JP2001305278A - Low-activated shielding vessel - Google Patents

Low-activated shielding vessel

Info

Publication number
JP2001305278A
JP2001305278A JP2000125680A JP2000125680A JP2001305278A JP 2001305278 A JP2001305278 A JP 2001305278A JP 2000125680 A JP2000125680 A JP 2000125680A JP 2000125680 A JP2000125680 A JP 2000125680A JP 2001305278 A JP2001305278 A JP 2001305278A
Authority
JP
Japan
Prior art keywords
concrete layer
shielding
covered
outside
shell plate
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
JP2000125680A
Other languages
Japanese (ja)
Other versions
JP4310883B2 (en
Inventor
Keigo Mio
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
Original Assignee
IHI Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by IHI Corp filed Critical IHI Corp
Priority to JP2000125680A priority Critical patent/JP4310883B2/en
Publication of JP2001305278A publication Critical patent/JP2001305278A/en
Application granted granted Critical
Publication of JP4310883B2 publication Critical patent/JP4310883B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • 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

Landscapes

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

Abstract

PROBLEM TO BE SOLVED: To prevent the activation of a stainless outer shell plate for covering a vessel body by thermal neutrons. SOLUTION: The outside of the vessel body 2 made of stainless structural material is covered with a shielding concrete layer 4 through a heat insulating material 3. The outside of the shielding concrete layer 4 is covered with a thermal neutron absorbing concrete layer 8 containing boron. The outside of the thermal neutron absorbing concrete layer 8 is covered with the stainless material outer shell plate 5. The thermal neutrons generated in the shielding concrete layer 4 are absorbed by boron of the thermal neutron absorbing concrete layer 8 to avoid the activation of the stainless material outer shell plate 5.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[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。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a low activation shielding container used as a vacuum container for accommodating a nuclear fusion device.

【0002】[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。
2. Description of the Related Art In a vacuum vessel used to house a nuclear fusion device, not only shielding performance but also low activation is important.

【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。
[0003] Therefore, this kind of conventional vacuum vessel is shown in FIG.
(B) As shown in (b), the cylindrical portion and the upper lid portion of the container body 2 are made of a stainless steel structural material, and the outside thereof is covered with a shielding concrete layer 4 of a required thickness via the heat insulating material 3. In addition, there is provided a vacuum vessel 1 having a structure in which the outside of the shielding concrete layer 4 is covered with a stainless steel outer shell plate 5. Reference numeral 6 denotes a vacuum exhaust port, and reference numeral 7 denotes a container support.

【0004】[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。
However, in the case of the above-mentioned conventional vacuum vessel 1, since neutrons are mainly shielded by the shielding concrete layer 4, the heat generated in the shielding concrete layer 4 is eliminated. If neutrons activate the stainless steel outer shell plate 5 over time with the neutrons, there is a possibility of exposure.

【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。
[0005] Therefore, the present invention is to prevent the outer shell plate made of stainless steel from being activated by thermal neutrons.

【0006】[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。
According to the present invention, in order to solve the above-mentioned problems, the outside of the container body is covered with a concrete layer for shielding, and the outside of the concrete layer for shielding is heated with boron. The concrete layer for thermal neutron absorption is covered with a concrete layer for thermal neutron absorption, and the outside of the concrete layer for thermal neutron absorption is covered with a shell plate made of stainless steel, and the amount of boron contained in the concrete layer for thermal neutron absorption. Is set to about 1%.

【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。
[0007] Since the outside of the shielding concrete layer is covered with a boron-containing concrete layer for absorbing thermal neutrons, thermal neutrons that cause activation can be absorbed by the concrete layer for absorbing thermal neutrons. The outer stainless steel shell plate can be prevented from being activated.

【0008】[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。
Embodiments of the present invention will be described below with reference to the drawings.

【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。
FIG. 1 shows an embodiment of the present invention. As in the case of the vacuum container shown in FIGS. 2A and 2B, the outside of a container body 2 made of stainless steel is successively heat-insulated. 3. In the configuration in which the concrete layer 4 for shielding and the outer shell plate 5 made of stainless steel are covered in layers, the thermal neutron absorption is provided between the concrete layer 4 for shielding and the outer shell plate 5 made of stainless steel. A low-energy radiation shielding container in which a thermal neutron absorbing concrete layer 8 impregnated with about 1% of boron (boron) as a material is interposed and arranged.

【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。
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 amount of boron added to the thermal neutron absorbing concrete layer 8 was set to about 1% because the amount of boron added was 1% in order to absorb thermal neutrons.
% Is necessary and sufficient.

【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。
Since boron impregnated in the thermal neutron absorbing concrete layer 8 absorbs thermal neutrons which cause activation, the thermal neutrons generated in the shielding concrete layer 4 can be absorbed by boron. Thermal neutrons can be blocked by the neutron absorbing concrete layer 8. Therefore, the activation of the outer shell plate 5 can be prevented, and the exposure of workers to radiation can be prevented. Further, since the activation of the outer shell plate 5 can be avoided, embrittlement of the stainless steel material which is the material of the outer shell plate 5 can be suppressed.

【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。
It should be noted that the present invention is not limited to only the above embodiment, and the concrete layer 8 for absorbing thermal neutrons is used.
Can be arbitrarily selected, and various changes can be made without departing from the scope of the present invention.

【0013】[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。
As described above, according to the low activation container of the present invention, the outside of the container main body is covered with the concrete layer for shielding, and the outside of the concrete layer for shielding is heated with boron. Covered with a neutron absorbing concrete layer,
The outer surface 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%. The thermal neutrons generated in the shielding concrete layer can be blocked by the thermal neutron absorbing concrete layer, which prevents the activation of the outer shell plate made of stainless steel. I do.

【図面の簡単な説明】[Brief description of the drawings]

【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。
FIG. 1 is an enlarged sectional view of a part of a low activation shielding container according to an embodiment of the present invention.

【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。
FIGS. 2A and 2B show an example of a vacuum vessel, wherein FIG. 2A is a schematic side view of the whole, and FIG. 2B is an enlarged sectional view of a portion A of FIG.

【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[Description of Signs] 2 Container body 4 Concrete layer for shielding 5 Shell plate 8 Concrete layer for absorbing thermal neutrons

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 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。
1. A concrete for thermal neutron absorption, wherein the outside of the container body is covered with a concrete layer for shielding, and the outside of the concrete layer for shielding is covered with a concrete layer for thermal neutron absorption containing boron. A low-energy shielding container having a structure in which the outside of a layer is covered with an outer shell plate made of stainless steel.
【請求項2】 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 activation 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)

Priority Applications (1)

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

Applications Claiming Priority (1)

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

Publications (2)

Publication Number Publication Date
JP2001305278A true JP2001305278A (en) 2001-10-31
JP4310883B2 JP4310883B2 (en) 2009-08-12

Family

ID=18635589

Family Applications (1)

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

Country Status (1)

Country Link
JP (1) JP4310883B2 (en)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2006072279A1 (en) * 2004-12-29 2006-07-13 Gesellschaft für Schwerionenforschung mbH Multi-layered radiation protection wall and radiation protection chamber
JP2007155497A (en) * 2005-12-05 2007-06-21 Japan Atomic Energy Agency Neutron beam shielding structure and its building method
JP2007155499A (en) * 2005-12-05 2007-06-21 Japan Atomic Energy Agency Neutron beam shielding structure and method of building neutron beam shielding structure
WO2007126161A1 (en) * 2006-05-01 2007-11-08 Nihon Shelter System Co., Ltd. Underground shelter
JP2008304303A (en) * 2007-06-07 2008-12-18 Fujita Corp Neutron-shielding body
JP2013521492A (en) * 2010-03-01 2013-06-10 ウェスティングハウス エレクトリック スウェーデン アーベー Neutron absorber and method for the production of neutron absorber
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
CN108053906A (en) * 2017-12-14 2018-05-18 东莞理工学院 It is a kind of for radiation protection block of neutron scientific research and preparation method thereof
EP3810559A4 (en) * 2018-05-09 2022-03-09 Mirrotron Kft. Neutron absorbing concrete wall and method for producing such concrete wall

Cited By (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7820993B2 (en) 2004-12-29 2010-10-26 Gsi Helmholtzzentrum Fur Schwerionenforschung Gmbh Multi-layered radiation protection wall and radiation protection chamber
WO2006072279A1 (en) * 2004-12-29 2006-07-13 Gesellschaft für Schwerionenforschung mbH Multi-layered radiation protection wall and radiation protection chamber
JP2007155497A (en) * 2005-12-05 2007-06-21 Japan Atomic Energy Agency Neutron beam shielding structure and its building method
JP2007155499A (en) * 2005-12-05 2007-06-21 Japan Atomic Energy Agency Neutron beam shielding structure and method of building 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
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
JP2007297898A (en) * 2006-05-01 2007-11-15 Nihon Shelter System Co Ltd Underground shelter and method for forming bearing partition wall of underground shelter
WO2007126161A1 (en) * 2006-05-01 2007-11-08 Nihon Shelter System Co., Ltd. Underground shelter
US7918056B2 (en) 2006-05-01 2011-04-05 Nihon Shelter System Co., Ltd. Underground shelter
JP2008304303A (en) * 2007-06-07 2008-12-18 Fujita Corp Neutron-shielding body
JP2013521492A (en) * 2010-03-01 2013-06-10 ウェスティングハウス エレクトリック スウェーデン アーベー Neutron absorber and method for the production of neutron absorber
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
CN108053906A (en) * 2017-12-14 2018-05-18 东莞理工学院 It is a kind of for radiation protection block of neutron scientific research and preparation method 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
EP3810559A4 (en) * 2018-05-09 2022-03-09 Mirrotron Kft. Neutron absorbing concrete wall and method for producing such concrete wall

Also Published As

Publication number Publication date
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