JP3164131B2 - Aggregate used in radioactive waste treatment structures - Google Patents
Aggregate used in radioactive waste treatment structuresInfo
- Publication number
- JP3164131B2 JP3164131B2 JP08289093A JP8289093A JP3164131B2 JP 3164131 B2 JP3164131 B2 JP 3164131B2 JP 08289093 A JP08289093 A JP 08289093A JP 8289093 A JP8289093 A JP 8289093A JP 3164131 B2 JP3164131 B2 JP 3164131B2
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- aggregate
- cement
- waste treatment
- cement clinker
- 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 - Fee Related
Links
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
- C04B7/00—Hydraulic cements
- C04B7/006—Cement-clinker used in the unground state in mortar - or concrete compositions
-
- 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
- C04B2103/00—Function or property of ingredients for mortars, concrete or artificial stone
- C04B2103/0068—Ingredients with a function or property not provided for elsewhere in C04B2103/00
- C04B2103/0094—Agents for altering or buffering the pH; Ingredients characterised by their pH
-
- 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
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Ceramic Engineering (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Processing Of Solid Wastes (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本発明は、放射性廃棄物の処理構
造物（例えば、充填材、固型化材、構築物など）に用い
られる骨材に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an aggregate used for a structure for treating radioactive waste (eg, a filler, a solidified material, a building, etc.).
【０００２】[0002]
【発明の背景】我が国における原子力平和利用は三十有
余年を経過し、今日では世界的にも注目されている。そ
して、原子力平和利用の一つとして原子力発電が有り、
今日では原子力発電が安定的な電力供給源として大きな
役割を発揮している。そして、各種の原子力施設からは
放射性廃棄物が生まれており、この放射性廃棄物の処理
は、ドラム缶などの処理容器内にセメント系固型化材と
放射性廃棄物とを入れてを混練固化したり、ドラム缶な
どの処理容器内に放射性廃棄物を入れ、その隙間にセメ
ント系固型化材を充填して固化させ、そして蓋をした
後、コンクリート等で構築された施設に移送し、施設内
に配置した後、これらの固化体の周囲をセメントモルタ
ルやコンクリート等の充填材で安定化処理し、保管され
る。BACKGROUND OF THE INVENTION Peaceful use of nuclear energy in Japan has been in use for more than thirty years, and is now receiving worldwide attention. And there is nuclear power as one of the peaceful uses of nuclear power,
Today, nuclear power plays an important role as a stable power supply. Various types of nuclear facilities produce radioactive waste, and this radioactive waste is treated by mixing and solidifying cement-based solidified material and radioactive waste in a processing container such as a drum. Put the radioactive waste in a processing container such as a drum can, fill the gap with a cement-based solidification material and solidify it.After closing the lid, transfer it to a facility constructed of concrete, etc. After the arrangement, the periphery of these solidified bodies is stabilized with a filler such as cement mortar or concrete and stored.
【０００３】ところで、放射性廃棄物の中にはＮｐ，Ｐ
ｕ，Ａｍのような半減期の長いＴＲＵ核種もあり、従っ
て放射性廃棄物が入れられた処理固化体の無害化を図る
為には、数百年後に固化体や構築物が崩壊した後でも数
百万年程度は半減期の長いＴＲＵ核種が生活環境下に移
行し難い環境をつくっておく必要が有る。By the way, some radioactive wastes include Np, P
Some TRU nuclides with a long half-life, such as u and Am, are used. Therefore, in order to detoxify the treated solid containing radioactive waste, several hundred years later, even after the solidified product or the structure has collapsed, it may be several hundreds. It is necessary to create an environment in which TRU nuclides with a long half-life of about ten thousand years are unlikely to migrate to the living environment.
【０００４】[0004]
【発明の開示】本発明の目的は、放射性廃棄物を長期間
にわたって安全に処理できる技術を提供することであ
る。上記本発明の目的は、放射性廃棄物の処理構造物に
用いられる骨材であって、この骨材がセメントクリンカ
で構成されてなることを特徴とする放射性廃棄物の処理
構造物に用いられる骨材によって達成される。DISCLOSURE OF THE INVENTION An object of the present invention is to provide a technique capable of safely treating radioactive waste for a long period of time. An object of the present invention is to provide an aggregate for use in a radioactive waste treatment structure, wherein the aggregate is constituted by a cement clinker. Achieved by the material.
【０００５】本発明における放射性廃棄物の処理構造物
とは、放射性廃棄物の処理に用いられるセメントモルタ
ル体やコンクリート体であり、例えば放射性廃棄物の処
理容器内あるいは容器の周囲に充填されるセメントモル
タルであったり、放射性廃棄物の処理施設のコンクリー
ト構築物であったりし、放射性廃棄物が処理され、長期
間にわたって放射性廃棄物が保管・処分などされる場所
に用いられ、骨材やセメントを用いて構成されるもので
あればよい。[0005] The radioactive waste treatment structure in the present invention is a cement mortar or concrete body used for radioactive waste treatment, for example, a cement filled in or around a radioactive waste treatment container. Used in places where mortar is used, where radioactive waste is treated, and where radioactive waste is stored and disposed of over a long period of time, such as concrete structures in radioactive waste treatment facilities. What is necessary is just what is comprised.
【０００６】そして、骨材には細骨材と粗骨材とがあ
り、細骨材のみがセメントクリンカで構成されていても
良く、又、粗骨材のみがセメントクリンカで構成されて
いても良く、そして細骨材及び粗骨材いずれの骨材もセ
メントクリンカで構成されていても良い。ここで、細骨
材とは約５ｍｍ以下の大きさを有するものであり、そし
て粗骨材とは約５ｍｍ以上の大きさを有するものである
が、この定義から多少外れていても、それが骨材として
の機能を発揮しているものであれば良い。[0006] The aggregate includes fine aggregate and coarse aggregate, and only the fine aggregate may be composed of cement clinker, or only the coarse aggregate may be composed of cement clinker. Good, and both fine and coarse aggregates may be comprised of cement clinkers. Here, the fine aggregate has a size of about 5 mm or less, and the coarse aggregate has a size of about 5 mm or more. Any material that functions as an aggregate may be used.
【０００７】以下、本発明を詳細に説明する。放射性廃
棄物処理体の保管施設がコンクリートで構築されていて
も、保管期間が数百年にもわたることを考慮すると、コ
ンクリートの風化が考慮されなければならない。そし
て、安全性を考慮したならば、風化が始まった後でも、
閉じ込められている放射性廃棄物、特に半減期の長い放
射性核種が施設内から移行し難いように、又、仮に、施
設が崩壊した後でも半減期の長い放射性核種が移行し難
いように設計されてなければならない。Hereinafter, the present invention will be described in detail. Even if the storage facility for radioactive waste disposal is made of concrete, weathering of the concrete must be taken into account in view of the storage period of several hundred years. And, considering safety, even after weathering has begun,
It is designed so that trapped radioactive waste, especially radionuclides with a long half-life, are unlikely to migrate out of the facility, and even if the facility collapses, radionuclides with a long half-life are difficult to migrate. There must be.
【０００８】ところで、放射性廃棄物処理体の保管の長
期安全性の確保にはｐＨが大事な因子であることが判っ
て来た。例えば、ｐＨが約１０以上（好ましくは１２以
上）といったような高ｐＨの状態では、金属製の構成要
素の腐食が遅くなり、従って施設を構成する鉄筋コンク
リート構築物の損傷がそれだけ遅くなり、耐久性に富む
から、保管の長期安全性が増すと考えられる。かつ、放
射性核種、特に長寿命の放射性核種の水溶液への溶解度
が低くなり、放射性廃棄物の処理容器や施設が数百年後
において風化するようなことが起きたとしても、放射性
核種、特に長寿命の放射性核種が地下水中に滲み出、拡
散してしまうことが効果的に防止されると考えられる。
又、微生物の活動も抑えられることから、放射性廃棄物
処理・処分施設等の長期安定性がそれだけ増すと考えら
れる。Meanwhile, it has been found that pH is an important factor for ensuring long-term safety of storage of a radioactive waste disposal body. For example, in high pH conditions, such as a pH of about 10 or more (preferably 12 or more), the corrosion of metal components is slowed, and thus the damage to the reinforced concrete structures that make up the facility is slowed down and the durability is reduced. It is thought that long-term safety of storage will increase because of the richness. Moreover, even if radionuclides, especially long-lived radionuclides, become less soluble in aqueous solutions and weathering of radioactive waste treatment containers and facilities will occur hundreds of years later, radionuclides, especially It is thought that long-lived radionuclides are effectively prevented from seeping and diffusing into groundwater.
In addition, since the activity of microorganisms is also suppressed, it is considered that the long-term stability of radioactive waste treatment / disposal facilities and the like increases accordingly.
【０００９】従って、放射性廃棄物処理施設や処理体が
高ｐＨな素材で構成されることが強く望まれる。ところ
で、放射性廃棄物の処理にこれまで用いられて来たセメ
ントは、３ＣａＯ・ＳｉＯ2 ，２ＣａＯ・ＳｉＯ2 ，３
ＣａＯ・Ａｌ2 Ｏ3 ，４ＣａＯ・Ａｌ2Ｏ3 ・Ｆｅ2 Ｏ
3 といった組成のものを有しており、従って水と反応す
るとＣａ（ＯＨ）2 を生成するから、セメント（コンク
リート）構造物は高ｐＨな素材であると考えられ、上記
の要望を満たしたものであると考えられる。[0009] Therefore, it is strongly desired that the radioactive waste treatment facility and the treated body are made of a material having a high pH. By the way, cements that have been used for the treatment of radioactive wastes are 3CaO.SiO 2 , 2CaO.SiO 2 , 3
CaO · Al 2 O 3, 4CaO · Al 2 O 3 · Fe 2 O
Cement (concrete) structure is considered to be a high-pH material because it has a composition such as 3 and therefore produces Ca (OH) 2 when it reacts with water, and meets the above-mentioned demands. It is considered to be.
【００１０】しかしながら、セメントのｐＨを決定する
Ｃａ（ＯＨ）2 の保持度を調べてみると、これは図１及
び図２に示されるような結果であった。図１は、市販の
ソックスレー浸出試験装置を使用し、その抽出部にセメ
ントの組成物を入れ、フラスコ部に水を入れ、マントル
ヒーターで加熱し、所定時間に浸出液を取り出し、浸出
液のＣａ（ＯＨ）2 を測定し、試料中にＣａ（ＯＨ）2
がどれだけ残存しているかを調べたグラフであり、図２
は試料中のＣａ／Ｓｉを調べたグラフである。However, when the retention of Ca (OH) 2 , which determines the pH of the cement, was examined, the results were as shown in FIGS. 1 and 2. FIG. 1 shows the use of a commercially available Soxhlet leaching test apparatus, in which the cement composition was put into the extraction part, water was put into the flask part, heated with a mantle heater, the leachate was taken out at a predetermined time, and Ca (OH 2 ) was measured and Ca (OH) 2
FIG. 2 is a graph showing how much remains in FIG.
Is a graph showing Ca / Si in the sample.
【００１１】これによれば、セメントペースト中の水酸
化カルシウムは水との反応によって生成すれども、これ
は次第に比較的速く失われていくことが推察される。例
えば、地下水の侵入・拡散を考えたならば、放射性廃棄
物処理施設や処理体を構成するセメント（コンクリー
ト）構造物から水酸化カルシウムが失われて行く速度は
かなりのものであると予測される。そして、数百年〜数
百万年にわたって高ｐＨであることを要求された場合に
は、これまでのようなセメント（コンクリート）構造物
では充分に満足できるものではなくなる。According to this, it is presumed that calcium hydroxide in the cement paste is generated by the reaction with water, but is gradually lost relatively quickly. For example, considering the intrusion and diffusion of groundwater, it is expected that the rate at which calcium hydroxide is lost from the cement (concrete) structures that make up radioactive waste treatment facilities and treatment bodies will be considerable. . If a high pH is required for hundreds to millions of years, a conventional cement (concrete) structure will not be sufficiently satisfactory.
【００１２】ところで、本願発明者は、上記ソックスレ
ー浸出試験装置を用いての研究に際して、セメントのみ
ではなく、セメントクリンカを所定の大きさに粉砕して
得た骨材についても同様に調べた。この結果は幸運なも
のであった。すなわち、セメントクリンカ製骨材の場合
についても、Ｃａ（ＯＨ）2 がどれだけ残存しているか
の結果を図１に、試料中のＣａ／Ｓｉの結果を図２に示
したが、これらによればセメントクリンカ製骨材からＣ
ａ（ＯＨ）2 が溶解消失して行く速度よりも生成する速
度の方が高く、残存Ｃａ（ＯＨ）2 濃度が高まる結果を
示している。かつ、Ｃａの溶解消失量もセメントの場合
に比べるとはるかに小さいことが判る。By the way, the inventor of the present application, when conducting a study using the above-described Soxhlet leaching test apparatus, similarly examined not only cement but also aggregate obtained by pulverizing a cement clinker to a predetermined size. The result was fortunate. That is, in the case of the aggregate made of cement clinker, the result of how much Ca (OH) 2 remains is shown in FIG. 1 and the result of Ca / Si in the sample is shown in FIG. From cement clinker aggregate to C
The rate at which a (OH) 2 is generated is higher than the rate at which a (OH) 2 dissolves and disappears, indicating that the residual Ca (OH) 2 concentration increases. Also, it can be seen that the amount of dissolved and lost Ca is much smaller than that of cement.
【００１３】尚、この現象は次のようなことに基づくも
のと思われる。所望の大きさを有するセメントクリンカ
製骨材は、その表面において水と反応し、Ｃａ（ＯＨ）
2 が生成する。この生成したＣａ（ＯＨ）2 はセメント
クリンカ製骨材表面に析出した状態にある。そして、析
出したＣａ（ＯＨ）2 が地下水などに溶解していって
も、Ｃａ（ＯＨ）2 はセメントクリンカ製骨材の内部か
ら徐々に供給されて来、結果的に残存Ｃａ（ＯＨ）2 濃
度が高まるものと思われる。It is considered that this phenomenon is based on the following. Aggregate made of cement clinker having a desired size reacts with water on its surface, and Ca (OH)
2 produces. The generated Ca (OH) 2 is in a state of being precipitated on the surface of the aggregate made of cement clinker. Even if the precipitated Ca (OH) 2 is dissolved in groundwater or the like, Ca (OH) 2 is gradually supplied from the inside of the aggregate made of cement clinker, and as a result, the remaining Ca (OH) 2 It is expected that the concentration will increase.
【００１４】又、セメントクリンカ製骨材を用いて構成
したセメントモルタルやコンクリートの強度は通常の砂
利などの骨材を用いて構成したセメントモルタルやコン
クリートの場合と同様に充分にあり、セメントクリンカ
製の骨材は放射性廃棄物の処理構造物の骨材として充分
に使用できるものである。このような知見を基にして本
発明が達成されたのである。すなわち、放射性廃棄物処
理施設や処理体を構成するセメント（コンクリート）構
造物の骨材としてセメントクリンカを使用すれば、長期
間にわたってセメント（コンクリート）構造物を高ｐＨ
のものに保持できるのではないかとの発想が得られ、本
発明が達成されたのである。Further, the strength of cement mortar and concrete formed by using aggregates made of cement clinker is sufficient as in the case of cement mortar and concrete formed by using aggregates such as ordinary gravel. The aggregate can be sufficiently used as an aggregate of a structure for treating radioactive waste. The present invention has been achieved based on such findings. That is, if a cement clinker is used as an aggregate of a cement (concrete) structure that constitutes a radioactive waste treatment facility or a treated body, the cement (concrete) structure can have a high pH over a long period of time.
The idea that it can be held in the object is obtained, and the present invention has been achieved.
【００１５】本発明で用いられるセメントクリンカは、
主原料である石灰石、粘土、珪石などを乾燥・調合し、
微粉砕し、そしてこれをプレヒータで８５０℃程度にま
で加熱後に仮焼炉及びキルンで１４５０℃程度の温度で
半溶融状態に焼き締められることによって得られる。そ
して、これを所望の大きさに粉砕することによってセメ
ントクリンカ製の粗骨材あるいは細骨材が得られる。The cement clinker used in the present invention is:
Dry and mix limestone, clay, silica, etc., which are the main ingredients,
It is obtained by pulverizing and heating this to about 850 ° C. with a preheater, and then baking to a semi-molten state at a temperature of about 1450 ° C. in a calciner and kiln. Then, this is pulverized to a desired size to obtain a coarse aggregate or a fine aggregate made of cement clinker.
【００１６】このようにして得られた骨材の組成は、例
えば３ＣａＯ・ＳｉＯ2 が約２８ｗｔ％、２ＣａＯ・Ｓ
ｉＯ2 が約５６ｗｔ％、３ＣａＯ・Ａｌ2 Ｏ3 が約２ｗ
ｔ％、４ＣａＯ・Ａｌ2 Ｏ3 ・Ｆｅ2 Ｏ3 が約８ｗｔ
％、その他ＭｇＯ，ＳＯ3 ，Ｎａ2 Ｏ，Ｋ2 Ｏ，ＴｉＯ
2 等が少量含まれている。尚、この組成のものに限られ
るものではない。The composition of the aggregate thus obtained is, for example, about 28 wt% of 3CaO.SiO 2 and 2CaO.S
iO 2 is about 56 wt%, 3CaO.Al 2 O 3 is about 2 w
t%, 4CaO.Al 2 O 3 .Fe 2 O 3 is about 8 wt%
%, Other MgO, SO 3 , Na 2 O, K 2 O, TiO
It contains a small amount of 2 mag. The composition is not limited to this.
【００１７】以下、実施例により具体的に本発明を説明
する。Hereinafter, the present invention will be described specifically with reference to examples.
【００１８】[0018]
〔実施例１〕３ＣａＯ・ＳｉＯ2 が約２８ｗｔ％、２Ｃ
ａＯ・ＳｉＯ2 が約５６ｗｔ％、３ＣａＯ・Ａｌ2 Ｏ3
が約２ｗｔ％、４ＣａＯ・Ａｌ2 Ｏ3 ・Ｆｅ2 Ｏ3 が約
８ｗｔ％、その他微量のＭｇＯやＳＯ3 等が含まれてい
る低熱型セメントクリンカを５ｍｍ以下の大きさに粉砕
し、セメントクリンカで構成されてなる放射性廃棄物の
処理構造物に用いられる骨材を作製した。Example 1 3CaO · SiO 2 about 28 wt%, 2C
aO.SiO 2 is about 56 wt%, 3CaO.Al 2 O 3
There about 2wt%, 4CaO · Al 2 O 3 · Fe 2 O 3 is about 8 wt%, by grinding a low thermal cement clinker contains other trace amounts of MgO and SO 3 and the like in the following sizes 5 mm, cement clinker The aggregate used for the radioactive waste treatment structure consisting of was manufactured.
【００１９】そして、３ＣａＯ・ＳｉＯ2 が約２８ｗｔ
％、２ＣａＯ・ＳｉＯ2 が約５６ｗｔ％、３ＣａＯ・Ａ
ｌ2 Ｏ3 が約２ｗｔ％、４ＣａＯ・Ａｌ2 Ｏ3 ・Ｆｅ2
Ｏ3が約８ｗｔ％、その他微量のＭｇＯやＳＯ3 等が含
まれているセメント２０００ｇ、上記の骨材２０００
ｇ、水９００ｇを混合し、４ｃｍ×４ｃｍ×１６ｃｍの
モルタル試験体を６本作製し、曲げ強度及び圧縮強度を
調べたので、その結果を下記の表−１に示す。Then, about 28 wt% of 3CaO.SiO 2
%, 2CaO.SiO 2 is about 56 wt%, 3CaO.A
about 2 wt% of l 2 O 3 , 4CaO.Al 2 O 3 .Fe 2
2000 g of cement containing about 8 wt% of O 3 and other trace amounts of MgO, SO 3, etc.
g and 900 g of water were mixed to prepare six mortar specimens of 4 cm × 4 cm × 16 cm, and the bending strength and the compressive strength were examined. The results are shown in Table 1 below.
【００２０】 表−１ 曲げ強度（ｋｇ／ｃｍ2 ） 圧縮強度（ｋｇ／ｃｍ2 ） ７日後 ７３ ３２９ ２８日後 １０３ ７５２ これによれば、セメントクリンカを骨材として構成され
た放射性廃棄物の固型化材、固化体の周囲の充填材ある
いは構築体は、その目的に必要な物理的性能を有したも
のであることが判る。Table 1 Flexural strength (kg / cm 2 ) Compressive strength (kg / cm 2 ) After 7 days 73 329 After 28 days 103 752 According to this, solid form of radioactive waste composed of cement clinker as aggregate It is understood that the filler or the structure around the solidified material, the solidified material has the physical performance required for the purpose.
【００２１】又、前記の図１や図２より、セメントクリ
ンカを骨材として構成された放射性廃棄物の固型化材、
固化体の周囲の充填材あるいは構築体は長期間にわたっ
て高ｐＨの環境が保持されることが窺え、従って放射性
廃棄物を長期間にわたって安全に保管処分できることが
判る。1 and 2, the solidification material of radioactive waste composed of cement clinker as an aggregate,
It can be seen that the high pH environment is maintained in the filler or the structure around the solidified body for a long period of time, and thus it can be seen that the radioactive waste can be safely stored and disposed for a long period of time.
【００２２】[0022]
【効果】本発明によれば、長期間にわたってセメント
（コンクリート）構造物を高ｐＨ環境下に保持でき、従
って放射性廃棄物の滲出の防止を一層図れるようにな
り、又、セメント（コンクリート）構造物の耐久性も高
く、放射性廃棄物処理の長期安全性が高いといった特長
が奏される。According to the present invention, a cement (concrete) structure can be maintained in a high pH environment for a long period of time, so that the leaching of radioactive waste can be further prevented. It has the features of high durability and high long-term safety of radioactive waste disposal.
【図１】試料中のＣａ（ＯＨ）2 残存量を示すグラフで
ある。FIG. 1 is a graph showing the amount of Ca (OH) 2 remaining in a sample.
【図２】試料中のＣａ／Ｓｉを示すグラフである。FIG. 2 is a graph showing Ca / Si in a sample.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 荒巻 政美 埼玉県熊谷市月見町二丁目１番１号 秩 父セメント株式会社 中央研究所内 (56)参考文献 特開 平１−191098（ＪＰ，Ａ) 特開 平４−50700（ＪＰ，Ａ) (58)調査した分野(Int.Cl.7，ＤＢ名) G21F 9/30 G21F 9/16 ──────────────────────────────────────────────────続 き Continuing from the front page (72) Inventor Masami Aramaki 2-1-1, Tsukimi-cho, Kumagaya-shi, Saitama Chichibu Cement Co., Ltd. Central Research Laboratory (56) References JP-A 1-191098 (JP, A JP-A-4-50700 (JP, A) (58) Fields investigated (Int. Cl. 7 , DB name) G21F 9/30 G21F 9/16
Claims (5)
骨材であって、この骨材がセメントクリンカで構成され
てなることを特徴とする放射性廃棄物の処理構造物に用
いられる骨材。1. An aggregate for use in a radioactive waste treatment structure, wherein the aggregate is composed of a cement clinker.
物の処理に用いられるコンクリート体であることを特徴
とする請求項１の放射性廃棄物の処理構造物に用いられ
る骨材。2. The aggregate used for the radioactive waste treatment structure according to claim 1, wherein the radioactive waste treatment structure is a concrete body used for radioactive waste treatment.
物の処理に用いられるセメントモルタル体であることを
特徴とする請求項１の放射性廃棄物の処理構造物に用い
られる骨材。3. The aggregate used in the structure for treating radioactive waste according to claim 1, wherein the structure for treating radioactive waste is a cement mortar used for treating radioactive waste.
骨材であることを特徴とする請求項１の放射性廃棄物の
処理構造物に用いられる骨材。4. The aggregate used for a radioactive waste treatment structure according to claim 1, wherein the aggregate composed of cement clinker is a coarse aggregate.
骨材であることを特徴とする請求項１の放射性廃棄物の
処理構造物に用いられる骨材。5. The aggregate used in the structure for treating radioactive waste according to claim 1, wherein the aggregate composed of cement clinker is a fine aggregate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP08289093A JP3164131B2 (en) | 1993-04-09 | 1993-04-09 | Aggregate used in radioactive waste treatment structures |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP08289093A JP3164131B2 (en) | 1993-04-09 | 1993-04-09 | Aggregate used in radioactive waste treatment structures |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH06294897A JPH06294897A (en) | 1994-10-21 |
| JP3164131B2 true JP3164131B2 (en) | 2001-05-08 |
Family
ID=13786874
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP08289093A Expired - Fee Related JP3164131B2 (en) | 1993-04-09 | 1993-04-09 | Aggregate used in radioactive waste treatment structures |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3164131B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7294375B2 (en) | 2002-07-18 | 2007-11-13 | Kabushiki Kaisha Kobe Seiko Sho | Cement composite, concrete, concrete cask and method of manufacturing concrete |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2750981B1 (en) * | 1996-07-12 | 1998-11-06 | Cia | METHOD FOR PROLONGING THE LONG-TERM PROTECTIVE EFFECT OF A CEMENT-BASED COMPOSITION AGAINST CORROSION OF STEELS INCLUDED AND PRODUCT ALLOWING THIS PROLONGATION |
-
1993
- 1993-04-09 JP JP08289093A patent/JP3164131B2/en not_active Expired - Fee Related
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7294375B2 (en) | 2002-07-18 | 2007-11-13 | Kabushiki Kaisha Kobe Seiko Sho | Cement composite, concrete, concrete cask and method of manufacturing concrete |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH06294897A (en) | 1994-10-21 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Asavapisit et al. | Solidification of electroplating sludge using alkali-activated pulverized fuel ash as cementitious binder | |
| PL189796B1 (en) | Encapsulation of hazardous wastes | |
| Singh et al. | Chemically bonded phosphate ceramics for low‐level mixed‐waste stabilization | |
| US20080134943A1 (en) | Encapsulation Medium | |
| JPH0634097B2 (en) | Solidifying agent for radioactive waste | |
| EP0644555B1 (en) | Preparation of inorganic hardenable slurry and method for solidifying wastes with the same | |
| He et al. | Utilization of soda residue and ground granulated blast furnace slag to stabilize/solidify sewage sludge in leachate soaking environment | |
| JP3164131B2 (en) | Aggregate used in radioactive waste treatment structures | |
| US5569153A (en) | Method of immobilizing toxic waste materials and resultant products | |
| JP2583729B2 (en) | Detoxification and stabilization of waste containing hazardous heavy metals | |
| Piyaphanuwat et al. | Alkali‐activated composites of calcium carbide and black rice husk ash for immobilizing electroplating sludge | |
| JP3213054B2 (en) | Treatment method for incinerated ash containing heavy metals | |
| JP2001208896A (en) | Method of cosolidifying low-level radioactive wetting waste generated from boiling water nuclear power plant | |
| KR100357524B1 (en) | Solidity material for reapplication of assignment waste harding foam having excellent compressive strength using the solidity material | |
| JPS62238499A (en) | Method of solidifying radioactive waste | |
| Langton | Slag-based materials for toxic metal and radioactive waste stabilization | |
| JP2002121064A (en) | Hydration reaction retardation type cement composition | |
| El-Sayed et al. | Incorporation of spent ion exchange resin simulate into cement composites | |
| Asavapisit et al. | Effects of Lead and Chromium Hvdroxides on Cement-BaseSd olidifiedW aste Properties | |
| JP3005617B2 (en) | Method for stable solidification of incinerated ash and solidified products | |
| Um et al. | The Effect of Ettringite on Cementitious Waste Form Development for Low-Activity Waste-17170 | |
| JP2007532897A (en) | How to enclose hazardous waste | |
| Maenami et al. | Hydrothermally prepared inorganic siliceous wastes: hydrothermal reaction of calcareous and steatite ceramic tile wastes | |
| JPH06331794A (en) | Aggregate for cementing radioactive waste and production thereof | |
| JPH0352421B2 (en) |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20080302 Year of fee payment: 7 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20090302 Year of fee payment: 8 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20090302 Year of fee payment: 8 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20100302 Year of fee payment: 9 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20100302 Year of fee payment: 9 |
|
| S531 | Written request for registration of change of domicile |
Free format text: JAPANESE INTERMEDIATE CODE: R313531 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20100302 Year of fee payment: 9 |
|
| R350 | Written notification of registration of transfer |
Free format text: JAPANESE INTERMEDIATE CODE: R350 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20100302 Year of fee payment: 9 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20110302 Year of fee payment: 10 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20110302 Year of fee payment: 10 |
|
| FPAY | Renewal fee payment (event date is renewal date of database) |
Free format text: PAYMENT UNTIL: 20120302 Year of fee payment: 11 |
|
| LAPS | Cancellation because of no payment of annual fees |