JPH0249680B2 - - Google Patents
Info
- Publication number
- JPH0249680B2 JPH0249680B2 JP58142403A JP14240383A JPH0249680B2 JP H0249680 B2 JPH0249680 B2 JP H0249680B2 JP 58142403 A JP58142403 A JP 58142403A JP 14240383 A JP14240383 A JP 14240383A JP H0249680 B2 JPH0249680 B2 JP H0249680B2
- Authority
- JP
- Japan
- Prior art keywords
- concrete
- sulfur
- container
- radioactive waste
- sulfur concrete
- 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 - Lifetime
Links
- 239000004567 concrete Substances 0.000 claims description 45
- 229910052717 sulfur Inorganic materials 0.000 claims description 41
- 239000011593 sulfur Substances 0.000 claims description 41
- NINIDFKCEFEMDL-UHFFFAOYSA-N Sulfur Chemical compound [S] NINIDFKCEFEMDL-UHFFFAOYSA-N 0.000 claims description 37
- 239000002893 slag Substances 0.000 claims description 16
- 238000009628 steelmaking Methods 0.000 claims description 15
- 229910000831 Steel Inorganic materials 0.000 claims description 13
- 239000010959 steel Substances 0.000 claims description 13
- 239000000428 dust Substances 0.000 claims description 12
- 239000002901 radioactive waste Substances 0.000 claims description 12
- 239000011257 shell material Substances 0.000 claims description 11
- 239000002131 composite material Substances 0.000 claims description 10
- 229910052751 metal Inorganic materials 0.000 claims description 8
- 239000002184 metal Substances 0.000 claims description 8
- 239000000203 mixture Substances 0.000 claims description 8
- 238000010438 heat treatment Methods 0.000 claims description 5
- 238000001816 cooling Methods 0.000 claims description 3
- 230000005855 radiation Effects 0.000 description 12
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 10
- 238000002834 transmittance Methods 0.000 description 8
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N iron oxide Inorganic materials [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 7
- 230000005484 gravity Effects 0.000 description 6
- 238000003860 storage Methods 0.000 description 6
- 229910052742 iron Inorganic materials 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 238000004519 manufacturing process Methods 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- 150000003463 sulfur Chemical class 0.000 description 4
- 229910004298 SiO 2 Inorganic materials 0.000 description 3
- 239000006227 byproduct Substances 0.000 description 3
- 235000013980 iron oxide Nutrition 0.000 description 3
- 230000007774 longterm Effects 0.000 description 3
- 238000012360 testing method Methods 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- GWEVSGVZZGPLCZ-UHFFFAOYSA-N Titan oxide Chemical compound O=[Ti]=O GWEVSGVZZGPLCZ-UHFFFAOYSA-N 0.000 description 2
- 239000004568 cement Substances 0.000 description 2
- 238000005336 cracking Methods 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 239000007769 metal material Substances 0.000 description 2
- 239000004570 mortar (masonry) Substances 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- 239000002994 raw material Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000011282 treatment Methods 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- ATJFFYVFTNAWJD-UHFFFAOYSA-N Tin Chemical compound [Sn] ATJFFYVFTNAWJD-UHFFFAOYSA-N 0.000 description 1
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 1
- HCHKCACWOHOZIP-UHFFFAOYSA-N Zinc Chemical compound [Zn] HCHKCACWOHOZIP-UHFFFAOYSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 239000001273 butane Substances 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 239000000571 coke Substances 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 229910052593 corundum Inorganic materials 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006477 desulfuration reaction Methods 0.000 description 1
- 230000023556 desulfurization Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010828 elution Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- VBMVTYDPPZVILR-UHFFFAOYSA-N iron(2+);oxygen(2-) Chemical class [O-2].[Fe+2] VBMVTYDPPZVILR-UHFFFAOYSA-N 0.000 description 1
- 238000004898 kneading Methods 0.000 description 1
- 239000011133 lead Substances 0.000 description 1
- 239000002925 low-level radioactive waste Substances 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- IJDNQMDRQITEOD-UHFFFAOYSA-N n-butane Chemical compound CCCC IJDNQMDRQITEOD-UHFFFAOYSA-N 0.000 description 1
- OFBQJSOFQDEBGM-UHFFFAOYSA-N n-pentane Natural products CCCCC OFBQJSOFQDEBGM-UHFFFAOYSA-N 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 238000010998 test method Methods 0.000 description 1
- 229910052718 tin Inorganic materials 0.000 description 1
- 239000011135 tin Substances 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
- 229910001845 yogo sapphire Inorganic materials 0.000 description 1
- 229910052725 zinc Inorganic materials 0.000 description 1
- 239000011701 zinc Substances 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/36—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing sulfur, sulfides or selenium
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00767—Uses not provided for elsewhere in C04B2111/00 for waste stabilisation purposes
- C04B2111/00775—Uses not provided for elsewhere in C04B2111/00 for waste stabilisation purposes the composition being used as waste barriers or the like, e.g. compositions used for waste disposal purposes only, but not containing the waste itself
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00862—Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
- C04B2111/26—Corrosion of reinforcement resistance
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
- C04B2111/28—Fire resistance, i.e. materials resistant to accidental fires or high temperatures
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
- Y02W30/91—Use of waste materials as fillers for mortars or concrete
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Ceramic Engineering (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Inorganic Chemistry (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
Description
本発明は、原子力発電所、医療施設などから出
る放射性廃棄物の運搬、貯蔵容器に関する。
原子力発電所の運転に伴つて排出される低レベ
ル放射性廃棄物は増加の一途をたどり、その処理
は急務の課題である。その処理方法としては焼
却、固形化、保管廃棄、海洋投棄があるがこのよ
うな処理において金属容器はコストが高くそのま
ま廃棄する場合に用いるには適当ではない。また
従来のコンクリート容器では器壁の厚みを大きく
とらなければ十分な遮蔽効果が得られず、いきお
い容器が大型にならざるを得ないという欠点があ
つた。またコンクリートは密度の経年変化が大で
遮蔽能力が低下するばかりか、長期保管中にヒビ
割れを生じる恐れが大きいことが重大な難点であ
つた。
本発明者らはこのような従来の放射性廃棄物容
器の欠点を克服するため鋭意研究を重ねた結果、
製鋼ダスト、鉄鋼スラグ及び硫黄を混融加熱後冷
却固化して形成した固化材を金属板等の殻材で被
覆したものが放射性廃棄物容器の材料として上記
目的を満たすことを見出し、この知見に基づき本
発明を完成するに至つた。
すなわち本発明は、器壁を、製鋼ダスト、鉄鋼
スラグ及び硫黄の配合物を混融加熱後冷却固化し
てなる硫黄コンクリート（以下単に硫黄コンクリ
ートと言う）とその表面に被覆した殻材とからな
る合成パネルで形成することを特徴とする放射性
廃棄物容器を提供するものである。
本発明を図示の１実施例に従つて詳細に説明す
ると、第１図ａは本発明の放射性廃棄物容器の縦
断面図、第２図ｂは第１図ａのＡ−Ａ線横断面図
である。図中１は容器本体であり、２は蓋、３は
放射性廃棄物収容部、４は硫黄コンクリート製の
容器の器壁、５は硫黄コンクリート製器壁の外表
面を覆う殻材の金属板である。６，７は吊り上げ
用フツクであり、不使用時は器壁中に収めてお
く。
第２図は第１図の殻材の金属板に代えてコンク
リート板８を用いた例の縦断面図であり第１図と
同符号は同じものを示す。
本発明において容器本体の形状は特に制限はな
く、第１図のように横断面の形状が６角形の多角
形のほか、第２図のような円形、方形などのよう
な形をとつてもよい。また容器は球状でもよい。
また殻材の金属板は亜鉛、アルミニウム、クロ
ム、スズ、チタン、鉄、銅、鉛、ニツケル、ステ
ンレススチールなどの金属材料からなる板であ
り、コンクリート板としては軽量コンクリート、
PSコンクリートなど普通コンクリートが好まし
く用いられる。殻材は通常、容器の少なくとも外
表面に設ければよいが、第１図に示すように廃棄
物収容部の内面にまで形成してもよい。なお、該
内面に鉛板を採用すればさらに遮蔽能力を高める
ことができる。
なお蓋の容器本体との取付方式には特に制限は
ない。
本発明において用いる硫黄コンクリートは前記
のように原料の製鋼ダスト、製鋼スラグ及び硫黄
を溶融固化して製造できる。その詳細は次の通り
である。
製鋼ダスト（ガス灰）は平炉工場、電炉工場な
どで製鋼過程で、集塵器に捕集されるもので、例
えば平炉ダスト（平炉ガス灰）は酸化鉄約68〜89
％、転炉ダスト（転炉ガス灰）は酸化鉄約84〜89
％含有している。その大部分が0.5〜1.0ミクロン
の微細な粉状物である。
次に鉄鋼スラグとは、高炉スラグ、製鋼スラグ
などの製鉄副生スラグを指称する。化学組成は、
高炉スラグでは、鉄鋼石の品質により変わるが主
成分の組成範囲は重量％でSiO230〜40％、
CaO35〜50％、Al2O35〜20％、MgO5〜10％、
FeO3％未満、MnO3％未満となつている。また
製鋼スラグは平炉、転炉における製鋼過程で生じ
る平炉スラグ、転炉スラグである。
この硫黄コンクリートにおいて上記の製鋼ダス
ト及び製鋼スラグを骨材とする主な理由は、鉄
（酸化鉄）及び重金属含有量が大であるので比重
が大きく、硫黄との結合力が大であるので溶融混
練処理により、放射線遮蔽能力が高く長期安定性
にすぐれた材料を与えるからである。しかもこれ
らが製鋼工程の副生物であり低コストであるとい
う利点を有する。
硫黄コンクリートに用いる硫黄は必ずしも高純
度のものである必要はなく、コークス製造、製
鉄、石油精製工場などの脱硫工程から副生する硫
黄でもよい。
硫黄コンクリートの組成は通常、製鋼ダストと
鉄鋼スラグと硫黄を１〜３重量部：３〜６重量
部：２〜３重量部の割合である。この場合製鋼ダ
ストが３重量部を越えると比重が大きくなるが、
強度、粘性が低下する。また充填密度が低いた
め、遮蔽力が悪くなる。一方、１重量部未満では
粘性が良くなるが比重が小さくなつてしまう。
鉄鋼スラグは６重量部を越えると粘性が低減し
圧縮強度もでなくなり、３重量部未未満では比重
が小さくなり、遮蔽力が悪くなる。また硫黄の量
が３重量部を越えると圧縮強度が低下し、２重量
部未満では骨材とのなじみが不足し、十分な粘性
のものが得られなくなる。
硫黄コンクリートは上記原料を通常95〜130℃
で混融物の粘性が十分に発現するまで加熱して製
造できる。
この硫黄コンクリートはあらかじめ容器の形に
成形して用いてもよく、また殻材を容器の形に形
成しこれに上記溶融物を流しこんでもよい。
この硫黄コンクリートは比重3.410〜3.650で遮
蔽材料としてコンクリートの中で、最も遮蔽能力
の高いとされるPSコンクリートよりもさらにす
ぐれた放射線遮蔽能力を示す。この硫黄コンクリ
ートは圧縮強度が500Kg／cm2以上で耐久性、粘性
にすぐれヒビ割れしにくい構造材料である。また
硫黄の特性として耐薬品性もすぐれ、耐酸化性で
ある。
次に本発明容器に用いる器壁の性能を示す。な
おここで使用した硫黄コンクリートの仕様は次の
通りである。
組成：硫黄（純度約70％）９重量部、電気炉ダス
ト（組成；SiO25.32％、CaO5.5％、
A12O31.59、Fe2O331％、ZnO11％、MgO3.9
％）４重量部、転炉スラグ（組成；SiO233.4
％、CaO41％、A12O314.5％、Fe2O34.0％、
MgO6.0％、S1.0％、MnO0.7％、TiO21.5
％）17重量部
比重：3.595
圧縮強度：650Kg／cm2
(a) 硫黄コンクリートの放射線遮蔽能力
第３図はCo−60を線源とした硫黄コンクリー
トのγ線の透過率を鉛ブロツク、PSコンクリー
トと比較して示すグラフである。試験方法は国際
放射線測定委員会（ICRU）の測定法に準じる。
測定条件は次の通り。
１ コバルト60：２分間照射
２ 吸収体−線源距離：50cm
３ 吸収体−線量計距離：50cm
４ 照射野：10cm×10cm
５ 線量計：IONEX TYPE2500／３ S.
No.1416Probe：0.6mm１ S.No.4060
同図より、硫黄コンクリートがコンクリートの
中で遮蔽能力の良いとされるPSコンクリートよ
りもはるかに低い透過率を示すことがわかる。
第４図に上記の線源Co−60に代えてより低エ
ネルギーの線源Ｉ−131、Tc−99ｍを用いて透過
率を測定したグラフを示す。
(b) 合成パネルの放射線遮蔽能力
第５図に本発明で用いる合成パネルの放射線遮
蔽能力のグラフを示す。上記硫黄コンクリート板
（厚さ193.6mm）の表裏面を厚さ3.2mmの鉄板で覆
つた合成パネル（全体厚さ200mm）にCo−60を15
分間照射した以外は第３図の場合と同様にして測
定した透過率を点Ａで示す。横軸は鉛の厚さ当量
を示す。また点Ｂは上記鉄板２枚だけの場合の透
過率であり、点Ｃは厚さ50mmの硫黄コンクリート
の表面を厚さ50mmの普通コンクリート（モルタル
セメント）で被覆した合成パネル（厚さ150mm）
の透過率である。
(c) 合成パネルの断熱、難燃性
第６図の縦断面図に示すように硫黄コンクリ
ート９の表面をモルタルセメント１０で被覆し
た供試パネルを作成した（硫黄コンクリート厚
さ90mm、普通コンクリート被覆厚さ各27.5mm）。
供試合成パネルに第６図の縦断面図に示すよう
に穴１１，１２，１３（後面からの深さ80mm）
を設け、前面170mmからトーチ（ブタンス）の
火焔で加熱して内部温度を測定した。結果を次
表に示す。なおテスト中、硫黄の溶出及びガス
の発生は全くみられなかつた。
The present invention relates to containers for transporting and storing radioactive waste from nuclear power plants, medical facilities, and the like. The amount of low-level radioactive waste discharged from the operation of nuclear power plants continues to increase, and its disposal is an urgent issue. Treatment methods include incineration, solidification, storage and disposal, and ocean dumping, but metal containers are expensive in these treatments and are not suitable for use when disposed of as is. In addition, conventional concrete containers had the disadvantage that sufficient shielding effects could not be obtained unless the walls of the container were made thicker, and the container had to be larger. Concrete also has a serious problem in that its density changes significantly over time, which not only reduces its shielding ability, but also increases the risk of cracking during long-term storage. The inventors of the present invention have conducted extensive research to overcome the drawbacks of conventional radioactive waste containers, and have found that:
We discovered that a solidified material formed by mixing and heating steelmaking dust, steel slag, and sulfur, then cooling and solidifying it and covering it with a shell material such as a metal plate satisfies the above purpose as a material for radioactive waste containers. Based on this, the present invention has been completed. That is, in the present invention, the vessel wall is made of sulfur concrete (hereinafter simply referred to as sulfur concrete) made by mixing and heating a mixture of steelmaking dust, steel slag, and sulfur and solidifying it by cooling, and a shell material covering the surface of the sulfur concrete. A radioactive waste container is provided, characterized in that it is formed from a synthetic panel. The present invention will be described in detail according to an illustrated embodiment. FIG. 1a is a longitudinal cross-sectional view of a radioactive waste container of the present invention, and FIG. 2b is a cross-sectional view taken along the line A--A in FIG. 1a. It is. In the figure, 1 is the container body, 2 is the lid, 3 is the radioactive waste storage area, 4 is the container wall made of sulfur concrete, and 5 is the metal plate of the shell material covering the outer surface of the sulfur concrete container wall. be. Numerals 6 and 7 are lifting hooks, which are stored inside the vessel wall when not in use. FIG. 2 is a longitudinal sectional view of an example in which a concrete plate 8 is used in place of the metal plate of the shell material in FIG. 1, and the same reference numerals as in FIG. 1 indicate the same parts. In the present invention, the shape of the container body is not particularly limited, and may be a polygon with a hexagonal cross section as shown in Figure 1, or a circular or rectangular shape as shown in Figure 2. good. The container may also be spherical. Metal plates for shell materials are plates made of metal materials such as zinc, aluminum, chromium, tin, titanium, iron, copper, lead, nickel, and stainless steel, and concrete plates include lightweight concrete,
Ordinary concrete such as PS concrete is preferably used. The shell material is usually provided on at least the outer surface of the container, but may also be formed on the inner surface of the waste container as shown in FIG. Note that if a lead plate is used for the inner surface, the shielding ability can be further enhanced. Note that there are no particular restrictions on the method of attaching the lid to the container body. The sulfur concrete used in the present invention can be produced by melting and solidifying the raw materials steelmaking dust, steelmaking slag, and sulfur as described above. The details are as follows. Steelmaking dust (gas ash) is collected in dust collectors during the steelmaking process at open hearth factories, electric furnace factories, etc. For example, open hearth dust (open hearth gas ash) contains approximately 68 to 89 iron oxides.
%, converter dust (converter gas ash) is iron oxide approximately 84-89
Contains %. Most of it is fine powder of 0.5 to 1.0 microns. Next, iron and steel slag refers to iron-making byproduct slag such as blast furnace slag and steel-making slag. The chemical composition is
In blast furnace slag, the composition range of the main components is SiO 2 30-40% by weight, although it varies depending on the quality of the steel ore.
CaO35~50%, Al2O3 5~20%, MgO5 ~ 10%,
FeO is less than 3% and MnO is less than 3%. Further, steelmaking slag is open hearth slag and converter slag produced during the steelmaking process in open hearth and converter furnaces. The main reasons for using the above-mentioned steelmaking dust and steelmaking slag as aggregates in this sulfur concrete are that they contain a large amount of iron (iron oxide) and heavy metals, so they have a high specific gravity, and their binding strength with sulfur is high, so they cannot be melted. This is because the kneading process provides a material with high radiation shielding ability and excellent long-term stability. Moreover, they are by-products of the steelmaking process and have the advantage of being low cost. The sulfur used in sulfur concrete does not necessarily have to be of high purity, and may be sulfur produced as a by-product from desulfurization processes in coke manufacturing, iron manufacturing, oil refineries, etc. The composition of sulfur concrete is usually steelmaking dust, steel slag, and sulfur in a ratio of 1 to 3 parts by weight: 3 to 6 parts by weight: 2 to 3 parts by weight. In this case, if the steelmaking dust exceeds 3 parts by weight, the specific gravity will increase;
Strength and viscosity decrease. Furthermore, since the packing density is low, the shielding power is poor. On the other hand, if it is less than 1 part by weight, the viscosity will be improved but the specific gravity will be decreased. If the amount of steel slag exceeds 6 parts by weight, the viscosity will decrease and the compressive strength will be lost, and if it is less than 3 parts by weight, the specific gravity will become small and the shielding power will deteriorate. Moreover, if the amount of sulfur exceeds 3 parts by weight, the compressive strength will decrease, and if it is less than 2 parts by weight, the compatibility with the aggregate will be insufficient and a product with sufficient viscosity will not be obtained. For sulfur concrete, the above raw materials are usually heated at 95 to 130℃.
It can be produced by heating the mixed melt until the viscosity is sufficiently developed. This sulfur concrete may be used by being formed into the shape of a container in advance, or the shell material may be formed into the shape of a container and the above-mentioned melt may be poured into it. This sulfur concrete has a specific gravity of 3.410 to 3.650 and exhibits a radiation shielding ability that is even better than PS concrete, which is said to have the highest shielding ability among concrete as a shielding material. This sulfur concrete has a compressive strength of over 500 kg/cm 2 and is a structural material with excellent durability and viscosity, and is resistant to cracking. Sulfur also has excellent chemical resistance and oxidation resistance. Next, the performance of the container wall used in the container of the present invention will be shown. The specifications of the sulfur concrete used here are as follows. Composition: 9 parts by weight of sulfur (approx. 70% purity), electric furnace dust (composition: SiO 2 5.32%, CaO 5.5%,
A1 2 O 3 1.59, Fe 2 O 3 31%, ZnO 11%, MgO3.9
%) 4 parts by weight, converter slag (composition; SiO 2 33.4
%, CaO41%, A1 2 O 3 14.5%, Fe 2 O 3 4.0%,
MgO6.0%, S1.0%, MnO0.7%, TiO2 1.5
%) 17 parts by weight Specific gravity: 3.595 Compressive strength: 650Kg/cm 2 (a) Radiation shielding ability of sulfur concrete Figure 3 shows the gamma ray transmittance of sulfur concrete using Co-60 as a radiation source, compared to lead blocks and PS concrete. This is a graph showing a comparison. The test method follows the measurement method of the International Commission on Radiation Measurements (ICRU).
The measurement conditions are as follows. 1 Cobalt 60: 2 minute irradiation 2 Absorber-source distance: 50cm 3 Absorber-dosimeter distance: 50cm 4 Irradiation field: 10cm x 10cm 5 Dosimeter: IONEX TYPE2500/3 S.
No.1416Probe: 0.6mm1 S.No.4060 From the same figure, it can be seen that sulfur concrete exhibits a much lower transmittance than PS concrete, which is said to have a good shielding ability among concrete. FIG. 4 shows a graph of transmittance measured using lower energy radiation sources I-131 and Tc-99m in place of the Co-60 radiation source. (b) Radiation shielding ability of the composite panel FIG. 5 shows a graph of the radiation shielding ability of the composite panel used in the present invention. 15 Co-60 was applied to a composite panel (total thickness 200 mm) made by covering the front and back sides of the above sulfur concrete plate (193.6 mm thick) with 3.2 mm thick steel plates.
Point A indicates the transmittance measured in the same manner as in FIG. 3 except that the irradiation was performed for a minute. The horizontal axis shows the thickness equivalent of lead. Also, point B is the transmittance when there are only the two steel plates mentioned above, and point C is a composite panel (150 mm thick) in which the surface of 50 mm thick sulfur concrete is covered with 50 mm thick ordinary concrete (mortar cement).
The transmittance is (c) Heat insulation and flame retardance of composite panels As shown in the longitudinal cross-sectional view of Figure 6, a test panel was prepared in which the surface of sulfur concrete 9 was covered with mortar cement 10 (sulfur concrete thickness 90 mm, ordinary concrete covered). 27.5mm thick each).
Holes 11, 12, and 13 (depth 80 mm from the rear surface) are made in the sample composite panel as shown in the longitudinal cross-sectional view of Figure 6.
was installed, and the internal temperature was measured by heating it with a flame from a torch (butane) from 170 mm in front. The results are shown in the table below. During the test, no sulfur elution or gas generation was observed.
【表】
また上記(b)で試験した同じ規格及びサイズ
の、硫黄コンクリートを鉄板で被覆した合成パ
ネルを上記のトーチで距離130mmから10分間直
火で加熱したところ加熱面の中心は105℃であ
つたが側面の角から約50mmの点は表面温度は35
℃である。
硫黄コンクリート板（厚さ50mm）上記と同様
のトーチで150mmの距離から火焔を照射すると
表面は１分以内で130℃に昇温し燃焼する。一
方、表面を厚さ3.2mmの鉄板で被覆し同様の条
件で火焔を照射すると２分間で鉄板は93℃に昇
温するが裏面の硫黄コンクリートは43℃に昇温
する。
以上詳述した本発明の放射性廃棄物容器は次の
ようなすぐれた特徴を有する。
(1) 合成パネルからなり、従来のコンクリート製
容器より器壁を薄くして放射線遮蔽能力のすぐ
れた小型の容器とすることができる。
(2) 断熱性、難燃性がすぐれる。
(3) 合成パネルは製鉄等における排出物を有効利
用して原料とするので鉛等の金属性材料のみか
らなるものよりはるかに製造コストが低廉で、
耐腐食性のすぐれ、特に長期にわたる陸上保
管、海洋投棄用の容器として好適である。
(4) 容器は機械的強度がすぐれ、保管中にヒビ割
れ等による放射性物質の漏洩を起す恐れがな
く、信頼性が高い。
(5) 硫黄コンクリートは金属製の殻材に対しも不
活性であり、その酸化を防止する。[Table] In addition, when a composite panel made of sulfur concrete covered with a steel plate of the same standard and size tested in (b) above was heated with the above torch over an open flame from a distance of 130mm for 10 minutes, the center of the heated surface was 105℃. The surface temperature of the point about 50mm from the corner of the side is 35
It is ℃. When a sulfur concrete plate (thickness 50mm) is irradiated with flame from a distance of 150mm using the same torch as above, the surface heats up to 130℃ within 1 minute and burns. On the other hand, if the surface is covered with a 3.2mm thick steel plate and exposed to flame under the same conditions, the temperature of the steel plate will rise to 93℃ in 2 minutes, but the temperature of the sulfur concrete on the back will rise to 43℃. The radioactive waste container of the present invention described in detail above has the following excellent features. (1) It is made of synthetic panels and has thinner walls than conventional concrete containers, making it possible to create a small container with excellent radiation shielding ability. (2) Excellent heat insulation and flame retardancy. (3) Because synthetic panels effectively utilize waste products from steel manufacturing, etc., their production costs are much lower than those made only from metallic materials such as lead.
It has excellent corrosion resistance and is particularly suitable for long-term storage on land or as a container for ocean dumping. (4) The container has excellent mechanical strength and is highly reliable as there is no risk of radioactive material leaking due to cracks during storage. (5) Sulfur concrete is also inert to metal shell materials and prevents their oxidation.
第１図は本発明の放射性廃棄物容器の１実施例
の断面図であり、第２図は他例の縦断面図であ
る。第３図及び第４図は硫黄コンクリートの放射
線透過率を示すグラフ、第５図は合成パネルの放
射線透過率を示すグラフであり、第６図は供試合
成パネルの縦断面図である。
符号の説明、１……容器本体、２……蓋、３…
…放射製廃棄物収容部、４……硫黄コンクリート
製器壁、５……金属板。
FIG. 1 is a sectional view of one embodiment of the radioactive waste container of the present invention, and FIG. 2 is a longitudinal sectional view of another embodiment. 3 and 4 are graphs showing the radiation transmittance of sulfur concrete, FIG. 5 is a graph showing the radiation transmittance of the composite panel, and FIG. 6 is a longitudinal cross-sectional view of the composite panel under test. Explanation of symbols, 1... Container body, 2... Lid, 3...
...Radioactive waste storage area, 4...Sulfur concrete equipment wall, 5...Metal plate.
Claims (1)
配合物を混融加熱後冷却固化してなる硫黄コンク
リートとその表面に被覆した殻材とからなる合成
パネルで形成することを特徴とする放射性廃棄物
容器。 ２ 殻材が金属板である特許請求の範囲第１項記
載の放射性廃棄物容器。 ３ 殻材が普通コンクリートである特許請求の範
囲第１項記載の放射性廃棄物容器。[Scope of Claims] 1. The vessel wall is formed of a composite panel made of sulfur concrete made by mixing and heating a mixture of steelmaking dust, steel slag, and sulfur and then cooling and solidifying it, and a shell material coated on the surface of the sulfur concrete. A radioactive waste container featuring: 2. The radioactive waste container according to claim 1, wherein the shell material is a metal plate. 3. The radioactive waste container according to claim 1, wherein the shell material is ordinary concrete.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58142403A JPS6035298A (en) | 1983-08-05 | 1983-08-05 | Radioactive waste vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58142403A JPS6035298A (en) | 1983-08-05 | 1983-08-05 | Radioactive waste vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6035298A JPS6035298A (en) | 1985-02-23 |
| JPH0249680B2 true JPH0249680B2 (en) | 1990-10-30 |
Family
ID=15314529
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58142403A Granted JPS6035298A (en) | 1983-08-05 | 1983-08-05 | Radioactive waste vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6035298A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0744226A1 (en) * | 1995-05-26 | 1996-11-27 | Ikari-Laboratory For Environmental Science Co., Ltd. | Method for manufacturing molded materials solidified by sulfur and apparatus used in the method |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61245095A (en) * | 1985-04-23 | 1986-10-31 | 電気化学工業株式会社 | Waste treating vessel |
| JPH01280299A (en) * | 1988-05-02 | 1989-11-10 | Shimizu Corp | Neutron shielding concrete material |
| US6083431A (en) | 1995-05-26 | 2000-07-04 | Ikari-Laboratory For Environmental Science Co., Ltd. | Method for solidifying and sealing in a toxic substance with sulfur |
| JP3453529B2 (en) * | 1997-12-03 | 2003-10-06 | 岩水開発株式会社 | Shielding material and its construction method |
| JP2013076659A (en) * | 2011-09-30 | 2013-04-25 | Hokukon Co Ltd | Hermetic storage container of radioactive waste |
| EP2807131B1 (en) * | 2012-01-27 | 2021-03-03 | Saudi Arabian Oil Company | Sulfur steel-slag aggregate concrete |
| JP5904053B2 (en) * | 2012-08-15 | 2016-04-13 | Ｊｆｅスチール株式会社 | Radiation shielding structure and embankment |
| JP5205540B1 (en) * | 2012-09-20 | 2013-06-05 | 株式会社カワハラ技研 | Radioactive contaminant storage container |
| JP2014102088A (en) * | 2012-11-16 | 2014-06-05 | Keiko Kato | Stone container for radioactive waste |
| JP6296276B2 (en) * | 2013-08-09 | 2018-03-20 | 清水建設株式会社 | Radioactive waste disposal facility |
| JP6487158B2 (en) * | 2014-07-11 | 2019-03-20 | 初一 松本 | Radioactive contaminated seabed treatment method |
| JP6422348B2 (en) * | 2015-01-09 | 2018-11-14 | 有限会社豊栄産業 | Radiation shielding concrete composition and radioactive material storage container formed of radiation shielding concrete composition |
-
1983
- 1983-08-05 JP JP58142403A patent/JPS6035298A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0744226A1 (en) * | 1995-05-26 | 1996-11-27 | Ikari-Laboratory For Environmental Science Co., Ltd. | Method for manufacturing molded materials solidified by sulfur and apparatus used in the method |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6035298A (en) | 1985-02-23 |
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