JP4310883B2 - Low activation shielding container - Google Patents

Low activation shielding container Download PDF

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Publication number
JP4310883B2
JP4310883B2 JP2000125680A JP2000125680A JP4310883B2 JP 4310883 B2 JP4310883 B2 JP 4310883B2 JP 2000125680 A JP2000125680 A JP 2000125680A JP 2000125680 A JP2000125680 A JP 2000125680A JP 4310883 B2 JP4310883 B2 JP 4310883B2
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Japan
Prior art keywords
concrete layer
shielding
outer shell
thermal neutron
shell plate
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Expired - Fee Related
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JP2000125680A
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Japanese (ja)
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JP2001305278A (en
Inventor
圭吾 三尾
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
IHI Corp
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IHI Corp
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Filing date
Publication date
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Priority to JP2000125680A priority Critical patent/JP4310883B2/en
Publication of JP2001305278A publication Critical patent/JP2001305278A/en
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

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  • Building Environments (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Particle Accelerators (AREA)

Description

【0001】
【発明の属する技術分野】
本発明は核融合装置を収納する真空容器として用いられる低放射化遮蔽容器に関するものである。
【0002】
【従来の技術】
核融合装置を収納するために用いられる真空容器は、遮蔽性能のみならず、低放射化性も重要である。
【0003】
そのため、従来のこの種真空容器は、図2(イ)(ロ)に一例を示す如く、容器本体2の円筒部や上蓋部をステンレス構造材で作製し、その外側を、断熱材3を介して所要厚さの遮蔽用コンクリート層4で覆うようにし、更に、該遮蔽用コンクリート層4の外側をステンレス材製の外殻板5で覆うようにしてなる構成の真空容器1としてある。6は真空排気ポート、7は容器支持台を示す。
【0004】
【発明が解決しようとする課題】
ところが、上記従来の真空容器1の場合、主として遮蔽用コンクリート層4で中性子の遮蔽を行うようにするものであるため、遮蔽用コンクリート層4内で発生した熱中性子がその外側のステンレス材製の外殻板5を経時的に放射化すると、被曝の可能性が出てくる。
【0005】
そこで、本発明は、ステンレス材製の外殻板が熱中性子によって放射化されることがないようにしようとするものである。
【0006】
【課題を解決するための手段】
本発明は、上記課題を解決するために、容器本体の外側を遮蔽用コンクリート層で被覆し、且つ該遮蔽用コンクリート層の外側を、ボロンを含有させた熱中性子吸収用コンクリート層で被覆して、該熱中性子吸収用コンクリート層の外側を、ステンレス材製の外殻板で被覆してなる構成とし、又、熱中性子吸収用コンクリート層に含有するボロンの量を1%程度とした構成とする。
【0007】
遮蔽用コンクリート層の外側をボロンを含有させた熱中性子吸収用コンクリート層で被覆したことから、放射化の原因となる熱中性子を熱中性子吸収用コンクリート層で吸収することができて、外側のステンレス材製の外殻板の放射化を防ぐことができるようになる。
【0008】
【発明の実施の形態】
以下、本発明の実施の形態を図面を参照して説明する。
【0009】
図1は本発明の実施の一形態を示すもので、図2(イ)(ロ)に示した真空容器と同様に、ステンレス構造材製とした容器本体2の外側を順次断熱材3、遮蔽用コンクリート層4、ステンレス材製の外殻板5で層状に覆うようにしてある構成において、上記遮蔽用コンクリート層4とステンレス材製の外殻板5との間に、熱中性子吸収材としてのボロン(ホウ素)を1%程度添加して含浸させてある熱中性子吸収用コンクリート層8を層状に介在配置してなる低放射化遮蔽容器とする。
【0010】
上記熱中性子吸収用コンクリート層8の厚さは、たとえば、容器本体2の内面から外殻板5の外面までの厚さを30cmとしたとき、5cm程度である。なお、熱中性子吸収用コンクリート層8のボロンの添加量を1%程度としたのは、熱中性子の吸収のためには1%程度で必要充分だからである。
【0011】
熱中性子吸収用コンクリート層8に含浸させたボロンは放射化の原因となる熱中性子を吸収するので、遮蔽用コンクリート層4内で発生した熱中性子をボロンで吸収することができ、熱中性子吸収用コンクリート層8で熱中性子を遮断することができる。したがって、外殻板5の放射化を防ぐことができ、作業員への被爆防止を図ることができる。又、外殻板5の放射化を避けることができるようになることから、外殻板5の材質であるステンレス材の脆化を抑制することができる。
【0012】
なお、本発明は上記実施の形態にのみ限定されるものではなく、熱中性子吸収用コンクリート層8の厚さは任意に選定できること、その他本発明の要旨を逸脱しない範囲内において種々変更を加え得ることは勿論である。
【0013】
【発明の効果】
以上述べた如く、本発明の低放射化容器によれば、容器本体の外側を遮蔽用コンクリート層で被覆し、且つ該遮蔽用コンクリート層の外側を、ボロンを含有させた熱中性子吸収用コンクリート層で被覆して、該熱中性子吸収用コンクリート層の外側を、ステンレス材製の外殻板で被覆してなる構成とし、又、熱中性子吸収用コンクリート層に含有するボロンの量を1%程度とした構成としてあるので、遮蔽用コンクリート層内で発生した熱中性子を熱中性子吸収用コンクリート層で遮断することができ、これにより、ステンレス材製の外殻板の放射化を防ぐことができる、という優れが効果を発揮する。
【図面の簡単な説明】
【図1】本発明の低放射化遮蔽容器の実施の一形態を示す容器一部の拡大断面図である。
【図2】真空容器の一例を示すもので、(イ)は全体の概略側面図、(ロ)は(イ)のA部拡大断面図である。
【符号の説明】
2 容器本体
4 遮蔽用コンクリート層
5 外殻板
8 熱中性子吸収用コンクリート層
[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a low radiation shielding container used as a vacuum container for storing a fusion device.
[0002]
[Prior art]
A vacuum vessel used for housing a fusion device is important not only for shielding performance but also for low radiation.
[0003]
Therefore, in this conventional vacuum vessel, as shown in FIG. 2 (B) and (B), the cylindrical portion and the upper lid portion of the vessel body 2 are made of a stainless structural material, and the outside thereof is interposed through the heat insulating material 3. Thus, the vacuum container 1 is configured so as to be covered with a shielding concrete layer 4 having a required thickness, and further, the outer side of the shielding concrete layer 4 is covered with an outer shell plate 5 made of stainless steel. Reference numeral 6 denotes an evacuation port, and 7 denotes a container support.
[0004]
[Problems to be solved by the invention]
However, in the case of the conventional vacuum vessel 1, since the neutron is shielded mainly by the shielding concrete layer 4, the thermal neutrons generated in the shielding concrete layer 4 are made of stainless steel on the outside. If the outer shell plate 5 is activated with time, the possibility of exposure will appear.
[0005]
Therefore, the present invention is intended to prevent the outer shell plate made of stainless steel from being activated by thermal neutrons.
[0006]
[Means for Solving the Problems]
In order to solve the above-mentioned problem, the present invention covers the outside of the container body with a shielding concrete layer, and coats the outside of the shielding concrete layer with a thermal neutron absorbing concrete layer containing boron. The outer layer of the thermal neutron absorbing concrete layer is covered with a stainless steel outer shell plate, and the amount of boron contained in the thermal neutron absorbing concrete layer is about 1%. .
[0007]
Since the outer surface of the shielding concrete layer is coated with a thermal neutron absorbing concrete layer containing boron, thermal neutrons that cause activation can be absorbed by the thermal neutron absorbing concrete layer, and the outer stainless steel layer It becomes possible to prevent activation of the outer shell plate made of material.
[0008]
DETAILED DESCRIPTION OF THE INVENTION
Hereinafter, embodiments of the present invention will be described with reference to the drawings.
[0009]
FIG. 1 shows an embodiment of the present invention. Similar to the vacuum container shown in FIGS. 2 (A) and 2 (B), the outside of a container body 2 made of a stainless steel structure is sequentially covered with a heat insulating material 3 and shielded. In the configuration in which the concrete layer 4 and the outer shell plate 5 made of stainless steel are covered in layers, a thermal neutron absorber is interposed between the shielding concrete layer 4 and the outer shell plate 5 made of stainless steel. A thermal radiation neutron absorbing concrete layer 8 impregnated with about 1% of boron (boron) is provided as a low radiation shielding container having a layered interposition.
[0010]
The thickness of the thermal neutron absorbing concrete layer 8 is, for example, about 5 cm when the thickness from the inner surface of the container body 2 to the outer surface of the outer shell plate 5 is 30 cm. The reason why the amount of boron added to the thermal neutron absorbing concrete layer 8 is about 1% is that about 1% is necessary and sufficient for absorbing thermal neutrons.
[0011]
Boron impregnated in the thermal neutron absorption concrete layer 8 absorbs thermal neutrons that cause activation, so that thermal neutrons generated in the shielding concrete layer 4 can be absorbed by boron, and the thermal neutron absorption Thermal neutrons can be blocked by the concrete layer 8. Therefore, activation of the outer shell plate 5 can be prevented, and exposure to workers can be prevented. Further, since the activation of the outer shell plate 5 can be avoided, embrittlement of the stainless steel material that is the material of the outer shell plate 5 can be suppressed.
[0012]
In addition, this invention is not limited only to the said embodiment, The thickness of the concrete layer 8 for thermal neutron absorption can be selected arbitrarily, and various changes can be added within the range which does not deviate from the summary of this invention. Of course.
[0013]
【The invention's effect】
As described above, according to the low activation container of the present invention, the outer side of the container body is covered with the shielding concrete layer, and the outer side of the shielding concrete layer is boron-containing concrete layer for thermal neutron absorption. And the outside of the concrete layer for absorbing thermal neutrons is covered with a stainless steel outer shell plate, and the amount of boron contained in the concrete layer for absorbing thermal neutrons is about 1%. Because it is configured, the thermal neutrons generated in the shielding concrete layer can be blocked by the thermal neutron absorbing concrete layer, which can prevent the activation of the stainless steel outer shell plate Excellent is effective.
[Brief description of the drawings]
FIG. 1 is an enlarged sectional view of a part of a container showing an embodiment of a low activation shielding container of the present invention.
FIGS. 2A and 2B show an example of a vacuum vessel. FIG. 2A is a schematic side view of the whole, and FIG.
[Explanation of symbols]
2 Container body 4 Concrete layer for shielding 5 Outer shell plate 8 Concrete layer for absorbing thermal neutrons

Claims (2)

容器本体の外側を遮蔽用コンクリート層で被覆し、且つ該遮蔽用コンクリート層の外側を、ボロンを含有させた熱中性子吸収用コンクリート層で被覆して、該熱中性子吸収用コンクリート層の外側を、ステンレス材製の外殻板で被覆させてなる構成を有することを特徴とする低放射化遮蔽容器。The outside of the container body is covered with a shielding concrete layer, and the outside of the shielding concrete layer is covered with a thermal neutron absorbing concrete layer containing boron, and the outside of the thermal neutron absorbing concrete layer is A low-radiation shielding container characterized by having a configuration in which it is covered with an outer shell plate made of stainless steel. 熱中性子吸収用コンクリート層に含有するボロンの量を1%程度とした請求項1記載の低放射化遮蔽容器。2. The low radiation shielding container according to claim 1, wherein the amount of boron contained in the thermal neutron absorbing concrete layer is about 1%.
JP2000125680A 2000-04-26 2000-04-26 Low activation shielding container Expired - Fee Related JP4310883B2 (en)

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JP2000125680A JP4310883B2 (en) 2000-04-26 2000-04-26 Low activation shielding container

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Application Number Priority Date Filing Date Title
JP2000125680A JP4310883B2 (en) 2000-04-26 2000-04-26 Low activation shielding container

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JP4310883B2 true JP4310883B2 (en) 2009-08-12

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Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE102004063732B4 (en) 2004-12-29 2013-03-28 Gsi Helmholtzzentrum Für Schwerionenforschung Gmbh Radiation protection chamber with in particular a multi-layered radiation protection wall
JP4586199B2 (en) * 2005-12-05 2010-11-24 独立行政法人 日本原子力研究開発機構 Construction method of neutron beam shielding structure
JP4590536B2 (en) * 2005-12-05 2010-12-01 独立行政法人 日本原子力研究開発機構 Construction method of neutron beam shielding structure
JP4072734B2 (en) 2006-05-01 2008-04-09 日本シェルターシステム株式会社 Underground shelter and underground shelter strength partition wall forming method
JP4883634B2 (en) * 2007-06-07 2012-02-22 株式会社フジタ Neutron shield and accelerator chamber formed by the neutron shield
SE536814C2 (en) * 2010-03-01 2014-09-16 Westinghouse Electric Sweden Neutron Absorbing Component and Process for Preparing a Neutron Absorbing Component
JP2017125715A (en) * 2016-01-12 2017-07-20 株式会社アトックス Neutron shielding body
EP3266754A1 (en) 2016-07-07 2018-01-10 Ion Beam Applications S.A. Compositions of low activation concrete and use thereof
CN108053906B (en) * 2017-12-14 2019-08-06 东莞理工学院 A kind of radiation protection block and preparation method thereof for neutron scientific research
HU231202B1 (en) * 2018-05-09 2021-10-28 Mirrotron Kft. Concrete wall for adsorbing neutron radiation and method for producing thereof

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