JP2016206145A - Neutron shield - Google Patents

Neutron shield Download PDF

Info

Publication number
JP2016206145A
JP2016206145A JP2015091684A JP2015091684A JP2016206145A JP 2016206145 A JP2016206145 A JP 2016206145A JP 2015091684 A JP2015091684 A JP 2015091684A JP 2015091684 A JP2015091684 A JP 2015091684A JP 2016206145 A JP2016206145 A JP 2016206145A
Authority
JP
Japan
Prior art keywords
neutron
shielding member
water
mass
neutron shielding
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.)
Pending
Application number
JP2015091684A
Other languages
Japanese (ja)
Inventor
哲一 木下
Tetsuichi Kinoshita
哲一 木下
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.)
Shimizu Construction Co Ltd
Shimizu Corp
Original Assignee
Shimizu Construction Co Ltd
Shimizu 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 Shimizu Construction Co Ltd, Shimizu Corp filed Critical Shimizu Construction Co Ltd
Priority to JP2015091684A priority Critical patent/JP2016206145A/en
Publication of JP2016206145A publication Critical patent/JP2016206145A/en
Pending legal-status Critical Current

Links

Images

Landscapes

  • Curing Cements, Concrete, And Artificial Stone (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide a neutron shield that can be manufactured from abundant materials and has high shielding capability.SOLUTION: (1) A neutron shield 1 is provided that comprises a neutron shielding member 2 containing water absorptive polymer, water and cement, and a holding member 3 for holding the neutron shielding member 2. (2) The neutron shield 1 is provided in which the holding member is a concrete box and the neutron shielding member is held in the box. (3) The neutron shield 1 is provided in which the total content of water contained in the neutron shielding member with respect to the gross mass of the neutron shielding member is 50-80 mass%. (4) The neutron shield 1 is provided in which the content of cement wit respect to the gross mass of the neutron shielding member is 10-40 mass%. (5) The neutron shield 1 is provided in which the content of water absorptive polymer with respect to the gross mass of the neutron shielding member is 1-10 mass%. (6) The neutron shield 1 is provided in which the water absorptive polymer is composed of a polyacrylic acid or its derivatives.SELECTED DRAWING: Figure 1

Description

本発明は、水分を含む中性子遮蔽体に関する。   The present invention relates to a neutron shield containing moisture.

従来、高い透過力のある中性子線を遮蔽する目的でコンクリート製の遮蔽体が使われている。例えば、コンクリートの骨材としてコレマナイトやヒルガダイト等の含ホウ素鉱物を使用し、コンクリート中のホウ素濃度を高めることにより、中性子線の遮蔽能力を高める技術が開示されている（特許文献１，２）。   Conventionally, concrete shields have been used to shield neutron beams with high penetrating power. For example, a technique is disclosed in which a boron-containing mineral such as colemanite or hirugadite is used as the aggregate of concrete, and the boron concentration in the concrete is increased to enhance the shielding ability of neutron beams (Patent Documents 1 and 2).

特開平６−１６４５号公報JP-A-6-1645 特開２０１４−１４１３８４号公報JP 2014-141384 A

しかしながら、前記含ホウ素鉱物は国内で生産されておらず、全て輸入に依存しているため国内で安定的に利用することに障害が生じる恐れがある、という問題があった。   However, since the boron-containing minerals are not produced domestically and all depend on imports, there is a problem that there is a possibility that obstacles may occur in stable use in the country.

本発明は、上記事情に鑑みてなされたものであり、潤沢な原料で製造可能であり、高い遮蔽能力を有する中性子遮蔽体の提供を課題とする。   The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a neutron shield that can be manufactured with abundant raw materials and has high shielding ability.

［１］吸水性ポリマー、水、及びセメントを含む中性子遮蔽部材と、前記中性子遮蔽部材を保持する保持部材と、を備えたことを特徴とする中性子遮蔽体。
［２］前記保持部材がコンクリート製の箱であり、前記箱の中に前記中性子遮蔽部材が保持されてなることを特徴とする上記［１］に記載の中性子遮蔽体。
［３］前記中性子遮蔽部材の総質量に対する当該中性子遮蔽部材に含まれる水分の総含有量が、５０〜８０質量％であることを特徴とする上記［１］又は［２］に記載の中性子遮蔽体。
［４］前記中性子遮蔽部材の総質量に対する前記セメントの含有量が、１０〜４０質量％であることを特徴とする上記［１］〜［３］の何れか一項に記載の中性子遮蔽体。
［５］前記中性子遮蔽部材の総質量に対する前記吸水性ポリマーの含有量が、１〜１０質量％であることを特徴とする上記［１］〜［４］の何れか一項に記載の中性子遮蔽体。
［６］前記吸水性ポリマーが、ポリアクリル酸又はその誘導体からなることを特徴とする上記［１］〜［５］の何れか一項に記載の中性子遮蔽体。 [1] A neutron shield comprising: a neutron shielding member containing a water-absorbing polymer, water, and cement; and a holding member that holds the neutron shielding member.
[2] The neutron shield according to [1], wherein the holding member is a concrete box, and the neutron shielding member is held in the box.
[3] The neutron shielding as described in [1] or [2] above, wherein a total content of water contained in the neutron shielding member with respect to a total mass of the neutron shielding member is 50 to 80% by mass. body.
[4] The neutron shield according to any one of [1] to [3], wherein a content of the cement with respect to a total mass of the neutron shielding member is 10 to 40% by mass.
[5] The neutron shielding according to any one of the above [1] to [4], wherein a content of the water absorbing polymer with respect to a total mass of the neutron shielding member is 1 to 10% by mass. body.
[6] The neutron shield according to any one of [1] to [5], wherein the water-absorbing polymer is made of polyacrylic acid or a derivative thereof.

本発明の中性子遮蔽体によれば、水が本来的に有する中性子線を吸収する性質を利用するため、高い遮蔽能力を示す。また、その水は吸水性ポリマーに吸収された状態で安定に保たれており、外部へ流出する恐れがない。さらに、吸水性ポリマー及び水は含ホウ素鉱物に比べて潤沢な原料であり、安定的に製造することができる。   According to the neutron shield of the present invention, since the property of absorbing neutron rays inherent in water is utilized, high shielding ability is exhibited. Further, the water is stably maintained in a state of being absorbed by the water-absorbing polymer, and there is no fear of flowing out to the outside. Furthermore, the water-absorbing polymer and water are abundant raw materials compared to boron-containing minerals, and can be produced stably.

本発明に係る中性子遮蔽体の第一実施形態の断面図である。It is sectional drawing of 1st embodiment of the neutron shield which concerns on this invention.

本発明に係る中性子遮蔽体の第一実施形態は、図１に示す様に、吸水性ポリマー、その吸水性ポリマーに吸収された水、及びセメントを含む中性子遮蔽部材２と、中性子遮蔽部材２を保持する保持部材３と、を備えた中性子遮蔽体１である。   As shown in FIG. 1, the first embodiment of the neutron shield according to the present invention includes a neutron shielding member 2 containing a water-absorbing polymer, water absorbed by the water-absorbing polymer, and cement, and a neutron shielding member 2. A neutron shield 1 including a holding member 3 to hold.

保持部材３は容器部３ａと蓋部３ｂとからなり、容器部３ａの中に中性子遮蔽部材２が保持されて、蓋部３ｂによって密封されている。   The holding member 3 includes a container portion 3a and a lid portion 3b. The neutron shielding member 2 is held in the container portion 3a and is sealed by the lid portion 3b.

保持部材３の材料は特に限定されないが、中性子遮蔽部材２に含まれる水分が蒸発し難い、水分透過性の低い材料であることが好ましい。このような材料として、例えば、コンクリート、セラミックス、木材、合成樹脂等が挙げられる。   Although the material of the holding member 3 is not particularly limited, it is preferable that the water contained in the neutron shielding member 2 is difficult to evaporate and has a low moisture permeability. Examples of such materials include concrete, ceramics, wood, and synthetic resin.

保持部材３の形態は、内部に中性子遮蔽部材２を保持することが可能な形態であれば特に限定されず、中性子遮蔽部材２を安定に保持し、持ち運びや設置が容易である観点から、図１に示す様に、コンクリート製の箱型部材であることが好ましい。
また、箱型に替えて、樹脂製の袋を保持部材として使用した袋型の保持部材であってもよい。 The form of the holding member 3 is not particularly limited as long as it can hold the neutron shielding member 2 therein, and from the viewpoint of stably holding the neutron shielding member 2 and being easy to carry and install. As shown in FIG. 1, it is preferably a concrete box-shaped member.
Further, instead of the box shape, a bag-type holding member using a resin bag as a holding member may be used.

中性子遮蔽部材２の総質量に対する当該中性子遮蔽部材に含まれる水分の総含有量は、例えば、５０〜８０質量％が好ましく、６０〜８０質量％がより好ましく、７０〜８０質量％がさらに好ましい。   50-80 mass% is preferable, for example, as for the total content of the water | moisture content contained in the said neutron shielding member with respect to the total mass of the neutron shielding member 2, 60-80 mass% is more preferable, and 70-80 mass% is further more preferable.

ここで、前記水分の総含有量には、前記吸水性ポリマーに吸収された水だけでなく、中性子遮蔽部材２を構成する前記吸水性ポリマー以外の材料、例えばセメント、に保持された水も含まれる。
前記水分の総含有量の上記範囲の下限値以上であると、遮蔽性能をより向上させることができる。上記範囲の上限値以下であると、保持部材の安定性をより向上させることができる。例えば、水分の総含有量が極度に高い場合、当該水分が吸水性ポリマーに吸収されずに自由に流動可能な状態の自由水となる場合がある。このような自由水は保持部材３の外部へ流出する恐れがあるので、自由水が存在しないことが好ましい。したがって、中性子遮蔽部材２に含まれる水分の総含有量は、吸水性ポリマー及びセメントの少なくとも一方に保持され得る量以下であることが好ましい。 Here, the total water content includes not only water absorbed in the water-absorbing polymer but also water retained in materials other than the water-absorbing polymer constituting the neutron shielding member 2, such as cement. It is.
Shielding performance can be improved more as it is more than the lower limit of the said range of the said total content of the said water | moisture content. The stability of a holding member can be improved more as it is below the upper limit of the said range. For example, when the total water content is extremely high, the water may become free water that can flow freely without being absorbed by the water-absorbing polymer. Since such free water may flow out of the holding member 3, it is preferable that there is no free water. Therefore, it is preferable that the total content of water contained in the neutron shielding member 2 is equal to or less than the amount that can be held in at least one of the water-absorbing polymer and cement.

中性子遮蔽部材２に含まれる水分の総含有量は、例えば、公知の水分計を使用して測定するか、より正確には、ＪＩＳ Ａ １１２５に準拠して、破砕した中性子遮蔽部材２を１０５℃で乾燥させて、乾燥前後の質量を測定して算出することができる。   The total content of water contained in the neutron shielding member 2 is measured using, for example, a known moisture meter, or more precisely, according to JIS A 1125, the crushed neutron shielding member 2 is 105 ° C. It can be calculated by measuring the mass before and after drying.

前記水分の総含有量が７０〜８０質量％である場合、中性子線を充分に遮蔽する観点から、中性子線が中性子遮蔽部材に入射する方向に見て、中性子遮蔽部材２の厚みは、例えば３０〜１００ｃｍであることが好ましく、５０〜１００ｃｍであることがより好ましく、７０〜１００ｃｍであることがさらに好ましい。   When the total content of the water is 70 to 80% by mass, the thickness of the neutron shielding member 2 is, for example, 30 in view of the direction in which the neutron rays are incident on the neutron shielding member from the viewpoint of sufficiently shielding the neutron rays. It is preferably ˜100 cm, more preferably 50 to 100 cm, and even more preferably 70 to 100 cm.

中性子遮蔽部材２の総質量に対する前記セメントの含有量は、例えば、１０〜４０質量％が好ましく、１０〜３０質量％がより好ましく、１０〜２０質量％がさらに好ましい。
上記範囲の下限値以上であると、中性子遮蔽部材２の硬化度合を高めて、その構造的強度を向上させることができる。上記範囲の上限値以下であると、吸水性ポリマー及び水分をより多く含有させて、遮蔽性能を向上させることができる。 10-40 mass% is preferable, for example, as for content of the said cement with respect to the gross mass of the neutron shielding member 2, 10-30 mass% is more preferable, and 10-20 mass% is further more preferable.
When it is at least the lower limit of the above range, the degree of curing of the neutron shielding member 2 can be increased, and its structural strength can be improved. When the amount is not more than the upper limit of the above range, more water-absorbing polymer and moisture can be contained to improve the shielding performance.

前記セメントとして従来のセメントが適用可能である。前記セメントの種類は特に限定されず、例えば、普通ポルトランドセメント、早強ポルトランドセメント、中庸熱ポルトランドセメント、白色ポルトランドセメント等のポルトランドセメント；高炉セメント、シリカセメント、フライアッシュセメント等の混合セメント；アルミナセメント等の特殊セメント等が挙げられる。   Conventional cement can be applied as the cement. The type of the cement is not particularly limited. For example, ordinary portland cement, early-strength portland cement, moderately hot portland cement, white portland cement and other portland cement; blast furnace cement, silica cement, fly ash cement and other mixed cement; alumina cement And special cements.

前記セメントは、水を含むセメントペーストが硬化してなるセメントであってもよいし、水及び砂を含むモルタルペーストが硬化してなるモルタルであってもよい。   The cement may be a cement formed by hardening a cement paste containing water, or may be a mortar formed by hardening a mortar paste containing water and sand.

中性子遮蔽部材２の総質量に対する前記吸水性ポリマーの含有量は、例えば、１〜１０質量％が好ましく、１〜７質量％がより好ましく、１〜４質量％がさらに好ましい。
上記範囲の下限値以上であると、当該吸水性ポリマーに含有される水分量を高めて遮蔽性能をより向上させることができる。上記範囲の上限値以下であると、セメントの含有量を高めて保持部材の安定性をより向上させることができる。 The content of the water-absorbing polymer with respect to the total mass of the neutron shielding member 2 is, for example, preferably 1 to 10% by mass, more preferably 1 to 7% by mass, and further preferably 1 to 4% by mass.
When it is at least the lower limit of the above range, the amount of water contained in the water-absorbing polymer can be increased to further improve the shielding performance. When the amount is not more than the upper limit of the above range, the cement content can be increased and the stability of the holding member can be further improved.

前記吸水性ポリマーは、水を吸収することが可能なポリマーであれば特に限定されず、例えば水を吸収してゲル化する公知のポリマーが適用可能である。この様なポリマーとして、例えば、ポリアクリル酸及び／又はその誘導体からなるポリマーが挙げられる。   The water-absorbing polymer is not particularly limited as long as it is a polymer that can absorb water, and for example, a known polymer that gels by absorbing water is applicable. Examples of such a polymer include a polymer made of polyacrylic acid and / or a derivative thereof.

ポリアクリル酸の重量平均分子量Ｍｗは特に限定されず、水を充分に保持し、中性子遮蔽材中に均一に分散することが容易である観点から、例えば、１万〜１０００万が好ましく、１万〜１００万がより好ましく、１万〜１０万がさらに好ましい。
上記範囲の下限値以上あると、中性子遮蔽部材２に適度な粘度を付与して、仮に硬化していない状態であったとしても、中性子遮蔽体１の運搬時や製造時に保持部材３の外部へ流出することを抑制することができる。上記範囲の上限値以下であると、中性子遮蔽部材２の粘度が過度に高くなることを防止したり、ポリアクリル酸が中性子遮蔽部材２中でセメント成分と分離したりすることを抑制し、中性子遮蔽部材２中に均一に分散させることができる。
ポリアクリル酸及びその誘導体の重量平均分子量Ｍｗは、ＧＰＣを使用した標準ポリスチレン換算値として測定される。 The weight average molecular weight Mw of the polyacrylic acid is not particularly limited, and is preferably 10,000 to 10,000,000, for example, from the viewpoint of sufficiently retaining water and being easily dispersed uniformly in the neutron shielding material. ˜1 million is more preferred, and 10,000 to 100,000 is more preferred.
If it is above the lower limit of the above range, even if the neutron shielding member 2 is imparted with an appropriate viscosity and is not cured, the neutron shielding body 1 is transported or manufactured to the outside of the holding member 3 at the time of manufacture. Outflow can be suppressed. When the viscosity is not more than the upper limit of the above range, the viscosity of the neutron shielding member 2 is prevented from becoming excessively high, or the polyacrylic acid is prevented from separating from the cement component in the neutron shielding member 2, and the neutron It can be uniformly dispersed in the shielding member 2.
The weight average molecular weight Mw of polyacrylic acid and its derivative is measured as a standard polystyrene conversion value using GPC.

ポリアクリル酸の誘導体は、ポリアクリル酸を使用する分野で公知の誘導体であり、例えば、ポリアクリル酸のα炭素原子に結合する水素原子（α水素）が炭素数１〜５の有機基で置換された誘導体、ポリアクリル酸の側鎖のカルボン酸エステル等が挙げられる。また、ポリアクリル酸の分子鎖同士が架橋された公知の架橋型ポリアクリル酸も誘導体に含まれる。このような架橋型ポリアクリル酸は、例えば特許第２６７２８６４号公報に記載されている。   Polyacrylic acid derivatives are known in the field of using polyacrylic acid. For example, a hydrogen atom (α hydrogen) bonded to an α carbon atom of polyacrylic acid is substituted with an organic group having 1 to 5 carbon atoms. Derivatives thereof, and side chain carboxylic acid esters of polyacrylic acid. In addition, known cross-linked polyacrylic acid in which molecular chains of polyacrylic acid are cross-linked is also included in the derivative. Such cross-linked polyacrylic acid is described in, for example, Japanese Patent No. 2672864.

中性子遮蔽部材２において、吸水性ポリマーの質量／セメントの質量で表される質量比は、例えば、０．０５〜１．０が好ましく、０．４〜１．０がより好ましく、０．７〜１．０がさらに好ましい。
上記範囲の下限値以上であることにより、中性子遮蔽部材２に充分な量の水分を含ませることができる。上記範囲の上限値以下であることにより、中性子遮蔽部材２を充分に硬化させて、中性子遮蔽体１の構造的強度を高めることができる。 In the neutron shielding member 2, the mass ratio represented by the mass of the water-absorbing polymer / the mass of the cement is, for example, preferably 0.05 to 1.0, more preferably 0.4 to 1.0, and 0.7 to 1.0 is more preferable.
By being above the lower limit of the above range, the neutron shielding member 2 can contain a sufficient amount of moisture. By being below the upper limit of the said range, the neutron shielding member 2 can fully be hardened and the structural strength of the neutron shielding body 1 can be raised.

（製造方法）
本実施形態の中性子遮蔽体１の製造方法の一例を説明する。
吸水性ポリマー１〜４質量部に水７０〜８０質量部を添加し、吸水性ポリマーに水を吸収させる。次に、水を吸収してゲル状となった吸水性ポリマー７１〜８４質量部に、セメント１６〜２９質量部を混合し、得られた混合物が硬化する前に、所望の大きさのコンクリート製の箱３ａ（容器部３ａ）の中に注入する。１日静置して、中性子遮蔽部材２が硬化した後、コンクリート製の蓋３ｂ（蓋部３ｂ）を載せて、別途用意したセメントで接着することにより、箱３ａ内に中性子遮蔽部材が密封された中性子遮蔽体１が得られる。 (Production method)
An example of the manufacturing method of the neutron shield 1 of this embodiment is demonstrated.
70 to 80 parts by mass of water is added to 1 to 4 parts by mass of the water-absorbing polymer, and the water-absorbing polymer absorbs water. Next, the water-absorbing polymer 71-84 parts by mass that absorbs water is mixed with 16-29 parts by mass of cement, and the resulting mixture is hardened before it is cured. Into the box 3a (container portion 3a). The neutron shielding member 2 is hardened after being left standing for one day, and then a concrete lid 3b (lid portion 3b) is placed and bonded with a separately prepared cement, thereby sealing the neutron shielding member in the box 3a. The obtained neutron shield 1 is obtained.

本例では、中性子遮蔽部材２を完全に硬化させたが、吸水性ポリマー又は水の配合量を増やすことにより、半硬化状態又はゲル状態の中性子遮蔽部材２としてもよい。   In this example, the neutron shielding member 2 is completely cured, but the neutron shielding member 2 in a semi-cured state or a gel state may be obtained by increasing the amount of the water-absorbing polymer or water.

箱３ａ内に注入する中性子遮蔽部材２の量は特に限定されず、例えば、箱３ａの容量の５０体積％以上であってもよいし、７５体積％以上であってもよいし、１００体積％であってもよい。   The amount of the neutron shielding member 2 injected into the box 3a is not particularly limited. For example, it may be 50% by volume or more, 75% by volume or more, or 100% by volume of the capacity of the box 3a. It may be.

製造された中性子遮蔽体１は、中性子線源から放射される中性子線を遮蔽したい箇所に設置して用いられる。中性子線は中性子遮蔽体１を透過し難いため、中性子線源と保護対象物との間に中性子遮蔽体１を設置することにより、保護対象物に中性子線が到達することを抑制することができる。
また、中性子遮蔽体１を従来のコンクリートブロックやレンガと同様の建材として使用し、複数の中性子遮蔽体１を並べて塀や建物を建造してもよい。 The manufactured neutron shield 1 is used by being installed at a place where it is desired to shield the neutron beam emitted from the neutron beam source. Since the neutron beam does not easily pass through the neutron shield 1, the neutron beam can be prevented from reaching the protection object by installing the neutron shield 1 between the neutron source and the protection object. .
Alternatively, the neutron shield 1 may be used as a building material similar to a conventional concrete block or brick, and a plurality of neutron shields 1 may be arranged to construct a fence or a building.

以上で説明した各実施形態における各構成及びそれらの組み合わせ等は一例であり、本発明の趣旨を逸脱しない範囲で、構成の付加、省略、置換、およびその他の変更が可能である。   The configurations and combinations thereof in the embodiments described above are examples, and the addition, omission, replacement, and other modifications of the configurations can be made without departing from the spirit of the present invention.

１…中性子遮蔽体、２…中性子遮蔽部材、３…保持部材、３ａ…容器部、３ｂ…蓋部 DESCRIPTION OF SYMBOLS 1 ... Neutron shielding body, 2 ... Neutron shielding member, 3 ... Holding member, 3a ... Container part, 3b ... Cover part

Claims (6)

吸水性ポリマー、水、及びセメントを含む中性子遮蔽部材と、前記中性子遮蔽部材を保持する保持部材と、を備えたことを特徴とする中性子遮蔽体。 A neutron shield comprising: a neutron shielding member containing a water-absorbing polymer, water, and cement; and a holding member that holds the neutron shielding member. 前記保持部材がコンクリート製の箱であり、前記箱の中に前記中性子遮蔽部材が保持されてなることを特徴とする請求項１に記載の中性子遮蔽体。 The neutron shield according to claim 1, wherein the holding member is a concrete box, and the neutron shielding member is held in the box. 前記中性子遮蔽部材の総質量に対する当該中性子遮蔽部材に含まれる水分の総含有量が、５０〜８０質量％であることを特徴とする請求項１又は２に記載の中性子遮蔽体。 The total content of moisture contained in the neutron shielding member with respect to the total mass of the neutron shielding member is 50 to 80% by mass, The neutron shield according to claim 1 or 2. 前記中性子遮蔽部材の総質量に対する前記セメントの含有量が、１０〜４０質量％であることを特徴とする請求項１〜３の何れか一項に記載の中性子遮蔽体。 The content of the cement with respect to the total mass of the neutron shielding member is 10 to 40 mass%, and the neutron shield according to any one of claims 1 to 3. 前記中性子遮蔽部材の総質量に対する前記吸水性ポリマーの含有量が、１〜１０質量％であることを特徴とする請求項１〜４の何れか一項に記載の中性子遮蔽体。 5. The neutron shield according to claim 1, wherein a content of the water-absorbing polymer with respect to a total mass of the neutron shielding member is 1 to 10% by mass. 前記吸水性ポリマーが、ポリアクリル酸又はその誘導体からなることを特徴とする請求項１〜５の何れか一項に記載の中性子遮蔽体。 The neutron shield according to any one of claims 1 to 5, wherein the water-absorbing polymer is made of polyacrylic acid or a derivative thereof.
JP2015091684A 2015-04-28 2015-04-28 Neutron shield Pending JP2016206145A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2015091684A JP2016206145A (en) 2015-04-28 2015-04-28 Neutron shield

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2015091684A JP2016206145A (en) 2015-04-28 2015-04-28 Neutron shield

Publications (1)

Publication Number Publication Date
JP2016206145A true JP2016206145A (en) 2016-12-08

Family

ID=57489689

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2015091684A Pending JP2016206145A (en) 2015-04-28 2015-04-28 Neutron shield

Country Status (1)

Country Link
JP (1) JP2016206145A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5119300A (en) * 1974-08-08 1976-02-16 Japan Atomic Energy Res Inst HOSHASENSHAHEIYOFUKUGOZAI
JPH10300880A (en) * 1997-04-23 1998-11-13 Tadao Sakurai Nuclear power station and radioactive waste treatment facility with radiation shielding outer periphery wall

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5119300A (en) * 1974-08-08 1976-02-16 Japan Atomic Energy Res Inst HOSHASENSHAHEIYOFUKUGOZAI
JPH10300880A (en) * 1997-04-23 1998-11-13 Tadao Sakurai Nuclear power station and radioactive waste treatment facility with radiation shielding outer periphery wall

Similar Documents

Publication Publication Date Title
Saleh et al. Innovative cement-based materials for environmental protection and restoration
US20100258751A1 (en) Borated Concrete-Rubber
JP6253930B2 (en) Radiation shielding material, radiation waste storage container, and method for manufacturing radiation waste storage container
JP2008536105A (en) Waste disposal method
CN103193439B (en) High integrity container sealing material and preparation method thereof and application
CN104098306A (en) Unfired water-permeable brick and preparation method thereof
JP2016206145A (en) Neutron shield
CN100580817C (en) Method for treating refuse in nuclear-power station
KR101688646B1 (en) Dual Layered Concrete for High-level Neutron Shielding Method for Manufacturing the Same
JP5832019B2 (en) Method for producing radiation shielding mortar and method for producing radiation shielding container
CN104310815B (en) A kind of cement
CN103880336B (en) The asphalt of anti-ultraviolet aging performance
CN106116670A (en) A kind of method utilizing mud and subway shoveling sintering self-insulating brick
JP2781566B2 (en) Cement solidification method and solidified body of radioactive waste
CN103588461A (en) Curing agent for fuse, and preparation method thereof
CN111689708B (en) High-calcium geological cement for nuclide solidification and application method
CN114751664A (en) Waste incineration fly ash geopolymer and preparation method thereof
CN102503341A (en) Ardealite building material and preparation method thereof
CN107445573A (en) A kind of radiation shield concrete
KR102181217B1 (en) A method of solidifying radioactive waste and the solidified waste form thereof
ES2440116A1 (en) Procedure for obtaining structural anti-radiation concrete (Machine-translation by Google Translate, not legally binding)
Song et al. Microscopic characterization and radon exhalation of metakaolin-uranium tailings polymer solidified body under alkali activation
JP2015152464A (en) Radiation shield body and radiation shield structure
CN107673643A (en) A kind of resistance to deformation cement material
CN109020381A (en) A kind of external thermal insulation system inorganic water-proof plate

Legal Events

Date Code Title Description
A621 Written request for application examination

Free format text: JAPANESE INTERMEDIATE CODE: A621

Effective date: 20171206

A977 Report on retrieval

Free format text: JAPANESE INTERMEDIATE CODE: A971007

Effective date: 20180815

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20180821

A02 Decision of refusal

Free format text: JAPANESE INTERMEDIATE CODE: A02

Effective date: 20190305