner receiving cylinder defining the sample receiving space therein; An outer accommodating cylinder inserted into the inner receiving cylinder concentrically and internally to provide an absorbent storage space for storing the neutron absorber between the outer circumferential surface of the inner receiving cylinder and the outer receiving cylinder; And both side ends of the inner receiving cylinder and the outer receiving cylinder are closed at both side openings of the absorber receiving space to close the absorber receiving space in which the neutron absorber is housed and the sample accommodating space inside the receiving cylinder is opened And a pair of accommodating cylinder end caps made of a hollow plate type.

In addition, the receiving end cap may be inserted into the absorbent storage space to protrude an insertion protrusion so as to close the opening of the tube body. At this time, the neutron absorber may be inserted into the insertion tube, It is preferable that the absorbent article is accommodated in the absorbent storage space.

In addition, at least three spacer projections for maintaining spacing between the receiving end cap and the inner circumferential surface of the mini capsule on the outer circumferential surface may be formed so as to protrude at intervals along the outer circumferential direction.

In addition, the tube body may be made of aluminum.

It is preferable that the neutron absorber is formed to have a tubular shape capable of storing the neutron absorber in sheet form so as to be housed in the absorber housing space so that both side ends of the neutron absorber can be housed therein.

The neutron absorber may be made of at least one neutron absorbing material selected from cadmium (Cd), hafnium (Hf), boron alloy, gadolinium compound or europium (Eu).

According to the irradiation test capsule capable of cutting the neutron energy spectrum of the present invention, the neutron absorber is installed inside the wall surface of the tube body constituting the neutron cutting apparatus, and the neutron energy spectrum irradiated to the sample receiving space through the neutron absorber is irradiated with heat neutrons Or at least a part of the exo-neutrons, thereby easily and easily simulating various irradiation conditions including irradiation conditions with high-speed neutrons which can not be achieved by operation with thermal neutrons.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a front sectional view showing an irradiation test capsule capable of neutron energy spectrum cutting according to a first embodiment of the present invention; FIG.
FIG. 2 is a front sectional view showing an enlarged view of a mini capsule accommodated in the irradiation test capsule of FIG. 1; FIG.
3 is a side cross-sectional view showing the decomposition state of the mini capsule of Fig.
FIG. 4 is a half-sectional perspective view of the neutron cutting apparatus of FIG. 3;
5 is a half sectional exploded perspective view showing a decomposed state of the neutron cutting apparatus of FIG.
6 is a flowchart showing a process of manufacturing a neutron absorber in sheet form of FIG. 5 in a cylindrical shape.
7 is a graph showing the neutron energy spectrum.
FIG. 8 is a side cross-sectional view showing a mini-capsule in which a neutron cutting apparatus according to a second embodiment is housed.
FIG. 9 is a perspective view showing the neutron cutting apparatus of FIG. 8. FIG.
10 is an exploded perspective view of the neutron cutting apparatus of FIG.
11 is a front sectional view of the present neutron cutting apparatus cut along the line XI-XI in FIG.
Fig. 12 is a cross-sectional view of the mini-capsule taken along the line XII-XII in Fig. 8;

Hereinafter, embodiments of the present invention will be described in detail with reference to the accompanying drawings so that those skilled in the art can easily carry out the present invention. The present invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein. In order to clearly illustrate the present invention, parts not related to the description are omitted, and the same or similar components are denoted by the same reference numerals throughout the specification.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a front sectional view showing an irradiation test capsule capable of neutron energy spectrum cutting according to a first embodiment of the present invention; FIG.

1, description will be made of a process of charging an irradiation test capsule 1 (hereinafter referred to as "irradiation test capsule") capable of performing neutron energy spectrum cutting in this embodiment into a thermal neutron (for example, one sample) In which neutron energy spectral cuts can be used to simulate high-speed neutron irradiation conditions that can not be achieved by thermal neutron activation.

The mini capsule 100 is accommodated in each of the capsule loading spaces 20 partitioned by the support tubes 11, 12 and 15 inside the capsule body 10 of the irradiation test capsule 1, And a neutron cutting apparatus 120 that is housed in each of the mini capsules 100 and provides a sample storage space for cutting off a spectrum of neutron energy irradiated in the thermal neutron beam.

The irradiation test capsule 1 includes a cylindrical capsule body 10 and upper, lower, and intermediate support tubes 11 and 12 for partitioning the capsule charging spaces 20 to charge the mini capsules 100 inside the capsule body. 12, and 15, upper and lower end plates 16 and 17 coupled to upper and lower ends of the capsule main body, a lower guide unit 21 positioned below the lower end plate to prevent vibration of the capsule, A lower guide spring 22 installed to be positioned between the lower end plate 17 and the lower guide part 21 to alleviate the capsule load and an upper guide spring assembly 22 installed to be positioned at an edge portion on the upper end plate 16, An upper guide 25 installed on the upper end plate 16 to prevent disassembly of the irradiation test capsule 1 and an upper guide spring assembly 23 installed on the upper guide 25,A grapple head lock 26 belonging to the grapple head lock 26 and connected to a capsule handling mechanism (not shown) A rod tip 18 coupled to a fixing device at the lower end of the reactor radiator at one end thereof and a collar 30 coupled to an upper portion of the rod tip 18 to limit the clearance of the lower guide spring 22, And a grapple head clamping nut 32 which is fastened to one end of the center support rod 30 protruding into the grapple head 31. The grapple head clamping nut 32 has a bushing (not shown)

The irradiation test capsule (1) to be applied to this embodiment is a nonaqueous-based irradiation test capsule, which is mainly charged into an isotope irradiation hole as a thermal neutron to perform an irradiation test necessary for qualification of a material for the development of a sodium- As shown in FIG.

Since the irradiation test capsule 1 of the present embodiment is an anisotropic irradiation test capsule, it is possible to measure the irradiation environment together with the samples 310 in the sample storage space 125 inside the neutron cutting apparatus 120 One or more thermal markers 320 and a neutron dosimeter 330 may be housed (see FIG. 2).

However, the present invention is not limited to this, and the mini capsules 100 in which the neutron cutting apparatus 120 is accommodated may be stored in the instrument parts (thermocouple, auxiliary heater, pressure The instrument can be configured as a probe-type test capsule to control the temperature or atmosphere inside the capsule body during neutron irradiation, and to acquire the temperature and neutron irradiation information of the sample through the neutron probe. In addition, it is natural that neutron energy spectrum cuts can be applied to various medical and general industrial fields by allowing various irradiation conditions to be simulated.

FIG. 2 is a front sectional view showing an enlarged view of a mini capsule accommodated in the irradiation test capsule of FIG. 1, and FIG. 3 is a side sectional view showing a decomposed state of the mini capsule of FIG.

2 and 3, a plurality of mini capsules 100 to be loaded into the capsule body 10 of the irradiation test capsule 1 are inserted into the mini capsule body 110, the neutron cutting device 120, A mini capsule end cap 130, and a spacer block 140. [

The mini capsule main body 110 has a capsule outer tube forming an inner receiving space 115 for receiving the neutron trimming device 120 therein while the lower end of the mini capsule main body 110 is opened, The upper fixing groove portion 15a (see FIG. 1) formed on the lower surface of the intermediate support tube 15 when the mini capsule 100 is inserted into the capsule charging space 20 of the capsule main body 10, As shown in Fig.

The neutron cutting device 120 is provided in the mini capsule main body 110 to provide a sample storage space 125 therein to shut off thermal neutrals or non-thermal neutrals in the thermal neutron, Cut the spectrum of irradiated neutron energy to simulate conditions.

The mini capsule end cap 130 is fastened to the lower end of the mini capsule body 110 to close and close the lower open end of the internal storage space 115 in which the neutron trimming device 120 is housed. A lower fixing protrusion 131 is formed on the lower bottom surface of the mini capsule end cap 130 so that the lower end of the mini capsule 100 when the capsule body 10 is inserted into the capsule charging space 20 (See FIG. 1) formed on the upper surface of the intermediate support tube 15 so as to be fixed.

The spacer block 140 fills the space occupied by the neutron cutting device 120 in the interior storage space 115 of the mini capsule body 110 to fill the remaining space, It is possible to prevent the neutron cutting apparatus 120 from flowing inside the capsule body 110 and to adjust the size of the neutron cutting apparatus 120 stored in the mini capsule body 110 through the height adjustment So that it can be transformed more freely.

In the present embodiment, the mini capsule 100 accommodates one neutron trimming device 120 in the interior storage space 115 of the mini capsule body 110, inserts the spacer block into the extra storage space, However, the mini capsule 100 of the present invention is not necessarily limited to this. The neutron trimming device 120 may be filled with the additional neutron trimming device 120, It is of course possible to use a conventional sample loading device (not shown) which does not contain the neutron absorber described later for filling the experiment.

FIG. 4 is a half-sectional perspective view showing the neutron cutting apparatus of FIG. 3, and FIG. 5 is a half sectional exploded perspective view showing a decomposed state of the neutron cutting apparatus of FIG.

4 and 5, the neutron cutting apparatus 120 includes a tube body 121 and a neutron absorber 124 housed in a wall of the tube body 121. The neutron-

The tube body 121 is formed in a cylindrical shape so as to be accommodated in the mini capsule body 110 and to provide a sample storage space 125 therein as described above, .

In this embodiment, the tube body 121 is exemplified as being composed of the receiving cylinder 122 and the receiving cylinder end cap 123.

Here, the receiving cylinder 122 and the receiving end cap 123 constituting the tube body 121 are preferably made of aluminum in consideration of the deformation occurring during the irradiation, which is good in thermal conductivity.

The receiving cylinder 122 is formed in a cylindrical shape having a predetermined thickness and is formed with an opening at one end of the wall through cutting and has an absorbent storage space for accommodating the neutron absorber 124 along the longitudinal direction The absorber receiving groove 122a is formed.

The receiving end cap 123 is coupled to one end of the receiving cylinder 122 at which the opening of the receiving cylinder 122 is formed to close the absorber receiving space in which the neutron absorber 124 is housed, The end cap body portion 123a is formed in a hollow disk shape so as to open the sample storage space 125 of the end cap body 123a.

Here, an insertion protruding portion 123b is formed on the lower side of the end plate body 123a of the hollow disc plate type that is coupled to the receiving cylinder 122 so as to be inserted into the absorber receiving groove 122a to close the opening of the absorber receiving space, It can be further protruded.

At this time, the neutron absorber 124 is installed in the absorber accommodation space from the insertion protrusion 123b through the clearance space 126 in consideration of the volume increase rate due to the internal thermal expansion during the irradiation test, while the clearance space 126 ) Is filled with an inert gas such as argon (Ar) or helium (He).

6 is a flowchart showing a process of manufacturing a neutron absorber in sheet form of FIG. 5 in a cylindrical shape.

Referring to FIG. 6, the neutron absorber 124 is cylindrical in shape corresponding to the absorber receiving groove 122a formed in the wall of the receiving cylinder 121.

Here, it is preferable that the neutron absorber 124 is formed by using a sheet-form neutron absorbing material so that both end portions of the neutron absorbing material 124 are brought into contact with each other, and a cylindrical shape capable of being stored in the absorber receiving groove 122a is formed.

   Therefore, the neutron cutting device 120 of this embodiment is formed by cutting the inside of the wall of the cylindrical receiving cylinder 122 made of an aluminum material (purity of 95% or more) to form the absorbent article receiving groove 122a, The neutron absorber 124 is inserted into the absorber receiving groove 122a of the receiving cylinder 122 by fitting the neutron absorber 124 in a cylindrical shape so that both ends of the neutron absorber are in contact with each other, And then the opening of the absorber receiving groove is closed with the receiving end cap 123 so as to be sealed by using an electron beam or a laser beam.

The neutron cutting apparatus 120 of the present embodiment forms the absorber receiving groove 122a through a cutting process inside the wall of the receiving cylinder 122 and closes it with the receiving end end cap 123, It is possible to minimize a welded portion of the receiving end cap 123 for closing and sealing the opening of the receiving groove.

After the primary assembly, the produced neutron cutting apparatus 120 is heated in a vacuum furnace (10 ^-7 ) at 450 ° C for about 8 hours in order to prevent the welding portion from being deformed due to oxidation or the like after sealing in the irradiation test After confirming the state of thermal change, it is used after visual inspection and X-ray radiographic inspection to check the integrity of dimensions and welding conditions.

At this time, the neutron absorber 124 is formed of a neutron absorber 124 containing neutrons including at least one selected from the group consisting of cadmium (Cd), hafnium (Hf), boron alloy or gadolinium compound or europium (Eu) according to the neutron energy spectral band to be shielded in the neutron energy spectrum Absorbing materials.

Shielding material Atomic number density
(g / cm3) Melting point (℃) Thermal conductivity
(w / m ° C) Coefficient of thermal expansion
(1 / C) Neutron absorption cross-sectional area
(barns) Cadmium
(CD) 48 8.64 321 92 3 x 10-5 2450 hafnium
(Hf) 72 13.31 2150 22.29 6 × 10 -6 20.5

Table 1 shows physical properties of cadmium (Cd) and hafnium (Hf) which are mainly used among the neutron absorbing materials constituting the neutron absorber (124). The physical properties of cadmium (Cd) and hafnium (Hf) will be described below.

 Since cadmium (Cd) has a low melting point and a large coefficient of thermal expansion, it is complicated in engineering design and has a very high thermal neutron cross section, so a thinner neutron screen is sufficient to adjust neutron flux distribution in most cases. And in the high neutron, 113Cd is rapidly depleted and frequent replacement may be required to prevent an unexpected increase in power in the irradiated sample.

Since hafnium (Hf) has a small neutron absorption cross section, it is expected that the output rise will progress gradually, so it can be used for the longest irradiation (more than 100 days) in high-speed spectrum, has excellent mechanical characteristics, And has a high melting point.

On the other hand, the thermal neutron cross-sectional area of hafnium (Hf) is not as high as other neutron absorbing materials mentioned above, and the hafnium isotope formed during irradiation is also a good thermal neutron neutron absorber. Hafnium can be used in combination with aluminum because it is a good thermal conductor because the decay due to the collapse of the thermal neutron absorption occurs slowly and the need for screen replacement is not frequent.

On the other hand, in addition to the foregoing cadmium (Cd) and hafnium (Hf), boron (B) is a boron-used as alloy type, including the aluminum alloy (B-Al), and gadolinium (Gd) is a gadolinium oxide (Gd ₂ O ₃₎ As a gadolinium compound. Here, the composition ratio of boron (B) and gadolinium (Gd) is varied depending on the irradiation characteristics to be simulated in the thermal neutron beam, respectively, for the boron alloy and the gadolinium compound. Although europium (Eu) has a very high thermal neutron cross-sectional area, its use is limited because it is rare and expensive.

7 is a graph showing the neutron energy spectrum.

Referring to FIG. 7, (1) shows an energy spectrum of a typical thermal neutron, and (2) shows a case where a thermal neutron and an extra-neutron portion are cut using a neutron cutting apparatus 120 including a neutron absorber 124 The neutron spectra shown in Fig.

As a result, the neutron absorbing member 124 can be received in the wall of the tube body 121, so that the neutron absorbing member 124 can be easily removed through the neutron absorbing member 124 during the irradiation test in the thermal neutron beam. The energy spectrum is cut so as to absorb thermal neutrons or neutrals in the neutron energy spectrum irradiated into the sample containing space 125 in which the sample is stored, It is possible to simulate irradiation conditions to neutrons.

Hereinafter, another embodiment of the irradiation test capsule capable of cutting the neutron energy spectrum according to the present invention will be described with reference to the accompanying drawings, wherein like reference numerals are used to designate like or similar components to those of the first embodiment described above A duplicate description of the function is omitted.

9 is a perspective view showing a neutron cutting apparatus of FIG. 8, FIG. 10 is a sectional view of a neutron cutting apparatus according to a second embodiment of the present invention, 11 is a front cross-sectional view of the present neutron cutting apparatus cut along the line XI-XI in FIG. 9, and FIG. 12 is a sectional view of the mini-capsule taken along the line XII-XII in FIG.

8 through 12, the neutron cutting device 220 accommodated in the mini capsule 100 according to the present embodiment is different from the neutron cutting device 120 of the first embodiment described above in that the neutron cutting device 220 of the double- And a neutron absorber 224 housed between the tube body 221 and the double pipe wall of the tube body 221.

The tube body 221 includes an inner accommodating cylinder 222, an outer accommodating cylinder 223, and a pair of accommodating cylinder end caps 225.

The inner receiving cylinder 222 is formed in a cylindrical shape so as to form the sample receiving space 125 in the mini capsule body 110. The outer receiving cylinder 223 is formed inside the inner receiving cylinder 222, And is formed into a cylindrical shape having a diameter larger than that of the inner receiving cylinder 222 so as to form a double pipe structure.

Therefore, an absorber accommodation space for accommodating the neutron absorber 224 is provided between the outer peripheral surface of the inner receiving cylinder 222 and the inner peripheral surface of the outer receiving cylinder 223.

The receiving end caps 225 are connected to both ends of the inner receiving cylinder 222 and the outer receiving cylinder 223 to block both side openings of the absorber receiving space and to receive the neutron absorber 224 The end cap body portion 225a is formed in a hollow disc shape so as to close the absorber receiving space and open the sample receiving space 125 inside the inner receiving cylinder 122, 225a are protrudingly formed on the inner side of the absorbent body accommodating space so as to protrude an insertion protruding portion 225b for closing both side openings.

On the other hand, as described above, the neutron absorber 224 housed in the absorber accommodating space partitioned between the inner receiving cylinder 222 and the outer receiving cylinder 223 is preferably made of the above- It is preferable to insert the space 126 away from the insertion protrusions 225b of the receiving end caps 225 so as to be spaced apart from the space 126. In the space 126, (He) or the like.

In addition, the receiving end caps 225 may include three or more spacer projections 225c for separating the neutron trimming device 220 from the inner circumferential surface of the mini capsule main body 110, It is more preferable that they are formed so as to protrude at intervals along the circumferential direction.

The spacer projections 225c form a gap G between the inner circumferential surface of the mini capsule body 110 and the outer circumferential surface of the tube body 221 at which the neutron cutting device 220 is inserted, And serves to hold and confine the neutron cutting device 220 by the gap G. [

Here, the spacer projection 225c is formed by calculating the inner circumferential surface of the mini capsule body 110 and the outer circumferential surface gap G of the tube body 221, do.

As described above, the neutron cutting apparatus 220 of the present embodiment precisely processes an aluminum pipe having a diameter difference to fabricate the inner receiving cylinder 222 and the outer receiving cylinder 223, A disk-shaped receiving cylinder end cap 225 is manufactured, and the neutron absorber 224 is manufactured by rolling both ends of the sheet-form neutron absorbing material against each other in a cylindrical shape.

The neutron absorber 224 is inserted into the absorber storage space formed between the outer receiving cylinder 223 and the inner receiving cylinder 222 housed in the outer receiving cylinder 223, (225) are joined by using an electron beam or a laser beam to seal and seal both side openings of the absorber accommodation space.

As described above, the manufactured neutron cutting apparatus 220 is installed in the vacuum furnace 10 ^-7 at 450C to prevent the welding part from being deformed due to oxidation or the like after sealing during the irradiation test, After heating for about 8 hours, the state of thermal change is checked and visual inspection and X-ray radiographic inspection are carried out to check the integrity of dimensions and welding conditions.

As described above, the neutron cutting apparatus 220 of the present embodiment uses two of the inner receiving tubes 222 and the outer receiving tubes 223 having a diameter difference, It is possible to shorten the manufacturing cost and manufacturing time of the neutron cutting apparatus 220.

As described above, the irradiation test capsule 1 capable of cutting the neutron energy spectrum of the present invention has neutron absorbers 124 and 224 inside the walls of the tube bodies 121 and 221 constituting the neutron cutting apparatuses 120 and 220, The neutron energy spectrum irradiated to the sample storage space through the neutron energy spectrum is blocked and at least a part of the thermal neutrons or the neutrons outside the neutrons is blocked so that various irradiation conditions, By doing so, it is possible to conduct research tests that are essential for qualification of materials for the development of sodium-cooled fast reactor (SFR), as well as neutrons irradiation with specific energy for medical and new semiconductor development fields such as cancer treatment, Artificial jewelery development, and the like.

 While the present invention has been particularly shown and described with reference to exemplary embodiments thereof, it is to be understood that the invention is not limited to the disclosed exemplary embodiments, but many variations and modifications may be made without departing from the spirit and scope of the invention. And it goes without saying that they belong to the scope of the present invention.

1: irradiation test capsule 10: capsule body
11: upper support tube 12: lower support tube
15: intermediate support tube 15a: upper fixing groove
15b: lower fixing groove portion 16: upper end plate
17: Lower end plate 18: Rod tip
19: Load 20: Capsule loading space
21: lower guide part 22: lower guide spring
23: guide spring assembly 25: upper guide
26: grapple head lock 30: center support rod
31: Grapple head 32: Grapple head clamping nut
100: Mini capsule 110: Mini capsule body
111: upper fixing protrusion 115: inner storage space
120, 220: Neutron cutting device 121, 221: Stacking body
122: receiving cylinder 122a: absorber housing groove
123: receiving cylinder end cap 123a: end cap body
123b: insertion protrusion 124: neutron absorber
125: sample storage space 126: free space
130: mini capsule end cap 131: lower fixing projection
140: spacer block 222: inner receiving cylinder
223: outer receiving cylinder 224: neutron absorber
225: receiving cylinder end cap 225a: end cap body part
225b: insert protrusion 225c: spacer projection
310: sample 320: temperature indicator
330: Neutron measurer

Claims (9)

delete A neutron trimming device for trimming the spectrum of the neutron energy irradiated in the neutron furnace so as to realize the required irradiation test environment respectively housed in the mini capsules charged in the irradiation test capsule to perform the irradiation test in the neutron furnace and,

The neutron cutting apparatus includes:
A tubular body housed in the mini capsule and having a cylindrical shape to provide a sample storage space therein; And
And a neutron absorber disposed in a wall surface of the tube body to cut off at least a part of thermal neutrals or neutrons from the neutron energy spectrum irradiated to the sample storage space to cut a neutron energy spectrum,

The tube body includes:
A receiving cylinder having an absorber receiving groove formed at one end thereof to form an opening and to provide an absorber receiving space along the longitudinal direction; And
And a receiving cylinder end cap which is formed in a hollow plate shape so as to cover the opening formed at one end of the receiving cylinder to close the absorber receiving space accommodating the neutron absorber and to open the sample accommodating space inside the receiving cylinder, Capable of irradiation test of energy spectrum cut.
A neutron trimming device for trimming the spectrum of the neutron energy irradiated in the neutron furnace so as to realize the required irradiation test environment respectively housed in the mini capsules charged in the irradiation test capsule to perform the irradiation test in the neutron furnace and,

The neutron cutting apparatus includes:
A tubular body housed in the mini capsule and having a cylindrical shape to provide a sample storage space therein; And
And a neutron absorber installed in the wall surface of the tube body to cut at least a part of thermal neutrals or neutrons from the neutron energy spectrum irradiated to the sample storage space to cut a neutron energy spectrum.

The tube body includes:
An inner storage cylinder for forming the sample storage space therein;
An outer accommodating cylinder inserted into the inner accommodating cylinder concentrically and having an absorbent storage space for storing the neutron absorber between the outer circumferential surface of the inner receiving cylinder and the outer circumferential surface of the inner accommodating cylinder; And
Both sides of said inner receiving cylinder and said outer receiving cylinder are closed at both side openings of said absorber receiving space to close said absorber receiving space in which said neutron absorber is housed and to open said sample accommodating space inside said inner receiving cylinder An irradiation test capsule capable of cutting a neutron energy spectrum including a pair of receiving end caps in a plate shape.
3. The method according to claim 2 or 3,
The receiving cylinder end cap includes:
And the insertion protrusion is protruded so as to close the opening of the tube body by being inserted into the absorbent storage space.
5. The method of claim 4,
The neutron absorber may be formed,
And the neutron energy spectrum cut out is installed in the absorber accommodating space of the tube body with a clearance from the insertion protruding portion.
4. The method of claim 3,
The receiving cylinder end cap includes:
And a plurality of spacer protrusions for maintaining a gap between the inner circumferential surface of the mini capsule and the inner circumferential surface of the mini capsule are formed on the outer circumferential surface at intervals along the outer circumferential direction.
3. The method according to claim 2 or 3,
Wherein the tube body is made of an aluminum material, and the neutron energy spectrum can be cut.
3. The method according to claim 2 or 3,
The neutron absorber may be formed,
The neutron absorbing material in the form of sheet can be accommodated therein so that both end portions of the neutron absorbing material come into contact with each other so as to have a cylindrical shape capable of being housed integrally in the absorbent storage space.
3. The method according to claim 2 or 3,
The neutron absorber may be formed,
An irradiation test capsule capable of cutting a neutron energy spectrum comprising at least one neutron absorbing material selected from cadmium (Cd), hafnium (Hf), boron alloy, gadolinium compound or europium (Eu).

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