KR20140030385A - Neutron absorber and method of manufacturing thereof - Google Patents

Neutron absorber and method of manufacturing thereof Download PDF

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Publication number
KR20140030385A
KR20140030385A KR1020120093866A KR20120093866A KR20140030385A KR 20140030385 A KR20140030385 A KR 20140030385A KR 1020120093866 A KR1020120093866 A KR 1020120093866A KR 20120093866 A KR20120093866 A KR 20120093866A KR 20140030385 A KR20140030385 A KR 20140030385A
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South Korea
Prior art keywords
neutron
base material
deposition layer
boron
neutron absorber
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KR1020120093866A
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Korean (ko)
Inventor
이경황
박종원
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주식회사 포스코
재단법인 포항산업과학연구원
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Priority to KR1020120093866A priority Critical patent/KR20140030385A/en
Publication of KR20140030385A publication Critical patent/KR20140030385A/en

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    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D15/00—Separating processes involving the treatment of liquids with solid sorbents; Apparatus therefor
    • C—CHEMISTRY; METALLURGY
    • C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F1/00—Treatment of water, waste water, or sewage
    • C02F1/28—Treatment of water, waste water, or sewage by sorption
    • C02F1/281—Treatment of water, waste water, or sewage by sorption using inorganic sorbents
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008—Containers for fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Hydrology & Water Resources (AREA)
  • Water Supply & Treatment (AREA)
  • Organic Chemistry (AREA)
  • Environmental & Geological Engineering (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Analytical Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Physical Vapour Deposition (AREA)

Abstract

The present invention provides a method for producing a neutron absorber comprising a neutron absorber having a base material and a deposition layer containing a neutron absorbing material on the surface of the base material and depositing a neutron absorber on the surface of the base material.
By using the method for producing a neutron absorber of the present invention, various types of neutron absorbers can be manufactured, and the manufacturing process can be simplified.

Description

Neutron absorber and method for manufacturing thereof

The present invention relates to a neutron absorber and a manufacturing method thereof.

There are two methods for storing spent fuel: temporarily stored in a tank, stored in a container, and disposed of permanently. The tank used for the temporary storage in the tank is provided with a metal rack (rack) inside, the rack is required to absorb neutrons, and excellent corrosion resistance. In addition, the container used for storing in the container should also be made of a neutron absorber to prevent neutron outflow to the outside.

As disclosed in Japanese Patent Application Laid-Open No. 2002-0078856, conventionally, after adding B4C or BN powder to stainless steel or aluminum powder, an extrusion process is performed to produce a quadrangular tube for accommodating spent fuel assemblies. To prepare a neutron absorber. However, when the neutron absorber is manufactured by such a conventional method, a number of processes and a high level of technology are required, and in particular, when B4C or BN powder is added to the stainless steel or aluminum, the workability becomes poor, and thus the processing into various shapes is performed. There was a difficult problem.

One aspect of the present invention is to provide a method for manufacturing a neutron absorber that can simplify the manufacturing process by depositing a neutron absorbent material on the surface of the base material, and can provide various types of neutron absorbers and a neutron absorber prepared by the above method.

According to one embodiment of the present invention, a neutron absorber having a base material and a deposition layer containing a neutron absorbing material on the surface of the base material is provided.

The neutron absorbing material may be any one of boron carbide, boron nitride, and mixtures thereof.

Boron included in the deposition layer may be at least 40% by weight of the total deposition layer weight.

Isotope 10 B of the boron included in the deposition layer may be more than 19% of the total boron.

The thickness of the deposition layer may be 0.4 ~ 0.8% of the thickness of the base material.

The metal may be any one of stainless steel and aluminum.

The stainless steel may be any one of STS 304, STS 304LN, STS 316, and STS 316LN.

According to another embodiment of the present invention, there is provided a neutron absorber manufacturing method comprising the step of depositing a neutron absorbing material on the surface of the base material.

The neutron absorbing material may be deposited by plasma chemical vapor deposition.

The neutron absorbing material may be any one of boron carbide, boron nitride, and mixtures thereof.

Boron included in the deposition layer may be at least 40% by weight of the total deposition layer weight.

Isotope 10 B of the boron included in the deposition layer may be more than 19% of the total boron.

The thickness of the deposition layer may be 0.4 ~ 0.8% of the thickness of the base material.

The base material may be any one of stainless steel and aluminum.

The stainless steel may be any one of STS 304, STS 304LN, STS 316, and STS 316LN.

By using the method for producing a neutron absorber of the present invention, various types of neutron absorbers can be manufactured, and the manufacturing process can be simplified.

1 schematically shows a neutron absorber of the present invention.

The present invention relates to a neutron absorber and a method for producing a neutron absorber prepared by depositing a neutron absorbent material on the surface of a base material. The present invention has the advantage of producing a neutron absorber without limitation of form by depositing a neutron absorbing material on the surface of the base material processed in various forms. In addition, since the neutron absorbing material is deposited on the surface of the base material to prepare the neutron absorbing material, the manufacturing process can be simplified.

1 schematically illustrates a neutron absorber of the present invention including a base layer 200 and a deposition layer 100 containing a neutron absorbent material, which will be described with reference to this.

According to one embodiment of the present invention, a neutron absorber having a base material 200 and a deposition layer 100 containing a neutron absorbing material on the surface of the base material 200 is provided. The deposition layer 100 of the neutron absorbing material contains a neutron absorbing material, which is suitable for manufacturing spent fuel storage containers and the like.

The neutron absorbing material may be boron carbide, boron nitride and mixtures thereof. However, the present invention is not limited thereto, and a neutron absorbing material which can be easily used by those skilled in the art may be used.

Boron included in the deposition layer of the neutron absorber may be at least 40% by weight of the total deposition layer weight. The higher the boron content in the deposition layer, the better the neutron absorption performance. However, when the content of boron is less than 40% by weight, the content of boron in the deposition layer is small and may not have the neutron absorption performance required by the present invention. Preferably the boron content may be 60% by weight or more.

Isotopes of the boron include 10 B and 11 B. Of these, the isotope 10B accounts for about 19.9% of the total boron in nature and has excellent neutron absorption. Therefore, although the ratio of the isotope 10B in the boron included in the deposition layer 100 is not particularly limited, it is preferable that it is 19% or more of the total boron.

The deposition layer 100 may effectively absorb neutrons when the deposition layer 100 is deposited in a thickness of a predetermined ratio or more relative to the thickness of the base material 200. In the neutron absorber of the present invention, the thickness of the deposition layer 100 is the base material ( 200) may be 0.4 to 0.8% of the thickness. If it is less than 0.4%, the neutron absorbing effect is insignificant, so it is not suitable as a neutron absorber used for storing spent nuclear fuel, and if it exceeds 0.8%, the deposition layer 100 is easily peeled from the base material 200 by internal stress, It is difficult to obtain the neutron absorption effect, resulting in poor economic efficiency and workability. More preferably, it may be 0.5 to 0.6%. For example, when the thickness of the metal base material 200 is 5 mm, the thickness of the deposition layer 100 may be 200 to 400 μm on a single side.

In the present invention, since the neutron absorbing material can be manufactured by depositing a neutron absorbing material on the surface of the base material 200, the base material 200 is not particularly limited, and the base material 200 which can be used by those skilled in the art can be used. For example, it may be any one of stainless steel and aluminum conventionally used as the base material 200 of the neutron absorber, and the stainless steel is not particularly limited in kind, for example, STS 304, STS 304LN, STS Preference is given to using either 316 or STS 316LN.

The base material 200 of the neutron absorber may be preprocessed in various forms before depositing the neutron absorber. Although the metal to which the conventional neutron-absorbing material powder is added is inferior in workability, the manufacturing method of the present invention can produce a neutron-absorbing material without limiting the form by depositing a neutron-absorbing material on the surface of the pre-processed base material 200. .

The shape of the base material 200 to be processed is not particularly limited, but may be a quadrangular tube shape for accommodating the spent fuel assembly. However, the form of the metal is not particularly limited thereto, and may be processed into a form that can be easily implemented by a person skilled in the art for storing spent nuclear fuel.

According to another embodiment of the present invention, there is provided a neutron absorber manufacturing method comprising the step of depositing a neutron absorbing material on the surface of the base material 200. The method of depositing the neutron absorbing material on the surface of the base material 200 is not particularly limited, and may be deposited in a manner that can be easily implemented by those skilled in the art. Preferably, chemical vapor deposition can be used.

Chemical vapor deposition is an industrial method for making thin films of silicon and the like on substrates in manufacturing processes such as ICs (Integrated Circuits). It is a surface treatment method using the property of radicalization, the reactivity becomes high, and it adsorb | sucks and deposits on a board | substrate. The deposition by raising the temperature is called 'thermal chemical vapor deposition', the use of light to promote chemical reaction or pyrolysis is called 'light chemical vapor deposition', and the excitation of gas into plasma is called 'plasma chemical vapor deposition'.

In the present invention, in particular, a plasma chemical vapor deposition method is used, in which the neutron absorbing material is plasma-deposited and deposited on the surface of the base material 200, and is performed under the following conditions. However, the present invention is not limited thereto, and may be performed within a range in which a person skilled in the art may perform plasma chemical vapor deposition.

The plasma is produced at reduced pressure (relative to ambient or atmospheric pressure). Preferably, the reduced pressure is preferably 0.5 Torr to 5 Torr. If the vacuum degree of the reduced pressure is less than 0.5 Torr, the deposition rate is low, the deposition time is long, there is a disadvantage that the deposition process is unstable because the plasma state is unstable at a state higher than 5 Torr.

Preferably, the plasma chemical vapor deposition method is performed by using a neutron absorbing material as RF as the main power, and applying a current with the electrodes subjected to the micro pulse power as the auxiliary power. In the case of processing a large-scale large workpiece by using RF power alone, it is difficult to uniformly process the workpiece due to electromagnetic influence and space non-uniformity in a large space. In order to solve the non-uniform electromagnetic field, the micro pulses are employed as auxiliary power to form the deposition layer 100. In addition, the preferred RF frequency range for carrying out the invention is from 100 kHz to less than 300 MHz, more preferably from 1 to 50 MHz, even more preferably from 10 to 15 MHz. At this time, the frequency of the micro pulse auxiliary power is preferably supplied with a frequency of 1 ~ 50kHz.

There are several advantages of using an RF power source as the main power: The heating of the base material 200 is lower because the RF operates a lower power source. Since the present invention imparts plasma deposition on the metal surface, lower processing temperatures are desirable to prevent melting and distortion of the substrate 200. In order to prevent the substrate 200 from overheating when using the microwave plasma chemical vapor deposition method, the microwave plasma chemical vapor deposition method is applied to short bursts by pulsed power. Power pulsing increases the cycle time for deposition, which is undesirable in the present invention. In addition, the higher the microwave frequency may cause offgassing of volatile materials such as residual moisture, oligomers and other materials in the substrate 200. Such degassing can interfere with deposition by plasma chemical vapor deposition.

For the coating of the present invention, plasma is generated using electrodes powered by a power source sufficient to form a deposition on the substrate 200 surface. Although not particularly limited, the plasma is preferably formed by applying a vacuum degree of 0.5 to 5 Torr, a main power RF frequency of 10 to 15 MHz, and an auxiliary micro pulse power frequency of 1 to 50 kHz.

The neutron absorbing material included in the gas reactant may be boron carbide, boron nitride, and mixtures thereof. However, the present invention is not limited thereto, and a neutron absorbing material which can be easily used by those skilled in the art may be used.

Boron included in the deposition layer of the neutron absorber may be at least 40% by weight of the total deposition layer weight. The higher the boron content in the deposition layer, the better the neutron absorption performance. However, when the content of boron is less than 40% by weight, the content of boron in the deposition layer is small and may not have the neutron absorption performance required by the present invention. Preferably the boron content may be 60% by weight or more.

Isotopes of the boron include 10 B and 11 B. Of these, the isotope 10B accounts for about 19.9% of the total boron in nature and has excellent neutron absorption. Therefore, although the ratio of the isotope 10B in the boron included in the deposition layer 100 is not particularly limited, it is preferable that it is 19% or more of the total boron. More preferably 25% or more.

The deposition layer 100 may effectively absorb neutrons when the deposition layer 100 is deposited in a thickness of a predetermined ratio or more relative to the thickness of the base material 200. In the neutron absorber of the present invention, the thickness of the deposition layer 100 is the base material ( 200) may be 0.4 to 0.8% of the thickness. If it is less than 0.4%, the neutron absorbing effect is insignificant, so it is not suitable as a neutron absorber used for storing spent nuclear fuel, and if it exceeds 0.8%, the deposition layer 100 is easily peeled from the base material 200 by internal stress, It is difficult to obtain the neutron absorption effect, resulting in poor economic efficiency and workability. More preferably, it may be 0.5 to 0.6%. For example, when the thickness of the metal base material 200 is 5 mm, the thickness of the deposition layer 100 may be 200 to 400 μm on a single side.

Since the neutron absorbing material can be manufactured by depositing a neutron absorbing material on the surface of the base material 200 by the chemical vapor deposition method of the present invention, the base material 200 is not particularly limited, and the base material 200 which can be used by those skilled in the art. Can be used. For example, the metal may be any one of stainless steel and aluminum that are conventionally used as the base material 200 of the neutron absorber, and the stainless steel is not particularly limited in kind, for example, STS 304, STS Preference is given to using any of 304LN, STS 316 and STS 316LN.

The neutron absorber manufacturing method may be a step of processing the base material 200 first. That is, the base material 200 used to manufacture the neutron absorber may be pre-processed in various forms before the neutron absorber is deposited on the base material 200 by chemical vapor deposition. Although the metal to which the conventional neutron-absorbing material powder is added is inferior in workability, in the manufacturing method of the present invention, the neutron-absorbing material can be manufactured without limitation in form by depositing a neutron-absorbing material on the surface of the pre-processed base material 200.

The shape of the base material 200 to be processed is not particularly limited, but may be a quadrangular tube shape for accommodating the spent fuel assembly. However, the shape of the base material 200 is not particularly limited thereto, and may be processed into a form that can be easily implemented by a person skilled in the art for storing spent nuclear fuel.

The present invention can be variously modified and changed without departing from the spirit of the present invention provided by the claims below.

100: neutron absorber-containing deposition layer
200: base material

Claims (15)

Base material and
A neutron absorber having a deposition layer containing a neutron absorbing material on the surface of the base material. The neutron absorber of claim 1, wherein the neutron absorbing material is any one of boron carbide, boron nitride, and mixtures thereof. The neutron absorber of claim 2, wherein boron included in the deposition layer is 40 wt% or more of the total deposition layer weight. The neutron absorber of claim 2, wherein a ratio of isotope 10 B in the boron included in the deposition layer is 19% or more of the total boron. The neutron absorber of claim 1, wherein the thickness of the deposition layer is 0.4 to 0.8% of the thickness of the base material. The neutron absorber of claim 1, wherein the base material is any one of stainless steel and aluminum. The neutron absorber of claim 6, wherein the stainless steel is any one of STS 304, STS 304LN, STS 316, and STS 316LN. A neutron absorber manufacturing method comprising the step of depositing a neutron absorbing material on the surface of the base material. The method of claim 8, wherein the neutron absorbing material is deposited by plasma chemical vapor deposition. The method of claim 8, wherein the neutron absorbing material is any one of boron carbide, boron nitride, and mixtures thereof. The method of claim 10, wherein the boron included in the deposition layer is 40 wt% or more of the total deposition layer weight. The method of claim 10, wherein the ratio of isotope 10B in the boron included in the deposition layer is 19% or more of the total boron. The method of claim 8, wherein the thickness of the deposition layer is 0.4 to 0.8% of the thickness of the base material. The method of claim 8, wherein the base material is any one of stainless steel and aluminum. 15. The method of claim 14, wherein the stainless steel is any one of STS 304, STS 304LN, STS 316, and STS 316LN.
KR1020120093866A 2012-08-27 2012-08-27 Neutron absorber and method of manufacturing thereof KR20140030385A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103956192A (en) * 2014-05-07 2014-07-30 镇江市纽科利核能新材料科技有限公司 Novel high-density neutron absorption plate

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103956192A (en) * 2014-05-07 2014-07-30 镇江市纽科利核能新材料科技有限公司 Novel high-density neutron absorption plate

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