WO1994014167A1 - RADIATION-BARRIER MATERIAL CAPABLE OF SIMULTANEOUS SHIELDING AGAINST η-RAY, X-RAY AND NEUTRON BEAM - Google Patents
RADIATION-BARRIER MATERIAL CAPABLE OF SIMULTANEOUS SHIELDING AGAINST η-RAY, X-RAY AND NEUTRON BEAM Download PDFInfo
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- WO1994014167A1 WO1994014167A1 PCT/JP1993/001799 JP9301799W WO9414167A1 WO 1994014167 A1 WO1994014167 A1 WO 1994014167A1 JP 9301799 W JP9301799 W JP 9301799W WO 9414167 A1 WO9414167 A1 WO 9414167A1
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- 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
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/10—Organic substances; Dispersions in organic carriers
- G21F1/103—Dispersions in organic carriers
- G21F1/106—Dispersions in organic carriers metallic dispersions
Definitions
- Radiation shielding material capable of simultaneous shielding of X-rays, X-rays and neutrons
- the present invention relates to a radiation shielding material that simultaneously shields X-rays and neutron rays, and more particularly to a radiation facility, storage of radioactive waste, nuclear fuel, radioisotope (RI), etc., transport containers and related equipment. And other radiation shielding materials.
- Shielding of X-rays and X-rays in radiation does not differ much in the mass attenuation coefficient of any substance, and the higher the density of the substance, the larger the linear attenuation coefficient and the smaller the thickness of the shield.
- lead, iron, concrete, etc. are used.
- high-molecular materials such as polyethylene, paraffin, and epoxy resin mixed with boron, and materials containing large amounts of hydrogen such as water are mainly used. Since concrete also contains hydrogen, it is used as a construction material that also serves as a shield.
- Hydrogen is very important for shielding neutrons.Fast neutrons irradiated into a substance lose their energy due to elastic scattering with hydrogen atoms in the substance and become thermal neutrons.Thermal neutrons are hydrogen and other elements Captured by nuclei. Thermal neutrons are more likely to be captured by nuclei with a larger thermal neutron capture cross section, but in this case secondary ⁇ rays may be emitted, so neutron beam shielding should include the shielding of this secondary y ray. There must be.
- a neutron-shielding material such as polyethylene, paraffin, or water
- an a-ray shielding material such as lead or iron.
- radiation facilities involving neutrons, shielding of waste, nuclear fuel, RI, etc., transport containers, and related equipment are constructed of high-density concrete, lead, iron, etc.
- the shield is made of polyethylene, paraffin, water, etc. as a completely different shield while being manufactured, or the shield is made of only a concrete structure.
- the present invention eliminates the need for the above-mentioned drawback of a double structure by simultaneously shielding neutron rays, 7 rays, and X-rays, and has sufficient strength, excellent moldability, workability, and heat resistance.
- An object of the present invention is to provide a new type of low-cost radiation shielding material having excellent properties, hydrophobicity and chemical resistance.
- radiation shielding materials were generally considered separately for 7 wires, X-rays, and neutrons.
- a substance with a high density is effective for shielding materials for X-rays and X-rays, whereas a substance containing a large amount of hydrogen is more effective for neutrons, so it is conceptually a low-density substance.
- the hydrogen content (% by weight) of the composition consisting of high-density inorganic material and synthetic resin is significantly lower than that of the molded product obtained from the resin alone, which is the base material. Was also thought to fall with it.
- the present inventors have focused on the fact that what is important in neutron shielding is not simply the hydrogen content (% by weight), but the number of hydrogen atoms per unit volume (hydrogen atom density).
- the hydrogen atom density of the composition obtained by mixing the high-density inorganic substance in the thermosetting resin material is higher than the hydrogen content (weight ),
- the neutron shielding effect was not as high as that of the resin alone as the base material. Reached.
- thermosetting resin material selected from a fuanol resin, an epoxy resin, a cresol resin, a xylene resin, a urea resin, and an unsaturated polyester.
- a fuanol resin an epoxy resin, a cresol resin, a xylene resin, a urea resin, and an unsaturated polyester.
- a radiation shielding material capable of simultaneously shielding X-rays, X-rays, and neutrons, characterized by containing 50 to 2,000 parts by weight of various inorganic substances and having a molded article density of 2.0 or more is provided. You.
- thermosetting resin which contains a large amount of hydrogen and is strong against heat
- the radiation shielding material for example, the radiation shielding material in the present invention.
- fuynol resin, epoxy resin, cresol resin, xylene resin, urea resin, non- A saturated polyester resin or the like may be used alone or in combination of two or more.
- Thermosetting resins have sufficient strength, excellent moldability and addi- bility, and are relatively heat-resistant dogs. Depending on their selection, they can be used at 150 ° C or higher.
- the molecular weight range or the degree of polymerization of the thermosetting resin used in the present invention is not particularly limited.
- the use of a substance with as high a density as possible increases the shielding effect of 7 rays and X-rays, and an element with a large thermal neutron capture cross section or a substance containing a large amount of such elements is more effective in shielding neutron rays.
- a high-density inorganic substance having these properties it is possible to produce a more excellent radiation shielding material.
- the high-density inorganic substances used in the present invention include Pb, W, Cr, Co, Cu, Fe, Mn, Mo, Ag, Ta, Cd, Dy, Eu, Gd, Au, In , H g, Re, Sn and U, or at least one element selected from the group consisting of these compounds is used in a powder or pellet state.
- These compounds also include minerals such as, for example, iron ore, nickel ore, and copper ore.
- the amount of the inorganic substance added to the thermosetting resin is preferably in the range of 50 to 2000 parts by weight of the inorganic substance per 100 parts by weight of the thermosetting resin. If it is less than 50 parts by weight, the shielding effect of a-rays and X-rays is inferior. In addition, the molded product becomes brittle and the mechanical strength of the molded product is deteriorated.
- the most effective shielding is performed by appropriately setting the mixing ratio within the above mixing ratio depending on the intensity and characteristics of various radiations. be able to.
- the density of the molded product must be 2.0 or more. Below this value, the ability to shield 7 rays and X-rays is inferior and unsuitable for simultaneous shielding. Since the density of concrete is usually 2.0 to 2.2, it must be larger than the shielding capacity of concrete.
- a high-density inorganic substance is added to the thermosetting resin, and a hydrogen storage alloy that has a relatively high dissociation temperature and combines and holds hydrogen up to a high temperature is added and mixed to maintain high density.
- a hydrogen storage alloy that has a relatively high dissociation temperature and combines and holds hydrogen up to a high temperature is added and mixed to maintain high density.
- Hydrogen storage alloys have a hydrogen atom density equivalent to that of polymer compounds such as resins, but are considerably higher in density than polymer compounds, so they are very effective for simultaneous shielding of neutron rays, ⁇ rays, and X-rays.
- Hydrogen storage alloys can store hydrogen as metal hydrides by reacting with hydrogen gas, and Ti, La (R), Mg, and Ca systems are known. However, for this purpose, an Mg system with a high hydrogen dissociation temperature at normal pressure is considered optimal.
- M g H 2 M g systems such as, M g. 2 M g- N i system such as N i 2, M, such as M g C u Ho 7 g- C u system, M g C a H 3 72 M g- C a system such as, and metal hydrides such as L a- M g system such as L a 2 M g 17 H 17 .
- the amount of hydrogen storage alloy added depends on product cost and cost. In consideration of the radiation shielding performance and the like, the range is preferably 1 to 50 parts by weight with respect to 100 parts by weight of the thermosetting resin.
- the thickness (1Z10 valence layer) of each test material for setting the dose equivalent rate of each radiation to 110 was determined, and the evaluation was performed based on the thickness.
- Bisphenol-based modified epoxy resin (epicon R-130A manufactured by Dainippon Ink and Chemicals, Inc., curing agent: Epicon R-130 BW manufactured by Dainippon Ink and Chemicals, Inc.) as a thermosetting resin and liquid Using phenolic resin (Regitop PL-4558, manufactured by Gunei Chemical Industry Co., Ltd., methanol-soluble), and metal lead powder, lead oxide (II) (specific gravity: 9.53), and tungsten oxide (VI) as high-density inorganic substances. Powders of wolframite (specific gravity: about 7.16) and iron pellets (specific gravity: 7.85), which are minerals whose main components are, are selected according to the mixing ratio shown in Table 1.
- test material 12 100 0 0 150 150 2000
- the test material cannot be manufactured because it is brittle.
- test material cannot be manufactured because it is brittle.
- the examples of No. 10, No. 11, and No. 13 have the same or higher neutron shielding capacity than the concrete of No. 16, which is a comparative example.
- it shows excellent y-ray shielding ability close to that of No. 17 carbon steel (SS41), which also has high performance in both a-ray, X-ray shielding ability and neutron ray shielding ability.
- SS41 No. 17 carbon steel
- the superiority was clearly recognized as compared with any of the comparative examples, and by changing the mixing ratio,
- the X-ray and X-ray shielding performance and neutron shielding performance can be set arbitrarily, and it is possible to manufacture the most effective shielding material according to the situation at that site.
- the test materials of No. 12 and No. 14 were brittle and could not be manufactured, and the neutron shielding performance of the test material of No. 11 was lower than that of concrete.
- the mixing ratio of the high-density inorganic substance to 200 parts by weight exceeds 2000 parts by weight, it is understood that a sufficient neutron beam shielding effect cannot be obtained and a molded article having sufficient strength cannot be obtained. .
- test material No. 7 in Test 1 The density and shielding ability of the test material No. 7 in Test 1 were compared when no antifoaming agent was added or deaeration kneading was performed, or when both were not performed.
- a defoaming agent 1% by weight of a silicon-based defoaming agent was added to the mixture of the resin and the inorganic substance, and deaeration and kneading were performed under reduced pressure. Table 2 shows the obtained results. Table 2
- Test 1 No. 5 to reduce the rate of in lead oxide and Uorufuramaito to No. 6, was mixed with M g- N i based alloy (M g 2 N i H 4 2) as a hydrogen-absorbing alloy instead test
- M g- N i based alloy M g 2 N i H 4 2
- the materials were evaluated for their density, hydrogen atom density, and shielding performance.
- the Mg-Ni-based hydrogen storage alloy can hold hydrogen up to a high temperature of 300 ° C or more in a normal state.
- the test materials of No. 21 and No. 22 were also deaerated and kneaded, and an antifoaming agent was added. Table 3 shows the obtained results.
- the radiation shielding material according to the present invention has a simultaneous shielding ability of X-rays, neutrons, and neutrons, which is much better than the conventional laminated type concrete, so that the shielding material can be made compact.
- By setting the mixing ratio of the raw materials appropriately it is possible to design an optimal shielding material.
- by selecting the type of thermosetting resin or high-density inorganic substance, the production method, and the like it is possible to produce a shielding material having sufficient mechanical strength and heat resistance for use.
- technologies related to molding of a thermosetting resin as a base material have already been established in various fields, and the present invention can be manufactured by utilizing those technologies and equipment. There are advantages such as being able to provide a cheap and stable shielding material.
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Abstract
Description
明 細 書 Specification
ァ線、 X線及び中性子線の同時遮蔽が可能な放射線遮蔽材 Radiation shielding material capable of simultaneous shielding of X-rays, X-rays and neutrons
[技術分野] [Technical field]
本発明はァ線、 X線及び中性子線を同時に遮蔽する放射線遮蔽材料に関するも のであり、 更に詳しくは放射線施設や、 放射性廃棄物、 核燃料、 ラジオァイソ トープ (R I ) 等の貯蔵、 輸送容器及び関連機器等の放射線遮蔽材料に関する。 TECHNICAL FIELD The present invention relates to a radiation shielding material that simultaneously shields X-rays and neutron rays, and more particularly to a radiation facility, storage of radioactive waste, nuclear fuel, radioisotope (RI), etc., transport containers and related equipment. And other radiation shielding materials.
[背景技術] [Background technology]
放射線の中で Ί線及び X線の遮蔽は、 どのような物質も質量減弱係数に大差は なく、 密度の大きい物質の方が線減弱係数が大きくなり、 遮蔽体の厚みが小さく て済むので、 一般には鉛や鉄、 コンクリートなどが使われている。 Shielding of X-rays and X-rays in radiation does not differ much in the mass attenuation coefficient of any substance, and the higher the density of the substance, the larger the linear attenuation coefficient and the smaller the thickness of the shield. Generally, lead, iron, concrete, etc. are used.
中性子線の遮蔽には主にポリエチレンやパラフィン、 ホウ素を混入したェポキ シ樹脂などの高分子材料や水などの水素を多量に含有する材料が用いられてい る。 またコンクリートも水素を含有しているので、 遮蔽を兼ねた構築材料として 用 ヽられ 。 For shielding neutrons, high-molecular materials such as polyethylene, paraffin, and epoxy resin mixed with boron, and materials containing large amounts of hydrogen such as water are mainly used. Since concrete also contains hydrogen, it is used as a construction material that also serves as a shield.
中性子線の遮蔽には水素が非常に重要であり、 物質中に照射された速中性子 は、 物質中の水素原子との弾性散乱によりエネルギーを失い熱中性子となり、 熱 中性子は水素やその他の元素の原子核により捕獲される。 熱中性子は熱中性子捕 獲断面積の大きな原子核によるほど捕獲され易いが、 この場合二次 Ί線が放出さ れる場合があるので、 中性子線遮蔽にはこの二次 y線の遮蔽も含めて考えなけれ ばならない。 Hydrogen is very important for shielding neutrons.Fast neutrons irradiated into a substance lose their energy due to elastic scattering with hydrogen atoms in the substance and become thermal neutrons.Thermal neutrons are hydrogen and other elements Captured by nuclei. Thermal neutrons are more likely to be captured by nuclei with a larger thermal neutron capture cross section, but in this case secondary Ί rays may be emitted, so neutron beam shielding should include the shielding of this secondary y ray. There must be.
従って、 中性子線の遮蔽、 あるいは中性子線とァ線、 X線を同時に遮蔽する場 合には、 ポリエチレンやパラフィン、 水などの中性子線遮蔽材と、 鉛や鉄などの ァ線遮蔽材を積層させるなど併用しているのが現状であり、 特に中性子線を伴う 放射線施設や廃棄物、 核燃料、 R I等の貯蔵、 輸送容器、 及び関連機器の遮蔽 は、 密度の大きいコンクリート、 鉛又は鉄等で構築、 製造するとともに全く別の 遮蔽材としてポリエチレン、 パラフィン又は水等により遮蔽体を構成するか、 コ ンクリ一ト構造体のみで遮蔽体としている。 Therefore, when shielding neutrons, or simultaneously shielding neutrons, a-rays, and X-rays, stack a neutron-shielding material such as polyethylene, paraffin, or water and an a-ray shielding material such as lead or iron. In particular, radiation facilities involving neutrons, shielding of waste, nuclear fuel, RI, etc., transport containers, and related equipment are constructed of high-density concrete, lead, iron, etc. The shield is made of polyethylene, paraffin, water, etc. as a completely different shield while being manufactured, or the shield is made of only a concrete structure.
コンクリートのみを遮蔽体として用いる場合は、 その遮蔽能力が充分でないた 7 一 2 — め相当の壁厚を必要とし、 施設の使用可能面積が小さくなる等の問題がある。 又 コンクリート構造体は、 その吸水性により放射性汚染水を吸水する恐れが有る 為、 防水塗装を施したりポリマーコンクリートを上塗りしたりしなければなら ず、 非常に高価になる欠点がある。 When only concrete is used as a shield, its shielding ability is not sufficient. There is a problem that a considerable wall thickness is required and the usable area of the facility is reduced. In addition, concrete structures have the disadvantage of being very expensive, because they must absorb radioactive contaminated water due to their water absorption, and must be waterproof-coated or polymer-coated.
またコンクリートや鉄、 鉛等とポリエチレンやパラフィンなどを組み合わせる 場合は、 接着性が悪く施工、 製造が困難である為、 特殊工法を用いなければなら ず問題が多い。 更に両者の熱膨張係数が著しく異なるために、 温度の差により罅 や反り、 脱離等も起こるので、 施工、 製造後の温度管理の面でもかなりの注意を 要する。 またポリエチレンやパラフィンなどは比較的低温で溶融し、 特にバラフ ィンは発火しやすいため耐熱耐火に細心の注意が必要とされ、 結果的に非常に高 価な施設や製品となってしまう。 また中性子線の遮蔽に水を用いる場合は、 液体 であるため使用箇所、 使用方法等が制限されてしまう。 In addition, when concrete, iron, lead, etc. are combined with polyethylene, paraffin, etc., it is difficult to construct and manufacture them due to poor adhesiveness. Furthermore, since the thermal expansion coefficients of the two are significantly different, cracks, warpage, desorption, etc. occur due to the difference in temperature, so considerable care must be taken in terms of construction and temperature control after production. Also, polyethylene and paraffin melt at a relatively low temperature, and varffin in particular tends to ignite, so careful attention must be paid to heat and fire resistance, resulting in extremely expensive facilities and products. When water is used to shield neutrons, the location and method of use are limited because of the liquid.
本発明は、 中性子線と 7線、 X線を同時に遮蔽することにより、 上記欠点とな る二重構造の必要性を無くすとともに、 充分な強度、 優れた成型性、 加工性を有 し、 耐熱性、 疎水性、 耐薬品性に優れた低コストの新しいタイプの放射線遮蔽材 を提供することを目的とする。 The present invention eliminates the need for the above-mentioned drawback of a double structure by simultaneously shielding neutron rays, 7 rays, and X-rays, and has sufficient strength, excellent moldability, workability, and heat resistance. An object of the present invention is to provide a new type of low-cost radiation shielding material having excellent properties, hydrophobicity and chemical resistance.
従来、 放射線遮蔽材は 7線、 X線用と中性子線用とに分けて考えるのが一般的 であった。 ァ線、 X線用遮蔽材には密度の大きい物質が有効であるのに対して、 中性子線用は水素を多量に含んでいる物質の方が効果が大きいため、 概念的に低 密度の物質が有効とされ、 両遮蔽材には互いに矛盾が生じ共用できないと考えら れていた。 Conventionally, radiation shielding materials were generally considered separately for 7 wires, X-rays, and neutrons. A substance with a high density is effective for shielding materials for X-rays and X-rays, whereas a substance containing a large amount of hydrogen is more effective for neutrons, so it is conceptually a low-density substance. Was considered to be effective, and it was thought that the two shielding materials could not be shared because of inconsistency.
さらに高密度無機物質と合成樹脂から成る組成物のの水素含有量 (重量%) は、 その母材となる樹脂単独で得られた成型品のそれよりも著しく減少してしま い、 中性子遮蔽能力もそれに伴い低下するかのように考えられていた。 In addition, the hydrogen content (% by weight) of the composition consisting of high-density inorganic material and synthetic resin is significantly lower than that of the molded product obtained from the resin alone, which is the base material. Was also thought to fall with it.
[発明の開示] [Disclosure of the Invention]
本発明者らは、 中性子線遮蔽において重要なのは単に水素の含有量 (重量%) 等ではなく、 単位体積当たりの水素原子数 (水素原子密度) であることに着目 . し、 水素を多量に含んだ熱硬化性樹脂材料中に高密度無機物質を混入して得られ た組成物の水素原子密度が、 その母材樹脂単独のものに比べて水素含有量 (重量 ) のような著しい低下を示さず、 中性子線遮蔽効果にあたっては、 その母材と なる樹脂単独の場合よりも、 寧ろ優れた性能を持つ場合があるという現象を見 、 出し本発明を完成するに至った。 The present inventors have focused on the fact that what is important in neutron shielding is not simply the hydrogen content (% by weight), but the number of hydrogen atoms per unit volume (hydrogen atom density). The hydrogen atom density of the composition obtained by mixing the high-density inorganic substance in the thermosetting resin material is higher than the hydrogen content (weight ), The neutron shielding effect was not as high as that of the resin alone as the base material. Reached.
本発明によれば、 フユノール樹脂、 エポキシ樹脂、 クレゾ一ル樹脂、 キシレン 樹脂、 ュリァ樹脂及び不飽和ポリエステルから選ばれる少なくとも 1種の熱硬化 性樹脂材料 1 00重量部に Pb, W, C r, C o, C u, F e, Mn, Mo, Ag, T a, C d, Dy, Eu, Gd, Au, I n, H g, Re, Sm, Uまた はこれらの化合物から選ばれる少なくとも 1種の無機物質を 50から 2000重 量部含有し、 成型品の密度が 2. 0以上であることを特徴とするァ線、 X線及び 中性子線の同時遮蔽が可能な放射線遮蔽材が提供される。 According to the present invention, Pb, W, Cr, and Pb are added to 100 parts by weight of at least one kind of thermosetting resin material selected from a fuanol resin, an epoxy resin, a cresol resin, a xylene resin, a urea resin, and an unsaturated polyester. Co, Cu, Fe, Mn, Mo, Ag, Ta, Cd, Dy, Eu, Gd, Au, In, Hg, Re, Sm, U or at least one selected from these compounds A radiation shielding material capable of simultaneously shielding X-rays, X-rays, and neutrons, characterized by containing 50 to 2,000 parts by weight of various inorganic substances and having a molded article density of 2.0 or more is provided. You.
本発明における放射線遮蔽材は、 まず、 水素を多量に含んでおり、 且つ熱に強 い熱硬化性樹脂を用いるのが望ましく、 例えばフユノール樹脂、 エポキシ樹脂、 クレゾール樹脂、 キシレン樹脂、 ユリア樹脂、 不飽和ポリエステル樹脂等を単独 または複数種を混合して用いる。 熱硬化性樹脂は充分な強度、 優れた成形性、 加 ェ性を有し、 比較的耐熱性が犬で、 その選択によっては 150°C以上での使用が 可能である。 本発明に用いられる熱硬化性樹脂の分子量範囲または重合度は特に 限定されない。 It is desirable to use a thermosetting resin which contains a large amount of hydrogen and is strong against heat, for example, the radiation shielding material in the present invention. For example, fuynol resin, epoxy resin, cresol resin, xylene resin, urea resin, non- A saturated polyester resin or the like may be used alone or in combination of two or more. Thermosetting resins have sufficient strength, excellent moldability and addi- bility, and are relatively heat-resistant dogs. Depending on their selection, they can be used at 150 ° C or higher. The molecular weight range or the degree of polymerization of the thermosetting resin used in the present invention is not particularly limited.
また、 無機物質はなるべく密度の大きい物質を用いるほど 7線、 X線遮蔽効果 が向上し、 熱中性子捕獲断面積の大きな元素又は該元素を多く含む物質ほど中性 子線遮蔽に効果があるため、 これらを兼ね備えた高密度な無機物質を用いるか、 組み合わせることによって、 一層優れた放射線遮蔽材の製造が可能である。 本発 明に用いられる高密度な無機物質としては Pb, W, C r, C o, Cu, F e, Mn, Mo, Ag, T a, C d, Dy, Eu, Gd, Au, I n, H g, Re, Sn及び Uの元素単体又はこれらの化合物の群から選ばれる少なくとも 1種を粉 体或いはペレツ ト状態で用いる。 これらの化合物には、 例えば、 鉄鉱石、 ニッケ ノレ鉱、 銅鉱などの鉱物も含まれる。 In addition, the use of a substance with as high a density as possible increases the shielding effect of 7 rays and X-rays, and an element with a large thermal neutron capture cross section or a substance containing a large amount of such elements is more effective in shielding neutron rays. By using or combining a high-density inorganic substance having these properties, it is possible to produce a more excellent radiation shielding material. The high-density inorganic substances used in the present invention include Pb, W, Cr, Co, Cu, Fe, Mn, Mo, Ag, Ta, Cd, Dy, Eu, Gd, Au, In , H g, Re, Sn and U, or at least one element selected from the group consisting of these compounds is used in a powder or pellet state. These compounds also include minerals such as, for example, iron ore, nickel ore, and copper ore.
熱硬化性樹脂に添加する無機物質の量は、 熱硬化性樹脂 100重量部に対し無 機物質 50〜2000重量部の範囲が好ましい。 50重量部未満では、 ァ線およ び X線の遮蔽効果が劣り、 2000重量部以上では、 中性子線の遮蔽効果が低下 するとともに成形品が脆くなり成形品の機械的強度が劣る。 The amount of the inorganic substance added to the thermosetting resin is preferably in the range of 50 to 2000 parts by weight of the inorganic substance per 100 parts by weight of the thermosetting resin. If it is less than 50 parts by weight, the shielding effect of a-rays and X-rays is inferior. In addition, the molded product becomes brittle and the mechanical strength of the molded product is deteriorated.
中性子線、 7線等の各種放射線が共存する環境での遮蔽には、 各種放射線の強 さや特性により、 上記配合割合の範囲内で、 配合割合を適宣設定し、 最も効果的 な遮蔽を行うことができる。 なお、 上記配合物を硬化成形した場合、 成形品の密 度が 2 . 0以上であることが必要である。 この値未満では、 7線、 X線遮蔽能力 が劣り、 同時遮蔽には不適となる。 通常、 コンクリートの密度は 2. 0〜2 . 2 であるので、 コンクリートの遮蔽能力より大きくする必要がある。 For shielding in environments where various radiations such as neutrons and 7 rays coexist, the most effective shielding is performed by appropriately setting the mixing ratio within the above mixing ratio depending on the intensity and characteristics of various radiations. be able to. When the above composition is cured and molded, the density of the molded product must be 2.0 or more. Below this value, the ability to shield 7 rays and X-rays is inferior and unsuitable for simultaneous shielding. Since the density of concrete is usually 2.0 to 2.2, it must be larger than the shielding capacity of concrete.
熱硬化性樹脂溶液に高密度な無機物質の粉体または顆粒を混練する場合の過程 において、 空気の巻き込みや、 樹脂の希釈剤に用いられる揮発性物質等が残留し 組成物中に留まることにより、 充分な密度の成型体が得られない場合がある。 こ の現象を防止するため、 減圧及び真空状態で混練する脱泡混練や、 表面張力を小 さくてし気泡等を材料中から抜け易くする消泡剤を添加することが成型品の密度 向上に有効である。 また、 この操作により、 各放射線の遮蔽性能の向上にも役立 つことが確認された。 本発明に用いられる消泡剤としては、 例えば、 シリコーン 系、 アルコール系のものが挙げられる。 消泡剤の添加量としては、 一般的には全 重量に対して 1重量%以下が好ましい。 In the process of kneading high-density inorganic powders or granules in a thermosetting resin solution, air entrainment or volatile substances used as resin diluents remain in the composition and remain in the composition However, a molded article having a sufficient density may not be obtained. In order to prevent this phenomenon, defoaming kneading under reduced pressure and vacuum, and addition of an antifoaming agent that reduces surface tension and makes it easier for air bubbles to escape from the material will improve the density of molded products. It is valid. It was also confirmed that this operation was useful for improving the shielding performance of each radiation. Examples of the antifoaming agent used in the present invention include silicone-based and alcohol-based defoaming agents. In general, the amount of the defoamer added is preferably 1% by weight or less based on the total weight.
次に、 本発明において、 熱硬化性樹脂に高密度な無機物質とともに、 比較的高 い解離温度を持ち、 高温まで水素を化合保持する水素吸蔵合金を、 添加混入する ことにより、 高密度を保持したまま、 水素原子密度の更なる増加が可能なことが 見い出された。 水素吸蔵合金は、 樹脂等の高分子化合物と同等の水素原子密度を 持ちながら、 高分子化合物よりはかなり密度が高いので、 中性子線及びァ線、 X 線の同時遮蔽に非常に有効である。 Next, in the present invention, a high-density inorganic substance is added to the thermosetting resin, and a hydrogen storage alloy that has a relatively high dissociation temperature and combines and holds hydrogen up to a high temperature is added and mixed to maintain high density. As a result, it was found that the hydrogen atom density could be further increased. Hydrogen storage alloys have a hydrogen atom density equivalent to that of polymer compounds such as resins, but are considerably higher in density than polymer compounds, so they are very effective for simultaneous shielding of neutron rays, α rays, and X-rays.
水素吸蔵合金は水素ガスと反応させることにより、 水素を金属水素化物として 貯蔵できるものであり、 T i系, L a系 (R系) , M g系, C a系等が知られて いるが、 本目的のためには常圧での水素解離温度の高い M g系が最適と考えられ る。 本発明に用いることができる水素吸蔵合金としては、 例えば、 M g H2 など の M g系、 M g.2 N i 2 などの M g— N i系、 M g C u Ho 7 などの M g— C u系, M g C a H3 72などの M g— C a系、 L a 2 M g 17H 17などの L a— M g系などの金属水素化物が挙げられる。 水素吸蔵合金の添加量は製品コス卜お よび放射線遮蔽性能等を考慮して熱硬化性樹脂 100重量部に対して 1〜50重 量部の範囲が好ましい。 Hydrogen storage alloys can store hydrogen as metal hydrides by reacting with hydrogen gas, and Ti, La (R), Mg, and Ca systems are known. However, for this purpose, an Mg system with a high hydrogen dissociation temperature at normal pressure is considered optimal. As the hydrogen storage alloy that can be used in the present invention, for example, M g H 2 M g systems such as, M g. 2 M g- N i system such as N i 2, M, such as M g C u Ho 7 g- C u system, M g C a H 3 72 M g- C a system such as, and metal hydrides such as L a- M g system such as L a 2 M g 17 H 17 . The amount of hydrogen storage alloy added depends on product cost and cost. In consideration of the radiation shielding performance and the like, the range is preferably 1 to 50 parts by weight with respect to 100 parts by weight of the thermosetting resin.
[本発明の好ましい実施例] [Preferred embodiment of the present invention]
次に、 本発明を実施例により具体的に説明するが、 本発明は以下の実施例に限 定されるものではない。 Next, the present invention will be specifically described with reference to examples, but the present invention is not limited to the following examples.
遮蔽性能の試験は、 各放射線の線量当量率を 1 1 0にする各試験材の厚さ (1Z10価層) を求め、 それによつて評価を行なった。 試験には中性子線源と して 2 C fを、 ァ線源として 6GCoを用いた。 In the test of the shielding performance, the thickness (1Z10 valence layer) of each test material for setting the dose equivalent rate of each radiation to 110 was determined, and the evaluation was performed based on the thickness. The 2 C f as a neutron source in the test, was used 6G Co as § ray source.
[試験 1 ] [Test 1]
熱硬化性樹脂として液状のビスフエノール系変性エポキシ樹脂 (大日本ィンキ 化学工業 (株) 製ェピコン R - 130 A、 硬化剤:大日本ィンキ化学工業 (株) 製ェピコン R— 130 BW) 及び液状のフヱノールレジン (群栄化学工業 (株) 製レジトップ PL— 4558、 メタノール溶性) を用い、 それに高密度無機物質 として金属鉛粉、 酸化鉛 (II) (比重: 9. 53) 、 酸化タングステン (VI) を 主成分とする鉱物である、 ゥオルフラマイ ト (Wolframite, 比重:約 7. 16) の粉体、 及び鉄ペレツ ト (比重: 7. 85) を選択し、 それぞれ表 1に示す配合 割合に従って配合し、 脱気混練及び消泡剤添加 (樹脂と、 鉄ペレツトを除く無機 物質の混合物に対し、 シリコン系消泡剤 1重量%、 信越化学工業 (株) 製 KS - 603) を行ない、 成形型に注入し 60 x 60 x 2 cmに硬化成形したものにつ いて、 その密度及び遮蔽性能を測定し、 水素含有量 (重量%) 及び水素原子密度 を求めた。 なお、 比較例としてエポキシ樹脂単独 (試験番号 No. 1) 、 ポリェチ レン (住友べ一クライ ト (株) 製低密度ポリエチレン) 、 コンクリート、 炭素鋼 (S S 41) についても行なった。 得られた結果を表 1に示す。 表 1 成分配合比 (重量部) 7k泰 1 10価層 (cm) 含有量 密度 (X Bisphenol-based modified epoxy resin (epicon R-130A manufactured by Dainippon Ink and Chemicals, Inc., curing agent: Epicon R-130 BW manufactured by Dainippon Ink and Chemicals, Inc.) as a thermosetting resin and liquid Using phenolic resin (Regitop PL-4558, manufactured by Gunei Chemical Industry Co., Ltd., methanol-soluble), and metal lead powder, lead oxide (II) (specific gravity: 9.53), and tungsten oxide (VI) as high-density inorganic substances. Powders of wolframite (specific gravity: about 7.16) and iron pellets (specific gravity: 7.85), which are minerals whose main components are, are selected according to the mixing ratio shown in Table 1. , Deaeration kneading and addition of defoaming agent (1% by weight of silicone defoamer, KS-603, Shin-Etsu Chemical Co., Ltd.) Inject 60 x 60 x 2 cm Molded into One had to those of, measure the density and shielding performance, the hydrogen content (wt%) and was determined a hydrogen atom density. As comparative examples, epoxy resin alone (test number No. 1), polyethylene (low-density polyethylene manufactured by Sumitomo Bey-Kit Co., Ltd.), concrete, and carbon steel (SS41) were also used. Table 1 shows the obtained results. Table 1 Composition ratio (parts by weight) 7k 1 1 10-valent layer (cm) Content Density (X
ェポ フエノ ゥオル Epo fueno zulu
o. 金属 酸化 鉄ペレ (g/cm3) lOVml) 252 Cf 60 - Co キシ 一ルレ フ o. Metal iron oxide pellets (g / cm 3 ) lOVml) 252 Cf 60-Co
鉛粉 J 鉛 ッ 卜 %) 中性子 7線 i fl 5 Lead powder J Lead% neutron 7-line i fl 5
曰 Say
1 100 0 0 0 0 0 1.35 8.04 6.478 15.8 33.0 1 100 0 0 0 0 0 1.35 8.04 6.478 15.8 33.0
2 100 0 50 0 0 0 2.05 5.38 6.547 15.6 22.5 2 100 0 50 0 0 0 2.05 5.38 6.547 15.6 22.5
3 100 0 0 100 0 0 2.23 4.05 5.394 15.4 20.0 3 100 0 0 100 0 0 2.23 4.05 5.394 15.4 20.0
4 100 0 0 0 100 0 2.33 4.05 5.638 15.2 18.2 4 100 0 0 0 100 0 2.33 4.05 5.638 15.2 18.2
5 100 0 0 150 0 0 2.53 3.25 4.917 16.0 17.2 5 100 0 0 150 0 0 2.53 3.25 4.917 16.0 17.2
6 100 0 0 0 150 0 2.74 3.25 5.326 15.8 15.7 6 100 0 0 0 150 0 2.74 3.25 5.326 15.8 15.7
7 Ι ϋϋ U U l ib 1丄 b U 3.13 2.46 4.597 16.1 13.87 Ι ϋϋ U U l ib 1 丄 b U 3.13 2.46 4.597 16.1 13.8
Q 丄 LMJ U U ΔΌΚ) U 3.81 1.66 3.785 16.3 11.8 q oU π U 1 io 1丄 Ο π U 3.10 2.33 4.315 16.3 14.1Q 丄 LMJ U U ΔΌΚ) U 3.81 1.66 3.785 16.3 11.8 q oU π U 1 io 1 丄 Ο π U 3.10 2.33 4.315 16.3 14.1
1 n 100 0 0 115 115 1200 5.64 0.54 1.806 27.3 8.11 n 100 0 0 115 115 1200 5.64 0.54 1.806 27.3 8.1
1 1 100 0 0 200 200 1600 5.89 0.40 1.404 31.5 7.81 1 100 0 0 200 200 1600 5.89 0.40 1.404 31.5 7.8
12 100 0 0 150 150 2000 脆くて試験材の製造不可能。 12 100 0 0 150 150 2000 The test material cannot be manufactured because it is brittle.
13 50 50 0 115 115 1200 5.52 0.50 1.655 28.9 8.3 13 50 50 0 115 115 1200 5.52 0.50 1.655 28.9 8.3
14 50 50 0 150 150 2000 脆くて試験材の製造不可能。 14 50 50 0 150 150 2000 The test material cannot be manufactured because it is brittle.
15 ポリエチレン 0.92 14.40 7.912 13.0 44.5 15 Polyethylene 0.92 14.40 7.912 13.0 44.5
16 コンク リート 2.10 ' 1.10 1.380 31.0 26.0 16 concrete 2.10 '1.10 1.380 31.0 26.0
17 炭素鋼 (SS41) 7.85 38.6 7.2 表 1より、 実施例である No. 2〜No. 9の試験材は比較例である No. 1のェポ キシ樹脂単独の場合と比べて、 同等或いはそれ以上の中性子線遮蔽能力を有して おり、 なお且つその密度の上昇により 7線遮蔽能力も増しており、 7線、 X線遮 蔽能力と中性子線遮蔽能力を高性能に兼ね備え持つことが明かである。 17 Carbon steel (SS41) 7.85 38.6 7.2 Table 1 shows that the test materials of Examples No. 2 to No. 9 have the same or higher neutron shielding ability than the case of the epoxy resin of No. 1 which is the comparative example alone. As the density increases, the 7-ray shielding capacity has also increased, and it is clear that the 7-ray, X-ray shielding ability and the neutron shielding ability have both high performance.
また、 No. 1 0、 No. 1 1、 No. 1 3の実施例は、 比較例である No. 1 6のコ ンクリートと比べて、 同等あるいはそれ以上の中性子線遮蔽能力を有しながらな お且つ、 No. 1 7の炭素鋼 (S S 4 1 ) に迫るほどの優れた y線遮蔽能力を示 し、 これらもまたァ線、 X線遮蔽能力と中性子線遮蔽能力を高性能に兼ね備え持 つことが明かである。 Also, the examples of No. 10, No. 11, and No. 13 have the same or higher neutron shielding capacity than the concrete of No. 16, which is a comparative example. In addition, it shows excellent y-ray shielding ability close to that of No. 17 carbon steel (SS41), which also has high performance in both a-ray, X-ray shielding ability and neutron ray shielding ability. One thing is clear.
このように、 何れの実施例も 7線遮蔽能力と中性子線遮蔽能力を統合的に考慮 した場合、 どの比較例と比べてもその優位性が明らかに認められ、 その配合割合 を変えることで、 ァ線、 X線遮蔽性能と中性子線遮蔽性能を任意に設定でき、 そ の場の状況に合わせたもっとも効果的な遮蔽材を製造することが可能である。 また、 No. 1 2、 No. 1 4の試験材が脆くて製造できなかったことや、 No. 1 1の試験材の中性子線遮蔽性能が、 コンクリートのそれより下回ることより、 熱硬化樹脂 1 0 0重量部に対する高密度無機物質の配合割合が 2 0 0 0重量部を 越えると、 十分な中性子線遮蔽効果が得られず、 また十分な強度を保持した成形 品も得られなくなるのがわかる。 As described above, in all the examples, when the 7-ray shielding ability and the neutron shielding ability were considered in an integrated manner, the superiority was clearly recognized as compared with any of the comparative examples, and by changing the mixing ratio, The X-ray and X-ray shielding performance and neutron shielding performance can be set arbitrarily, and it is possible to manufacture the most effective shielding material according to the situation at that site. In addition, the test materials of No. 12 and No. 14 were brittle and could not be manufactured, and the neutron shielding performance of the test material of No. 11 was lower than that of concrete. When the mixing ratio of the high-density inorganic substance to 200 parts by weight exceeds 2000 parts by weight, it is understood that a sufficient neutron beam shielding effect cannot be obtained and a molded article having sufficient strength cannot be obtained. .
[試験 2 ] [Test 2]
試験 1の No. 7の試験材について消泡剤の添加、 或いは脱気混練のどちらかを 行わない場合、 又はその両方を行わない場合について、 その密度、 遮蔽能力につ いて比較した。 消泡剤は樹脂、 無機物質混合物に対しシリコン系消泡剤を 1重量 %添加し、 脱気混練は減圧により行った。 得られた結果を表 2に示す。 表 2 The density and shielding ability of the test material No. 7 in Test 1 were compared when no antifoaming agent was added or deaeration kneading was performed, or when both were not performed. As a defoaming agent, 1% by weight of a silicon-based defoaming agent was added to the mixture of the resin and the inorganic substance, and deaeration and kneading were performed under reduced pressure. Table 2 shows the obtained results. Table 2
表 2から、 高密度遮蔽材を製造するに当たって、 消泡剤の添加及び脱気混練が 相当な効果があり、 高密度になることは勿論、 それぞれの遮蔽性能にも大きな影 響を与えていることが明かである。 From Table 2, it can be seen that in the production of high-density shielding materials, the addition of an antifoaming agent and deaeration and kneading have considerable effects, and not only increases the density, but also greatly affects the shielding performance of each. It is clear that.
[試験 3 ] [Test 3]
試験 1の No. 5、 No. 6に於ける酸化鉛およびゥオルフラマイトの割合を減ら し、 代わりに水素吸蔵合金として M g— N i系合金 (M g2 N i H4 2 ) を混入 した試験材について、 その密度及び水素原子密度、 遮蔽性能の評価を行なった。 M g - N i系水素吸蔵合金は通常状態で 3 0 0 °C以上の高温まで水素を保持する ことができる。 なお、 No. 2 1、 No. 2 2の試験材も脱気混練及び消泡剤の添加 を行なった。 得られた結果を表 3に示す。 Test 1 No. 5, to reduce the rate of in lead oxide and Uorufuramaito to No. 6, was mixed with M g- N i based alloy (M g 2 N i H 4 2) as a hydrogen-absorbing alloy instead test The materials were evaluated for their density, hydrogen atom density, and shielding performance. The Mg-Ni-based hydrogen storage alloy can hold hydrogen up to a high temperature of 300 ° C or more in a normal state. The test materials of No. 21 and No. 22 were also deaerated and kneaded, and an antifoaming agent was added. Table 3 shows the obtained results.
表 3 成分配合比 (重量部) 密度 水素原子 1 10価層 (cm) ェポキシ ゥオル 密度 (X Table 3 Composition ratio (parts by weight) Density Hydrogen atom 1 Decavalent layer (cm) Epoxy dye Density (X
酸化 水素吸蔵 (g/cm3) 1022/ml) 252 - Cf 60 - Co 樹脂 フ Hydrogen oxide storage (g / cm 3 ) 10 22 / ml) 252-Cf 60-Co resin
No. 鉛 合金 中性子 7線 No. Lead alloy Neutron 7 wire
ラマイ Lamai
5 100 150 0 0 2.53 4.917 16.0 17.2 5 100 150 0 0 2.53 4.917 16.0 17.2
21 100 125 0 25 2.50 5.391 15.7 17.2 21 100 125 0 25 2.50 5.391 15.7 17.2
6 100 0 150 0 2.74 5.326 15.8 15.7 6 100 0 150 0 2.74 5.326 15.8 15.7
22 100 0 125 25 2.69 5.801 15.3 15.7 表 3より、 水素吸蔵合金の混入によって得られた No. 2 1、 No. 2 2は、 水素 吸蔵合金を混入していない No. 5、 No. 6と比較してそれぞれ同等のァ線遮蔽能 力を持ちながら中性子線遮蔽能力が向上しており、 その優位性は明らかである。 22 100 0 125 25 2.69 5.801 15.3 15.7 From Table 3, it can be seen that No. 21 and No. 22 obtained by mixing the hydrogen storage alloy had the same line shielding performance as No. 5 and No. 6 not mixed with the hydrogen storage alloy. The neutron shielding ability has been improved while having power, and its superiority is clear.
[発明の効果] [The invention's effect]
本発明による放射線遮蔽材は 線、 X線及び中性子線の同時遮蔽能力が、 従来 の方法の積層タイプゃコンクリートよりも非常に優れているため遮蔽材のコンパ クト化が図られる。 また原料の配合割合を適宣設定することにより、 最適な遮蔽 材の設計が可能である。 更に、 熱硬化性樹脂や高密度無機物質の種類、 製造方法 等を選択することで、 使用上充分な機械的強度及び耐熱性を持たせた遮蔽材の製 造が可能である。 また母材となる熱硬化性樹脂の成形などに関する技術は、 既に 種々の分野で定着しており、 本発明品はそれらの技術、 設備等を活かして製造す ることが可能であるため、 より安価で安定した遮蔽材の提供が可能であるなどの 利点がある。 The radiation shielding material according to the present invention has a simultaneous shielding ability of X-rays, neutrons, and neutrons, which is much better than the conventional laminated type concrete, so that the shielding material can be made compact. By setting the mixing ratio of the raw materials appropriately, it is possible to design an optimal shielding material. Furthermore, by selecting the type of thermosetting resin or high-density inorganic substance, the production method, and the like, it is possible to produce a shielding material having sufficient mechanical strength and heat resistance for use. In addition, technologies related to molding of a thermosetting resin as a base material have already been established in various fields, and the present invention can be manufactured by utilizing those technologies and equipment. There are advantages such as being able to provide a cheap and stable shielding material.
Claims
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| EP94902107A EP0628968A4 (en) | 1992-12-11 | 1993-12-10 | RADIATION-BARRIER MATERIAL CAPABLE OF SIMULTANEOUS SHIELDING AGAINST -g(g)-RAY, X-RAY AND NEUTRON BEAM. |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4352400A JPH06180389A (en) | 1992-12-11 | 1992-12-11 | Radiation shielding material capable of simultaneous shielding of gamma-ray, x-ray and neutron ray |
| JP4/352400 | 1992-12-11 |
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|---|---|
| WO1994014167A1 true WO1994014167A1 (en) | 1994-06-23 |
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| Application Number | Title | Priority Date | Filing Date |
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| PCT/JP1993/001799 Ceased WO1994014167A1 (en) | 1992-12-11 | 1993-12-10 | RADIATION-BARRIER MATERIAL CAPABLE OF SIMULTANEOUS SHIELDING AGAINST η-RAY, X-RAY AND NEUTRON BEAM |
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|---|---|
| EP (1) | EP0628968A4 (en) |
| JP (1) | JPH06180389A (en) |
| WO (1) | WO1994014167A1 (en) |
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| CN116790012A (en) * | 2022-10-31 | 2023-09-22 | 国家电投集团电站运营技术(北京)有限公司 | Lead-free light gamma-ray protection material and preparation method thereof |
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| RU2133990C1 (en) * | 1998-06-15 | 1999-07-27 | Курносов Владимир Александрович | Safety structure for radioactive materials, method and material for its manufacture |
| JP4592234B2 (en) * | 2001-08-24 | 2010-12-01 | 三菱重工業株式会社 | Neutron shielding material composition, shielding material, container |
| FR2830367B1 (en) | 2001-10-01 | 2003-12-19 | Transnucleaire | NEUTRONIC SHIELDING AND SUB-CRITICITY MAINTAINING MATERIAL BASED ON UNSATURATED POLYESTER |
| JP3951685B2 (en) * | 2001-11-30 | 2007-08-01 | 株式会社日立製作所 | Neutron shielding material and spent fuel container |
| FR2833402B1 (en) | 2001-12-12 | 2004-03-12 | Transnucleaire | NEUTRONIC SHIELDING AND SUB-CRITICITY MAINTAINING MATERIAL BASED ON VINYLESTER RESIN |
| WO2003056569A1 (en) * | 2001-12-26 | 2003-07-10 | Yuri Sergeyevich Alexeyev | Protective container |
| UA64033C2 (en) * | 2002-03-06 | 2004-02-16 | Yurii Sergiiovych Aleksieiev | Composite material for radiation protection and the method for producing the material |
| RU2294030C2 (en) * | 2002-10-02 | 2007-02-20 | Российский федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики - РФЯЦ ВНИИЭФ | X-ray protection composition |
| FR2846467B1 (en) | 2002-10-25 | 2005-01-28 | Cogema Logistics | NEUTRONIC SHIELDING AND DE-CRITICITE MAINTAINING MATERIAL, PREPARATION METHOD AND APPLICATIONS THEREOF |
| CN1321423C (en) * | 2003-03-03 | 2007-06-13 | 三菱重工业株式会社 | Container, composition for neutron shielding body, and manufacturing method of neutron shielding body |
| EP1713089B1 (en) * | 2004-02-04 | 2015-04-08 | Mitsubishi Heavy Industries, Ltd. | Composition for neutron shield material, shield material and container |
| WO2005076288A1 (en) * | 2004-02-04 | 2005-08-18 | Mitsubishi Heavy Industries, Ltd. | Composition for neutron shield material, shield material and container |
| US7632545B2 (en) * | 2005-05-10 | 2009-12-15 | General Electric Company | Radiation shielding composition and a preparation method thereof |
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| KR100833729B1 (en) * | 2006-07-31 | 2008-05-29 | 미츠비시 쥬고교 가부시키가이샤 | Compositions, shields, and containers for neutron shielding materials |
| KR100843807B1 (en) * | 2006-08-01 | 2008-07-03 | 미츠비시 쥬고교 가부시키가이샤 | Compositions, shields, and containers for neutron shielding materials |
| CN101245215B (en) * | 2008-02-02 | 2010-10-13 | 广州秀珀化工股份有限公司 | Radioresistant paint for nuclear power plant and manufacture method thereof |
| DE102008008379A1 (en) * | 2008-02-09 | 2009-08-20 | Engelmann, Hans-Jürgen, Dr. | Shielding material for shielding radiation |
| JP5740078B2 (en) * | 2009-03-06 | 2015-06-24 | 株式会社東芝 | X-ray tube device |
| JP5582715B2 (en) * | 2009-04-08 | 2014-09-03 | 株式会社東芝 | Rotating anode type X-ray tube device |
| JP2014055854A (en) * | 2012-09-12 | 2014-03-27 | High Energy Accelerator Research Organization | Neutron absorber and neutron exposure preventing structure |
| JP6313684B2 (en) * | 2014-08-01 | 2018-04-18 | 三光医理化株式会社 | Radiation shielding resin composition, radiation shielding resin material, and radiation shielding resin molding |
| KR20180081209A (en) * | 2017-01-06 | 2018-07-16 | 내일테크놀로지 주식회사 | Manufacturing method for 3-D printable radiation shielding body, manufacturing apparatus for radiation shielding body and radiation shielding body |
| JP7447037B2 (en) * | 2021-03-05 | 2024-03-11 | 東芝エネルギーシステムズ株式会社 | Method for manufacturing luminescent radiation shielding body and resinous shielding part |
| CN115874072A (en) * | 2021-09-29 | 2023-03-31 | 中核北方核燃料元件有限公司 | Preparation method of ray shielding material of electron irradiation accelerator |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59163597A (en) * | 1983-03-08 | 1984-09-14 | 日本電気株式会社 | Neutron ray shielding material |
| JPS63293498A (en) * | 1987-05-27 | 1988-11-30 | Mitsubishi Cable Ind Ltd | X-ray shielding block for medical purpose |
| JPH01253696A (en) * | 1988-04-01 | 1989-10-09 | Ask Corp | Shielding material for thermal neutron |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS55132237A (en) * | 1979-04-02 | 1980-10-14 | Yoshio Asanuma | Frp laminated molding structure which shield and control radiation |
| US4619963A (en) * | 1983-02-24 | 1986-10-28 | Toray Industries, Inc. | Radiation shielding composite sheet material |
| GB8827531D0 (en) * | 1988-11-25 | 1988-12-29 | Du Pont Canada | Highly filled compositions |
-
1992
- 1992-12-11 JP JP4352400A patent/JPH06180389A/en active Pending
-
1993
- 1993-12-10 WO PCT/JP1993/001799 patent/WO1994014167A1/en not_active Ceased
- 1993-12-10 EP EP94902107A patent/EP0628968A4/en not_active Withdrawn
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59163597A (en) * | 1983-03-08 | 1984-09-14 | 日本電気株式会社 | Neutron ray shielding material |
| JPS63293498A (en) * | 1987-05-27 | 1988-11-30 | Mitsubishi Cable Ind Ltd | X-ray shielding block for medical purpose |
| JPH01253696A (en) * | 1988-04-01 | 1989-10-09 | Ask Corp | Shielding material for thermal neutron |
Non-Patent Citations (1)
| Title |
|---|
| See also references of EP0628968A4 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116790012A (en) * | 2022-10-31 | 2023-09-22 | 国家电投集团电站运营技术(北京)有限公司 | Lead-free light gamma-ray protection material and preparation method thereof |
Also Published As
| Publication number | Publication date |
|---|---|
| EP0628968A4 (en) | 1995-04-26 |
| JPH06180389A (en) | 1994-06-28 |
| EP0628968A1 (en) | 1994-12-14 |
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