JPH0458595B2 - - Google Patents
Info
- Publication number
- JPH0458595B2 JPH0458595B2 JP4559084A JP4559084A JPH0458595B2 JP H0458595 B2 JPH0458595 B2 JP H0458595B2 JP 4559084 A JP4559084 A JP 4559084A JP 4559084 A JP4559084 A JP 4559084A JP H0458595 B2 JPH0458595 B2 JP H0458595B2
- Authority
- JP
- Japan
- Prior art keywords
- powder
- radiation shielding
- shielding material
- material according
- plating
- 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.)
- Expired
Links
- 239000000843 powder Substances 0.000 claims description 33
- 230000005855 radiation Effects 0.000 claims description 31
- 238000007747 plating Methods 0.000 claims description 21
- 239000000463 material Substances 0.000 claims description 20
- 239000010802 sludge Substances 0.000 claims description 18
- 229910000464 lead oxide Inorganic materials 0.000 claims description 16
- YEXPOXQUZXUXJW-UHFFFAOYSA-N oxolead Chemical compound [Pb]=O YEXPOXQUZXUXJW-UHFFFAOYSA-N 0.000 claims description 16
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 14
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 11
- 229910052750 molybdenum Inorganic materials 0.000 claims description 11
- 239000011733 molybdenum Substances 0.000 claims description 11
- 229920005989 resin Polymers 0.000 claims description 10
- 239000011347 resin Substances 0.000 claims description 10
- 239000000203 mixture Substances 0.000 claims description 9
- WGLPBDUCMAPZCE-UHFFFAOYSA-N Trioxochromium Chemical compound O=[Cr](=O)=O WGLPBDUCMAPZCE-UHFFFAOYSA-N 0.000 claims description 8
- 229910052782 aluminium Inorganic materials 0.000 claims description 8
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 8
- 239000011230 binding agent Substances 0.000 claims description 8
- 229910000423 chromium oxide Inorganic materials 0.000 claims description 8
- 239000011162 core material Substances 0.000 claims description 7
- 229910052759 nickel Inorganic materials 0.000 claims description 7
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 6
- 239000012784 inorganic fiber Substances 0.000 claims description 6
- 229910000480 nickel oxide Inorganic materials 0.000 claims description 5
- TWNQGVIAIRXVLR-UHFFFAOYSA-N oxo(oxoalumanyloxy)alumane Chemical compound O=[Al]O[Al]=O TWNQGVIAIRXVLR-UHFFFAOYSA-N 0.000 claims description 5
- GNRSAWUEBMWBQH-UHFFFAOYSA-N oxonickel Chemical compound [Ni]=O GNRSAWUEBMWBQH-UHFFFAOYSA-N 0.000 claims description 5
- 239000002245 particle Substances 0.000 claims description 4
- 229910052804 chromium Inorganic materials 0.000 claims description 3
- 239000011651 chromium Substances 0.000 claims description 3
- 239000004744 fabric Substances 0.000 claims description 3
- 239000003365 glass fiber Substances 0.000 claims description 3
- 229910052751 metal Inorganic materials 0.000 claims description 3
- 239000002184 metal Substances 0.000 claims description 3
- 238000005245 sintering Methods 0.000 claims description 3
- 239000004640 Melamine resin Substances 0.000 claims description 2
- 229920000877 Melamine resin Polymers 0.000 claims description 2
- 239000003513 alkali Substances 0.000 claims description 2
- 239000003822 epoxy resin Substances 0.000 claims description 2
- 229920000647 polyepoxide Polymers 0.000 claims description 2
- 239000002354 radioactive wastewater Substances 0.000 claims description 2
- 229920001187 thermosetting polymer Polymers 0.000 claims description 2
- 239000002912 waste gas Substances 0.000 claims 1
- 238000010521 absorption reaction Methods 0.000 description 8
- 230000000694 effects Effects 0.000 description 6
- 239000006227 byproduct Substances 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- 239000002440 industrial waste Substances 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000007670 refining Methods 0.000 description 2
- 239000002893 slag Substances 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- YCKRFDGAMUMZLT-UHFFFAOYSA-N Fluorine atom Chemical compound [F] YCKRFDGAMUMZLT-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000003915 air pollution Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 239000011737 fluorine Substances 0.000 description 1
- 229910052731 fluorine Inorganic materials 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000000227 grinding Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical group C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000009628 steelmaking Methods 0.000 description 1
Landscapes
- Materials For Medical Uses (AREA)
- Compositions Of Macromolecular Compounds (AREA)
Description
本発明は、放射線吸収崩壊特性を有する酸化
鉛・酸化クロム系放射線遮蔽材に関する。
医療および工業分野、たとえば放射線関係研究
所、原子力発電所および原子力船等において、取
扱者、作業員、研究者機能障害を与えないように
するため、放射線取扱室の天井、壁、とくに原子
力発電所の冷却水循環系、放射能廃棄物の貯蔵容
器等を、鉛板または鉛シヨツトを含むコンクリー
ト構造体で囲んで遮蔽することは既に周知であ
る。
しかし、かかる鉛系遮蔽材は良好な放射線吸収
能を有するが、なお吸収されない放射線を後方に
散乱させる難点がある。これを別としても鉛板等
は高価であり、その加工方法に手間がかかるし、
一般に鉛系遮蔽板は、鉛の比重が高いため遮蔽材
が極めて高重量となり、施工または運搬に著しく
不利なものであつた。
このような欠点を排除する目的で、酸化鉛粉末
を主体とし、モリブデン鉱石粉末およびアルミニ
ウムまたはニツケルの電気精錬もしくは電気製鋼
法からの鉱滓粉末を含有する組成を有し、バイン
ダ樹脂の存在で無機繊維芯材の間挿下にプレス成
形し、焼結してなる放射線遮蔽板は既に提案され
ている（特願昭58−57955号（特公昭64−6433
号））。
ところで、この提案されたものにおいて、アル
ミニウムまたはニツケルの電気精錬もしくは電気
製鋼法からの鉱滓粉末に代えてアルミめつきおよ
びクロムめつきまたはニツケルめつきからの酸化
アルミニウム汚泥および酸化クロムまたは酸化ニ
ツケル汚泥の粉末を使用すれば、放射線、殊に高
レベル放射線、たとえばγ線に対する吸収崩壊に
よる遮蔽効果が著しく増加することが判明した。
本発明による放射線遮蔽材は、酸化鉛粉末およ
びクロムめつきからの酸化クロム汚泥粉末を主体
とし、アルミニウムめつきからの酸化アルミニウ
ム汚泥粉末およびモリブデン鉱石粉末を含有する
組成を有し、バインダ樹脂の存在で無機繊維芯材
の間挿下にプレス成形し、焼結したものである。
本発明による放射線遮蔽材は、付加的にニツケ
ルめつきからの酸化ニツケル汚泥粉末を含有する
ことができ、これにより不変の放射線の吸収崩壊
作用において酸化鉛合量の減少が達成される。
本発明により使用されるモリブデン鉱石粉末、
酸化鉛粉末および金属めつきからの汚泥粉末は、
有利に300〜900メツシユの粒度を有する。
本発明により使用されるバインダ樹脂は、メラ
ミン樹脂またはエポキシ樹脂のような熱硬化性樹
脂である。無機繊維芯材としてはカーボン繊維芯
材等を使用することもできるが、アルカリガラス
繊維布が有利である。
プレス成形体の焼結は、成形体の硬度を増加さ
せるために温度180〜200℃で行なわれる。
本発明で使用される酸化鉛は、化学的に純粋な
ものである必要はなく、バツテリーからの廃物酸
化鉛または他の工業的副産物であつてもよい。
本発明で使用されるアルミニウムめつきからの
汚泥粉末は、たとえば下記の組成を有する：
The present invention relates to a lead oxide/chromium oxide radiation shielding material having radiation absorption and decay properties. In the medical and industrial fields, such as radiation-related laboratories, nuclear power plants, and nuclear ships, the ceilings and walls of radiation handling rooms, especially nuclear power plants, must be It is already known to surround and shield cooling water circulation systems, storage containers for radioactive waste, etc. with concrete structures containing lead plates or lead shots. However, although such lead-based shielding materials have good radiation absorption ability, they still have the disadvantage of scattering unabsorbed radiation back. Apart from this, lead plates etc. are expensive, and the processing method is time-consuming.
In general, lead-based shielding plates have a high specific gravity of lead, making the shielding material extremely heavy, which is extremely disadvantageous in construction and transportation. In order to eliminate such drawbacks, the composition is based on lead oxide powder, containing molybdenum ore powder and slag powder from aluminum or nickel electro-refining or electro-steel manufacturing, and in the presence of a binder resin, inorganic fibers are produced. A radiation shielding plate formed by press-forming and sintering a core material has already been proposed (Japanese Patent Application No. 58-57955 (Japanese Patent Application No. 64-6433).
issue)). By the way, in this proposal, aluminum oxide sludge and chromium oxide or nickel oxide sludge from aluminum plating and chrome plating or nickel plating are used instead of slag powder from aluminum or nickel electrorefining or electric steelmaking. It has been found that the use of powders significantly increases the shielding effect against radiation, especially high-level radiation, such as gamma rays, by absorption decay. The radiation shielding material according to the present invention has a composition mainly consisting of lead oxide powder and chromium oxide sludge powder from chromium plating, aluminum oxide sludge powder from aluminum plating and molybdenum ore powder, and the presence of a binder resin. It is press-formed with an inorganic fiber core interposed therein and sintered. The radiation shielding material according to the invention can additionally contain nickel oxide sludge powder from nickel plating, so that a reduction in the amount of lead oxide is achieved with a constant radiation absorption and decay effect. Molybdenum ore powder used according to the invention,
Sludge powder from lead oxide powder and metal plating is
It preferably has a particle size of 300 to 900 mesh. The binder resin used according to the invention is a thermosetting resin such as a melamine resin or an epoxy resin. As the inorganic fiber core material, a carbon fiber core material or the like may be used, but an alkali glass fiber cloth is advantageous. Sintering of the press-formed body is carried out at a temperature of 180 to 200°C in order to increase the hardness of the press-formed body. The lead oxide used in the present invention need not be chemically pure and may be waste lead oxide from batteries or other industrial by-products. The sludge powder from aluminum plating used in the invention has, for example, the following composition:
【表】
クロムめつきからの汚泥粉末としては酸化クロ
ムめつき（）70〜90％を含有し、ニツケルめつ
きからの汚泥粉末としては酸化ニツケルめつき80
〜93％を含有するものを使用する。
本発明で使用されるモリブデン鉱石末中のモリ
ブデン分は、放射線遮蔽効果とともに、原子炉か
ら発生するフツ素を結合固定する作用をも有する
ものと考えられる。
本発明による放射線遮蔽材は次のようにして製
造される。
酸化鉛粉末（主としてバツテリーからの廃物酸
化鉛、東日本非鉄金属精錬加工組合から入手）25
〜35重量部、モリブデン鉱石（新潟県中浦原群村
松町内鉱山または米国コロラド州クライマツクス
鉱山産輝水鉛鉱）をクラツシヤーで酸化鉛と同程
度の粒度（300〜900メツシユ）に粉砕したもの５
〜７重量部、酸化鉛と同程度の粒度を有するアル
ミニウムめつきからの酸化アルミニウム汚泥粉末
９〜25重量部、クロムめつきからの酸化クロム汚
泥粉末30から40重量部、必要に応じニツケルめつ
きからの酸化ニツケル汚泥粉末５〜９重量部を混
合した後、バインダ樹脂（大日本インキ株式会社
製品、ペースト状）４重量部を混入し、混合物を
といし製造用プレスに入れ、製品に撓み性および
強度を与えるため市販のガラス繊維布（直径約１
mm、幅約３〜４mm９を適宜挿入しプレス圧150か
ら200気圧で所望の厚さの板にプレス成形し、こ
うして得た成形品を硬度を高めるためオーブン中
で温度180〜200℃で２〜５時間熱処理して焼結す
る。熱処理時間はバインダ樹脂による。
実施例
本発明の実施例による放射線遮蔽材は次表に示
す組成を有する。[Table] Sludge powder from chrome plating contains 70 to 90% of chromium oxide plating (), and sludge powder from nickel plating contains 80% nickel oxide plating.
Use one containing ~93%. The molybdenum content in the molybdenum ore powder used in the present invention is thought to have a radiation shielding effect as well as a function of binding and fixing fluorine generated from a nuclear reactor. The radiation shielding material according to the present invention is manufactured as follows. Lead oxide powder (mainly lead oxide waste from batteries, obtained from the East Japan Nonferrous Metal Refining and Processing Association) 25
~35 parts by weight, molybdenum ore (molybdenum ore from Matsucho Mine in Nakaurahara Gunmura, Niigata Prefecture or molybdenum ore from Climacus Mine in Colorado, U.S.A.) crushed to the same particle size as lead oxide (300 to 900 mesh) using a crusher5
~7 parts by weight, 9 to 25 parts by weight of aluminum oxide sludge powder from aluminum plating with particle size similar to lead oxide, 30 to 40 parts by weight of chromium oxide sludge powder from chrome plating, nickel plating if necessary After mixing 5 to 9 parts by weight of nickel oxide sludge powder, 4 parts by weight of binder resin (product of Dainippon Ink Co., Ltd., paste form) is mixed, and the mixture is put into a grinding press to give the product flexibility. and commercially available glass fiber cloth (approximately 1 inch in diameter) to provide strength.
mm, width approximately 3 to 4 mm9, and press-formed into a plate of desired thickness at a press pressure of 150 to 200 atm.The molded product thus obtained was placed in an oven at a temperature of 180 to 200°C for 2 to 20 minutes to increase hardness. It is heat treated for 5 hours and sintered. The heat treatment time depends on the binder resin. Examples Radiation shielding materials according to examples of the present invention have compositions shown in the following table.
【表】【table】
【表】
上記の組成を有する放射線遮蔽板の放射線吸収
崩壊による遮蔽効果を調べるため、厚さ10mmおよ
び30mmの焼結板からそれぞれ100mm×50mmの被検
体を載断し、被検体による高レベル放射線の吸収
崩壊による減衰率を測定した。この場合放射線源
としては鉛コリメータに内蔵された口径７mmの
60Coガンマ線発生器を使用し、それに向かい合つ
て配置され、同じく鉛コリメータに内蔵された口
径3.8cm、長さ2.54cm（１1/2インチ×１インチ）
のNaI（Tl）光電子増倍管（Du Pont6292）を検
出器として使用した。第２表はその結果を示す。[Table] In order to investigate the shielding effect due to radiation absorption and decay of the radiation shielding plate having the above composition, a test object of 100 mm x 50 mm was cut from a sintered board with a thickness of 10 mm and 30 mm. The attenuation rate due to absorption decay was measured. In this case, the radiation source is a 7 mm caliber built into the lead collimator.
Using a 60 Co gamma ray generator, placed opposite it and also housed in a lead collimator, the diameter is 3.8 cm and the length is 2.54 cm (1 1/2 inches x 1 inch).
A NaI (Tl) photomultiplier tube (Du Pont6292) was used as a detector. Table 2 shows the results.
【表】
このような本発明による酸化鉛・酸化クロム系
遮蔽材の示す放射線の吸収崩壊による遮蔽効果
は、この目的に常用の鉛板（厚さ3.0mm）を用い
てえられる遮蔽効果よりも著しく高く、されに提
案された酸化鉛系遮蔽板のほぼ３倍に達する。
本発明による放射線遮蔽材は、上述したように
すぐれた放射線吸収崩壊作用を示すので、板状で
室の天井、容器壁構成体として有用であるのみな
らず、環境汚染の防止のため有利に使用すること
もできる。たとえば原子力発電所の原子炉から出
る放射能を帯びた廃水を処理するため、排水溝中
に球状体として順次に成槽配置することもできる
し、原子炉から大気に通じる排気路、たとえば煙
突中にフイルタの形で配置して放射能による大気
汚染を有効に防止することもできる。
本発明による放射線遮蔽材は、その構成成分な
いしは原料が鉱石または工業上の副産物ないしは
産業廃棄物であるため、製造コストが著しく低廉
であるとともに、従来その処置が大きな課題であ
つた副産物ないしは産業廃棄物の有効な利用法を
開拓した点にかんがみ本発明は工業上多大の貢献
をするものである。[Table] The shielding effect of the lead oxide/chromium oxide shielding material according to the present invention due to absorption and decay of radiation is greater than the shielding effect obtained by using a regular lead plate (thickness 3.0 mm) for this purpose. It is extremely high, almost three times as high as the previously proposed lead oxide-based shielding plate. Since the radiation shielding material according to the present invention exhibits excellent radiation absorption and decay properties as described above, it is not only useful in the form of a plate as a ceiling of a room or a wall structure of a container, but also can be advantageously used to prevent environmental pollution. You can also. For example, to treat radioactive wastewater discharged from the reactor of a nuclear power plant, tanks can be placed one after another in the form of spherical bodies in a drainage ditch, or in an exhaust passage leading from the reactor to the atmosphere, such as in a chimney. It can also be placed in the form of a filter to effectively prevent air pollution caused by radioactivity. Since the radiation shielding material according to the present invention uses ores or industrial by-products or industrial waste as its constituent components or raw materials, the manufacturing cost is extremely low, and the by-product or industrial waste, which has conventionally been a major problem to dispose of, is In view of the fact that it has pioneered an effective method of using materials, the present invention makes a great contribution to industry.
Claims (1)
ロム汚泥粉末を主体とし、アルミニウムめつきか
らの酸化アルミニウム汚泥粉末およびモリブデン
鉱石粉末を含有する組成を有し、バインダ樹脂の
存在で無機繊維芯材の間挿下にプレス成形し、焼
結したことを特徴とする放射線遮蔽材。 ２ 酸化鉛粉末およびクロムめつきからの酸化ク
ロム汚泥粉末を主体とし、アルミニウムめつきか
らの酸化アルミニウム汚泥粉末、ニツケルめつき
からの酸化ニツケル汚泥粉末およびモリブデン鉱
石粉末を含有する組成を有し、バインダ樹脂の存
在で無機繊維芯材の間挿下にプレス成形し、焼結
したことを特徴とする放射線遮蔽材。 ３ 酸化鉛粉末、金属めつきからの汚泥粉末およ
びモリブデン鉱石粉末が300〜900メツシユの粒度
を有する、特許請求の範囲第１項記載の放射線遮
蔽材。 ４ バインダ樹脂がメラミン樹脂またはエポキシ
樹脂のような熱硬化性樹脂である、特許請求の範
囲第１項記載の放射線遮蔽材。 ５ 無機繊維芯材がアルカリガラス繊維布であ
る、特許請求の範囲第１項記載の放射線遮蔽材。 ６ 焼結を温度180〜200℃で行なう、特許請求の
範囲第１項記載の放射線遮蔽材。 ７ 板状で天井または容器壁構成体として使用さ
れる、特許請求の範囲第１項記載の放射線遮蔽
材。 ８ 球状で原子炉からの放射能を帯びた廃水の排
水溝中に順次に成層配置される、特許請求の範囲
第１項記載の放射線遮蔽材。 ９ フイルタの形で原子炉から大気への廃ガスの
排気路中に配置される、特許請求の範囲第１項記
載の放射線遮蔽材。[Scope of Claims] 1 The composition is mainly composed of lead oxide powder and chromium oxide sludge powder from chromium plating, and contains aluminum oxide sludge powder from aluminum plating and molybdenum ore powder, and has a composition in which a binder resin is present. A radiation shielding material characterized by being press-molded and sintered with an intercalated inorganic fiber core material. 2 It has a composition mainly consisting of lead oxide powder and chromium oxide sludge powder from chromium plating, aluminum oxide sludge powder from aluminum plating, nickel oxide sludge powder from nickel plating, and molybdenum ore powder, and a binder. A radiation shielding material characterized by being press-molded and sintered under an inorganic fiber core material in the presence of a resin. 3. The radiation shielding material according to claim 1, wherein the lead oxide powder, sludge powder from metal plating and molybdenum ore powder have a particle size of 300 to 900 mesh. 4. The radiation shielding material according to claim 1, wherein the binder resin is a thermosetting resin such as melamine resin or epoxy resin. 5. The radiation shielding material according to claim 1, wherein the inorganic fiber core material is an alkali glass fiber cloth. 6. The radiation shielding material according to claim 1, wherein the sintering is performed at a temperature of 180 to 200°C. 7. The radiation shielding material according to claim 1, which is plate-shaped and used as a ceiling or container wall structure. 8. The radiation shielding material according to claim 1, which has a spherical shape and is sequentially arranged in layers in a drainage ditch of radioactive wastewater from a nuclear reactor. 9. Radiation shielding material according to claim 1, which is arranged in the form of a filter in the exhaust path of waste gas from the nuclear reactor to the atmosphere.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4559084A JPS60190898A (en) | 1984-03-12 | 1984-03-12 | Radiation shielding material |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4559084A JPS60190898A (en) | 1984-03-12 | 1984-03-12 | Radiation shielding material |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60190898A JPS60190898A (en) | 1985-09-28 |
| JPH0458595B2 true JPH0458595B2 (en) | 1992-09-17 |
Family
ID=12723561
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4559084A Granted JPS60190898A (en) | 1984-03-12 | 1984-03-12 | Radiation shielding material |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60190898A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7632545B2 (en) * | 2005-05-10 | 2009-12-15 | General Electric Company | Radiation shielding composition and a preparation method thereof |
| JP5740078B2 (en) * | 2009-03-06 | 2015-06-24 | 株式会社東芝 | X-ray tube device |
| JP6395175B2 (en) | 2012-02-23 | 2018-09-26 | 凸版印刷株式会社 | Radiation shielding sheet paper and manufacturing method thereof |
-
1984
- 1984-03-12 JP JP4559084A patent/JPS60190898A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60190898A (en) | 1985-09-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US2796411A (en) | Radiation shield | |
| US4587277A (en) | Radiation shield | |
| JPH10226533A (en) | Radiation shielding glass | |
| JPH06180389A (en) | Radiation shielding material capable of simultaneous shielding of gamma-ray, x-ray and neutron ray | |
| CA2742613A1 (en) | Matrix material of graphite and inorganic binders suitable for ultimate disposal of radioactive wastes, method for producing the same, processing the same and use thereof | |
| KR102128822B1 (en) | Concrete composition for shielding radiation and hardened concrete thereof | |
| EP4211080A1 (en) | High dense red mud shields for x- and gamma -ray attenuation | |
| Tashlykov et al. | An extensive experimental study on the role of micro-size pozzolana in enhancing the gamma-ray shielding properties of high-density polyethylene | |
| US4753756A (en) | Radiation shielding material | |
| CN103000242A (en) | High-performance radiation-shielding concrete | |
| JPH0458595B2 (en) | ||
| Ali et al. | Radiation shielding properties of sustainable concrete with novel plastering techniques | |
| US20230154637A1 (en) | Radiation shield unit, method of manufacturing radiation shield unit, and radiation shield structure | |
| US20020165082A1 (en) | Radiation shielding phosphate bonded ceramics using enriched isotopic boron compounds | |
| Paul et al. | A review on radiation shielding materials based on low-strength chemical wastes and nanomaterials | |
| JP2520978B2 (en) | Radiation shield | |
| DE3821684C2 (en) | ||
| US3645916A (en) | Metallic mortars | |
| US3827982A (en) | Moldable lead composition | |
| Labador et al. | Radiation Attenuation Properties of Concrete Blended with Rice Husk Ash, Oyster Shell Powder, and Ferrous Powder. | |
| Camilleri et al. | Utilization of pulverized fuel ash in Malta | |
| Evcin et al. | Use of ilmenite and boron waste as a radiation shielding panel | |
| EP2240940A1 (en) | Material for shielding from radiation | |
| Elamin et al. | The effect of replacements 30% for each concrete component by iron filling in concrete on attenuation properties | |
| Akgül et al. | Effect of Increasing Weight of SiC Ceramic on Radiation Shielding of Al 2219 |