JPS61215999A - Solidifying agent for radioactive waste - Google Patents

Solidifying agent for radioactive waste

Info

Publication number
JPS61215999A
JPS61215999A JP5616285A JP5616285A JPS61215999A JP S61215999 A JPS61215999 A JP S61215999A JP 5616285 A JP5616285 A JP 5616285A JP 5616285 A JP5616285 A JP 5616285A JP S61215999 A JPS61215999 A JP S61215999A
Authority
JP
Japan
Prior art keywords
cement
waste
water
solidifying agent
agent
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.)
Granted
Application number
JP5616285A
Other languages
Japanese (ja)
Other versions
JPH0634097B2 (en
Inventor
悦郎 坂井
柴山 幸夫
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Denka Co Ltd
Original Assignee
Denki Kagaku Kogyo KK
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Denki Kagaku Kogyo KK filed Critical Denki Kagaku Kogyo KK
Priority to JP60056162A priority Critical patent/JPH0634097B2/en
Publication of JPS61215999A publication Critical patent/JPS61215999A/en
Publication of JPH0634097B2 publication Critical patent/JPH0634097B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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  • Fats And Perfumes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔座業上の利用分野〕 本発明は放射性廃棄物の同化剤、詳しくはセメント質物
質、超微粉、尚性能減水剤及び水を生成分とし、処理能
力が犬で、永久貯蔵も可能で放射性物質の浴出性が低い
、安全な放射性廃棄物の同化剤に関する。
[Detailed description of the invention] [Field of sedentary use] The present invention is an assimilating agent for radioactive waste, specifically a cementitious material, an ultrafine powder, a water reducing agent, and water as the product components, and the treatment capacity is comparable to that of a dog. This invention relates to a safe radioactive waste assimilation agent that can be stored permanently and has a low tendency to release radioactive materials.

〔従来技術〕[Prior art]

原子力発電所、核燃料再処理工場等の原子力施設から発
生する放射性廃棄物としては、磯縮廃液、便用断みイオ
ン交換樹脂、フィルタースラッジ、焼却灰、雑固体、各
iスラッジ及び原子力発電所の解体に伴い廃山されるコ
ンクリート廃材などの、いわゆる低、中レベル放射性廃
棄物をはじめ高レベル放射性M来物があげられる。
Radioactive waste generated from nuclear facilities such as nuclear power plants and nuclear fuel reprocessing plants includes slag waste, ion exchange resin for toilet use, filter sludge, incineration ash, miscellaneous solids, various i-sludges, and nuclear power plant waste. These include so-called low- and medium-level radioactive waste, such as concrete scraps that are disposed of during demolition, as well as high-level radioactive materials.

これら放射性PA粱物、特に低、中レベル放射性廃棄物
の固化処理法としては、セメント固化法、ビチューメン
固化法、プラスチック同化法が実用されている。
The cement solidification method, the bitumen solidification method, and the plastic assimilation method are in practical use as methods for solidifying these radioactive PA residues, especially low- and medium-level radioactive wastes.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

しかしながら、セメント固化法は、耐久性にはすぐれて
いるものの、処m能力が小さいことや、浸出性が比較的
大きいこと寺の欠点があった。また、ビチューメン固化
法やプラスチック固化法は、処理能力は大きいが、処理
方法が複雑であることや耐候性等の面からの安全性に問
題があることなどの欠点があった。
However, although the cement solidification method has excellent durability, it has disadvantages such as low processing capacity and relatively high leachability. Further, although the bitumen solidification method and the plastic solidification method have high processing capacity, they have drawbacks such as complicated processing methods and safety problems in terms of weather resistance and the like.

以上のことから、処理能力が大きく、かつ浸出性が低く
、耐候性の優れた放射性廃棄物の処理方法が切望され【
いる。
Based on the above, there is a strong need for a radioactive waste disposal method that has large processing capacity, low leachability, and excellent weather resistance.
There is.

本発明者らは、上記欠点を解消すべく、糧々検討を行っ
た結果、特定の成分を生成分とする固化剤を用いること
により、上記欠点を改良することを見い出し、本発明を
完成するに到った。
In order to eliminate the above-mentioned drawbacks, the present inventors have made extensive studies and have discovered that the above-mentioned drawbacks can be improved by using a solidifying agent containing a specific component as a product, thereby completing the present invention. reached.

〔問題点を解犬するための手段〕[Means for solving problems]

即ち、不発明は、セメント買物質、超微粉、高性能減水
剤及び水を生成分とする放射性Xfi物の固化剤である
That is, the invention is a solidifying agent for a radioactive Xfi substance whose product components are a cement substance, an ultrafine powder, a high-performance water reducer, and water.

以下、不発明の詳細な説明する。Hereinafter, the non-invention will be explained in detail.

本発明でいうセメント質物質とは、晋通、早強、超早強
、白色もしくは耐億ば塩等各櫨ポルトランドセメント、
さらには高炉スラグ、フライアッシュ!#混和材を混合
した混合セメント、及び混合材及び/又は混合されるセ
メントを粉砕した混合セメントなどが一般に用いられる
The cementitious materials referred to in the present invention include various types of portland cement such as Shintsu, early strength, ultra early strength, white or salt-resistant,
Furthermore, blast furnace slag and fly ash! #Commonly used are mixed cement containing admixtures, and mixed cement obtained by pulverizing the mixed material and/or the cement to be mixed.

また、さらに膨張セメントを用いて収縮補償したり、急
硬セメントを用いて短時間に所要強度を発現させたり、
石膏系の高強度混和材を併用することもできる。
In addition, we can use expanding cement to compensate for shrinkage, and use rapid hardening cement to develop the required strength in a short time.
A gypsum-based high-strength admixture can also be used.

膨張セメントの膨張成分としては、エトリンガイト系の
もの例えば電気化学工業((社)[rcsA#:20j
や焼成CaOが好ましく、焼成CaO中でも1100〜
1600°Cで焼成され、結晶径平均が10μ以下のも
のが特に好ましい。
As the expanding component of the expanding cement, ettringite-based ones such as those manufactured by Denki Kagaku Kogyo Co., Ltd. [rcsA#:20j
or calcined CaO is preferable, and among calcined CaO, 1100~
Particularly preferred are those which are fired at 1600°C and have an average crystal diameter of 10μ or less.

急硬セメントは、各イ1のカルシウムアルミネート単独
又はそれと硫酸カルシウムとの混合物等のように、カル
シウムアルミネート系の急硬成分を含んだものであって
、それには、電気化学工業(休)−商品名[デンカE8
Jを配合したセメントや、小野田セメント(休)製画品
名「ジェットセメント」などがある。
Rapid hardening cement is one that contains a calcium aluminate-based rapid hardening component, such as calcium aluminate alone or a mixture of calcium aluminate and calcium sulfate. -Product name [Denka E8
There are cements containing J and the product name ``Jet Cement'' manufactured by Onoda Cement (now closed).

また、高強度混和材としては石膏系のものであり、電気
化学工業((社)製「デンカΣ−1000J、日本セメ
ント((社)襄「アサノスーパーミックス」、大阪セメ
ント(株)製「ノンクレープ」等があげられる。
In addition, high-strength admixtures include gypsum-based ones, such as "Denka Σ-1000J" manufactured by Denki Kagaku Kogyo Co., Ltd., "Asano Super Mix" manufactured by Nippon Cement Co., Ltd., and "Non-Non" manufactured by Osaka Cement Co., Ltd. Crepes, etc.

本発明で便用する超微粉とは、平均粒径が前述のセメン
ト質物質より少なくとも1オーダー低いものであり、臀
に平均粒径が2オーダー低いものが混練物の流動特性の
而から好ましい。具体的には、シリコン、含シリコン合
並ならびにジルコニアを製造する−に一生するシリカダ
スト(シリカヒユーム)、及びシリカ買ダストが特に最
適であり、その他に、炭酸カルシウム、シリカゾル、オ
パール質硅石、フライアッシュ、スラグ、酸化チタン、
酸化アルミニウムなどの超微粉も使用できる。特に、オ
パール質硅石、フライアッシュ1スラグを分級器つきシ
ェツトミル等により粉砕した超微粉の使用は硬化収縮を
改嵜するという面から有効である。
The ultrafine powder conveniently used in the present invention has an average particle size that is at least one order of magnitude lower than that of the above-mentioned cementitious material, and preferably one that has an average particle diameter of two orders of magnitude lower from the viewpoint of the fluidity of the kneaded product. Specifically, silica dust (silica hume) and silica powder, which are used for manufacturing silicon, silicon-containing materials, and zirconia, are particularly suitable.In addition, calcium carbonate, silica sol, opalescent silica, fly ash, slag, titanium oxide,
Ultrafine powders such as aluminum oxide can also be used. In particular, the use of ultrafine powder obtained by pulverizing opalescent silica or fly ash 1 slag using a shet mill equipped with a classifier or the like is effective from the standpoint of improving hardening shrinkage.

超微粉の使用量は、好ましくはセメント買物質60〜9
5′jL]を部に対して5〜40重量部、さらに好まし
くは65〜90x′Ik部に対して10〜65重量部で
あり、5TLt部未満では高強度(@牢性)を得ること
が困難であり、また、40重量部を越えると混練物の流
動性が著しく低下し、成形することが困難となり、かつ
、強度発現も不充分となる。
The amount of ultrafine powder used is preferably 60 to 9
5'jL] is 5 to 40 parts by weight, more preferably 10 to 65 parts by weight relative to 65 to 90x'Ik parts, and if it is less than 5TLt parts, high strength (@tightness) cannot be obtained. Moreover, if the amount exceeds 40 parts by weight, the fluidity of the kneaded product will be significantly reduced, making it difficult to mold it and developing insufficient strength.

本発明で使用する高性能減水剤(以下減水剤という)と
は、セメント比多量添加しても凝結の過遅延や過度の空
気連行を伴なわない分散能力の大きな界面活性剤であっ
て、ナフタリンスルホン酸ホルムアルデヒド縮金物の塩
、メラミンスルホン酸ホルムアルデヒド縮金物の塩、高
分子量リグニンスルホン酸塩、ポリカルボン酸塩などを
生成分とするものがあげられる。減水剤は、混線物を低
水比で得るために必要なものであり、従来の使用量は、
セメント買′1821買に対し固形分として0.5〜1
東菫チが使用されているが、本発明においては、それよ
りも多量に添加することが好ましい。具体的には、セメ
ント質物質と超微粉との混合物100][x部に対し固
形分として10貞量部程度まで使用され、それよりも多
量に添加すると硬化反応にかえって悪影響を与える。特
に好ましい添加量は1〜5I童部である。このような減
水剤の使用量において、超微粉と組み合わせることによ
り、水セメント質物質と超微粉比が25%以下でも、通
常の方法により成形可能な流動性のある混練物を侍るこ
とができる。
The high-performance water reducing agent (hereinafter referred to as water reducing agent) used in the present invention is a surfactant with a large dispersion ability that does not cause too much delay in setting or excessive air entrainment even when added in a large amount compared to cement, and is Examples include salts of sulfonic acid formaldehyde condensed metals, salts of melamine sulfonic acid formaldehyde condensed metals, high molecular weight lignin sulfonates, polycarboxylic acid salts, and the like. Water reducing agents are necessary to obtain mixed materials at low water ratios, and the conventional usage amount is
0.5 to 1 as solid content for cement purchase '1821 purchase
Although Higashi Sumirechi is used, in the present invention, it is preferable to add it in a larger amount. Specifically, a mixture of a cementitious material and an ultrafine powder is used up to about 10 parts by weight as a solid content for x parts, and if it is added in a larger amount, it will adversely affect the curing reaction. A particularly preferable addition amount is 1 to 5 I Dobe. By using such a water reducing agent in combination with ultrafine powder, it is possible to obtain a fluid kneaded material that can be molded by a conventional method even if the ratio of water cementitious material to ultrafine powder is 25% or less.

本発明で混合物を調整する際に使用する水は成形上必要
なものであるが、高強度硬化体を得るためにはできるだ
け少量にするのが艮く、セメント質vlJ負と超微粉と
の混合物100貞童部に対し12.5〜50 N jt
 mとすルノが好ましく、15〜28、重意部がさらに
好ましい。水型が60重重部より多いと高強度硬化体を
得ることが困−であり、12.5電量部より少ないと通
常の流し込み等の成形が困難となる。なお、圧着成形等
においては、これに制限されるものではなく 12.5
重量部より少ない場合においても成形が可能となる。
The water used when preparing the mixture in the present invention is necessary for molding, but in order to obtain a high-strength hardened product, it is advisable to use as little water as possible. 12.5 to 50 N jt for 100 children
m and Luno are preferable, and 15 to 28 and a weight part are more preferable. When the amount of water is more than 60 parts by weight, it is difficult to obtain a high-strength cured product, and when it is less than 12.5 parts by weight, it is difficult to perform normal molding such as pouring. Note that pressure molding, etc. is not limited to this. 12.5
Molding is possible even when the amount is less than parts by weight.

本発明に係る固化剤を用いて放射性廃棄物(以下廃棄物
という)を処理するには、従来のセメント固化法が通用
できる。即ち、廃棄物をドラムやコンクリート製容器等
の処分容器内で練り混ぜる方法、あらかじめ練り混ぜた
ものを処分容器に充填する方法、処分容器内に廃棄物を
予め詰めておき、その後その空隙に固化剤を充填させる
方法、又逆に同化剤を予め処分容器内に詰め、そこを減
圧するか、廃棄物を加圧するかして処分容器内へ注入す
る方法などが適用される。この際、同化剤の添加瀘は廃
棄物が固体であるか、含水状態であるかなどにより大幅
に異なるが、廃棄物100電蓋鄭に対し、10〜500
重量部程度が一般的である。処理能力を大きくするとい
う面からは、固化剤が少ない程好ましいが、10:a重
量部以下では固化することは娼しく、放射性物質の解出
を抑制する効米も乏しい。
Conventional cement solidification methods can be used to treat radioactive waste (hereinafter referred to as waste) using the solidification agent according to the present invention. These methods include mixing the waste in a disposal container such as a drum or concrete container, filling the disposal container with a mixture that has been mixed in advance, and filling the waste into the disposal container and then solidifying it in the void space. A method of filling the disposal container with an assimilating agent, or conversely, a method of filling the disposal container with an assimilating agent in advance, reducing the pressure there, or pressurizing the waste and injecting it into the disposal container, etc. are applied. At this time, the addition rate of assimilation agent varies greatly depending on whether the waste is solid or water-containing, but for every 100 tons of waste, 10 to 500
It is generally about parts by weight. From the viewpoint of increasing processing capacity, it is preferable to use as little solidifying agent as possible, but if the amount is less than 10:a parts by weight, solidifying is difficult and the effect of suppressing the release of radioactive substances is poor.

〔実施例〕〔Example〕

以下実施例によりさらに詳しく説明する。 This will be explained in more detail below with reference to Examples.

実施例1 表−1y162に示す配合に0.2μc1”CJ、−/
α3となるよう放射性同位体を練り混ぜ、φ5X5t、
Mの供試体を作製し、密閉容器中で養生を行い、材令6
日後、Q、lMo1のNaCj溶液中でのリーチングテ
ストを実施し、浸漬日数と浴出量の関係より有効拡散係
数Deを求めた。さらに、表−144に示す配合で厚さ
1c!!Lの薄膜を作製し、それを隔てて一方に134
 C8+を含む1Q−’ MolのC5CJを入れ、1
34 CS+の拡散係数りを求めた。結果を衆−2に示
す。
Example 1 0.2μc1”CJ, -/ in the formulation shown in Table-1y162
Mix radioactive isotope to obtain α3, φ5X5t,
A specimen of M was prepared and cured in a sealed container until the material age was 6.
After a day, a leaching test was carried out in a NaCj solution of Q, lMo1, and the effective diffusion coefficient De was determined from the relationship between the number of days of immersion and the amount of bathing. Furthermore, with the formulation shown in Table 144, the thickness is 1c! ! A thin film of L was prepared, and one side was separated by 134
Add 1Q-' Mol of C5CJ containing C8+ and add 1
The diffusion coefficient of 34 CS+ was determined. The results are shown to public-2.

我−1 表−2 く使用材料〉 セメント :電気化学工業(休)製、普通ポルトランド
セメント 趙微松二日本嵐化芋工業(休)襄、シリカヒユーム 減水剤:第−工業製系(休)製、[セルフロー10PJ 比較例1 記号/161及びそれに配合/166を用いたこと以外
は実施例1と同様に行った。結果を表−2に示す。
I-1 Table-2 Materials used> Cement: Manufactured by Denki Kagaku Kogyo (closed), ordinary Portland cement, Zhao Weisong Nihon Arashi Kaimo Kogyo (closed), silica hume Water reducer: Manufactured by Dai-Kogyo (closed), [ Cellflow 10PJ Comparative Example 1 The same procedure as Example 1 was carried out except that the symbol /161 and its blend /166 were used. The results are shown in Table-2.

実施例2 沸騰水型原子炉から排出されるイオン交侠樹脂再生廃液
、フィルタースラッジ、使用新イオン交換樹脂などから
なる廃棄物を蒸発嬢縮し、脱水した後サンプリングし、
表−6に示す配合からなる固化剤を用いて処理した。尚
、廃棄物の含水率は80%であり、この廃棄物100!
童部に対して固化剤は200!量部とした。その除の材
令6日における圧縮強度及び水中における浸出率を測定
し表−6に示す。
Example 2 Waste consisting of ion exchange resin regeneration waste liquid, filter sludge, used new ion exchange resin, etc. discharged from a boiling water nuclear reactor was evaporated, dehydrated, and then sampled.
It was treated using a solidifying agent having the formulation shown in Table 6. In addition, the moisture content of the waste is 80%, and this waste is 100%!
Solidifying agent is 200 for Dobe! It is expressed as a quantity part. The compressive strength and leaching rate in water of the wood at 6 days old were measured and shown in Table 6.

諌−6 比較例2 実1mA3の配合を用いたこと以外は実施例2と同様に
行った。結果を表−6に示す。
Isa-6 Comparative Example 2 The same procedure as in Example 2 was carried out except that the blend of 1 mA3 was used. The results are shown in Table-6.

実施例6 原子力発電所内建屋の解体に伴い、発生するコンクリー
ト廃材を、予めドラム管内に詰め、実施例2の実験/1
66の配合を用いた同化剤を注入し、φ15X3011
;711の供試体を作製し、材令28日の圧縮強度を求
めたところ、1,077 icgt7c、−mlであっ
た。比較のため、実験/I65の配合を用いた固化剤を
使用し、同様に試験したところ、圧縮強度は586にf
/ f /(7+2″L、かならず、しかも、コンクリ
ート廃材の下面にブリージング水による空隙が顕著にあ
られれた。
Example 6 Concrete waste generated during the demolition of a nuclear power plant building was packed in advance into a drum pipe, and experiment/1 of Example 2 was carried out.
Inject anabolic agent using the formulation of 66, φ15X3011
A specimen of No. 711 was prepared and the compressive strength at 28 days of age was determined to be 1,077 icgt7c, -ml. For comparison, a similar test was conducted using a solidifying agent with the formulation of Experiment/I65, and the compressive strength was 586 f.
/f/(7+2″L), and moreover, there were noticeable voids due to breathing water on the underside of the concrete waste.

〔発明の効果〕〔Effect of the invention〕

以上のように為本発明の固化剤を用いる固イヒ法は、従
来のセメント固化法より、処理能力カー大きく、ビチュ
ーメン同化法やプラスチック固化法に比して、化学抵抗
性、耐久性にすぐれ、しかも処理方法が簡単であり、耐
熱性にすぐれ、又、圧縮強度カー犬きく運搬中にも安全
であり、廃采物の貯蔵のみならず、永久貯蔵をも可能と
する処理方法である。
As described above, the hardening method using the hardening agent of the present invention has a larger processing capacity than the conventional cement hardening method, and has superior chemical resistance and durability compared to the bitumen assimilation method and the plastic hardening method. In addition, the treatment method is simple, has excellent heat resistance, and is safe even during transportation due to its compressive strength, making it possible not only to store waste kettle but also to permanently store it.

Claims (1)

【特許請求の範囲】[Claims] セメント質物質、超微粉、高性能減水剤及び水を生成分
とする放射性廃棄物の固化剤。
Solidifying agent for radioactive waste containing cementitious materials, ultrafine powder, high performance water reducer, and water.
JP60056162A 1985-03-22 1985-03-22 Solidifying agent for radioactive waste Expired - Lifetime JPH0634097B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60056162A JPH0634097B2 (en) 1985-03-22 1985-03-22 Solidifying agent for radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60056162A JPH0634097B2 (en) 1985-03-22 1985-03-22 Solidifying agent for radioactive waste

Publications (2)

Publication Number Publication Date
JPS61215999A true JPS61215999A (en) 1986-09-25
JPH0634097B2 JPH0634097B2 (en) 1994-05-02

Family

ID=13019395

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60056162A Expired - Lifetime JPH0634097B2 (en) 1985-03-22 1985-03-22 Solidifying agent for radioactive waste

Country Status (1)

Country Link
JP (1) JPH0634097B2 (en)

Cited By (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62267700A (en) * 1986-05-16 1987-11-20 株式会社東芝 Method of solidifying and processing radioactive waste
JPS62267699A (en) * 1986-05-16 1987-11-20 株式会社東芝 Method of solidifying and processing radioactive waste
JPS63167297A (en) * 1986-12-29 1988-07-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63205600A (en) * 1987-02-23 1988-08-25 電気化学工業株式会社 Solidifying agent for radioactive waste
JPS63223597A (en) * 1987-03-13 1988-09-19 株式会社日立製作所 Method of solidifying industrial waste and solidified body
JPS63243798A (en) * 1987-03-31 1988-10-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63243797A (en) * 1987-03-31 1988-10-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63289498A (en) * 1987-05-22 1988-11-25 Denki Kagaku Kogyo Kk Solidifying agent for radioactive waste
WO1989011149A1 (en) * 1988-05-02 1989-11-16 Hitachi, Ltd. Process for cementing radioactive waste and product of cementation
US5481061A (en) * 1987-03-13 1996-01-02 Hitachi, Ltd. Method for solidifying radioactive waste
US5732363A (en) * 1994-10-27 1998-03-24 Jgc Corporation Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product
WO2008114877A1 (en) 2007-03-16 2008-09-25 Denki Kagaku Kogyo Kabushiki Kaisha Low-activation hydraulic setting composition, low-activation cement, and those production methods
JP2013205272A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment method
JP2013205271A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment agent
JP2013205273A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment method
JP2018138505A (en) * 2017-02-24 2018-09-06 鹿島建設株式会社 Filling mortar and processing method for water absorptive waste

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55500863A (en) * 1978-11-03 1980-10-30
JPS5630697A (en) * 1979-08-22 1981-03-27 Mitsubishi Heavy Ind Ltd Method and device for filling and sealing container for radioactive liquid waste
JPS58132698A (en) * 1982-02-02 1983-08-08 電気化学工業株式会社 Method of processing radioactive waste

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55500863A (en) * 1978-11-03 1980-10-30
JPS5630697A (en) * 1979-08-22 1981-03-27 Mitsubishi Heavy Ind Ltd Method and device for filling and sealing container for radioactive liquid waste
JPS58132698A (en) * 1982-02-02 1983-08-08 電気化学工業株式会社 Method of processing radioactive waste

Cited By (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62267699A (en) * 1986-05-16 1987-11-20 株式会社東芝 Method of solidifying and processing radioactive waste
JPS62267700A (en) * 1986-05-16 1987-11-20 株式会社東芝 Method of solidifying and processing radioactive waste
JPS63167297A (en) * 1986-12-29 1988-07-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63205600A (en) * 1987-02-23 1988-08-25 電気化学工業株式会社 Solidifying agent for radioactive waste
US5481061A (en) * 1987-03-13 1996-01-02 Hitachi, Ltd. Method for solidifying radioactive waste
JPS63223597A (en) * 1987-03-13 1988-09-19 株式会社日立製作所 Method of solidifying industrial waste and solidified body
WO1988007256A1 (en) * 1987-03-13 1988-09-22 Hitachi, Ltd. Process for solidifying industrial waste and solidified waste
JPS63243798A (en) * 1987-03-31 1988-10-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63243797A (en) * 1987-03-31 1988-10-11 株式会社東芝 Solidifying processing method of radioactive waste
JPS63289498A (en) * 1987-05-22 1988-11-25 Denki Kagaku Kogyo Kk Solidifying agent for radioactive waste
WO1989011149A1 (en) * 1988-05-02 1989-11-16 Hitachi, Ltd. Process for cementing radioactive waste and product of cementation
US5732363A (en) * 1994-10-27 1998-03-24 Jgc Corporation Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product
WO2008114877A1 (en) 2007-03-16 2008-09-25 Denki Kagaku Kogyo Kabushiki Kaisha Low-activation hydraulic setting composition, low-activation cement, and those production methods
JP2013205272A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment method
JP2013205271A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment agent
JP2013205273A (en) * 2012-03-29 2013-10-07 Taiheiyo Material Kk Radioactive contaminant treatment method
JP2018138505A (en) * 2017-02-24 2018-09-06 鹿島建設株式会社 Filling mortar and processing method for water absorptive waste

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