JPS58109895A - Solidified material of radioactive waste - Google Patents

Solidified material of radioactive waste

Info

Publication number
JPS58109895A
JPS58109895A JP20710781A JP20710781A JPS58109895A JP S58109895 A JPS58109895 A JP S58109895A JP 20710781 A JP20710781 A JP 20710781A JP 20710781 A JP20710781 A JP 20710781A JP S58109895 A JPS58109895 A JP S58109895A
Authority
JP
Japan
Prior art keywords
water
layer
radioactive waste
solidified
waste
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
JP20710781A
Other languages
Japanese (ja)
Other versions
JPS6137600B2 (en
Inventor
玉田 慎
進 堀内
幹雄 平野
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP20710781A priority Critical patent/JPS58109895A/en
Priority to EP82111669A priority patent/EP0082483A1/en
Publication of JPS58109895A publication Critical patent/JPS58109895A/en
Publication of JPS6137600B2 publication Critical patent/JPS6137600B2/ja
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste
    • G21F9/36Disposal of solid waste by packaging; by baling

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】 本発明は、原子力発電所等で発生する放射性廃棄物を処
理するための固化処理体、轡に容器内への放射性廃棄物
の固化被覆部を改^してなゐ放射性廃棄物の固化処理体
に関する。
[Detailed Description of the Invention] The present invention is a solidification treatment body for treating radioactive waste generated at nuclear power plants, etc., and a solidification coating for radioactive waste inside a container has been modified. Concerning solidification of radioactive waste.

従来ドラム缶等の容器内κセメント等の同化体で放射性
廃棄物を被覆収容し良園化処理体とする技術がめるが、
このセメント園化体は無機剤でめることから安定性は高
いが、セメントのポークス状であるという特性から、対
水浸透性を考慮して一般に固化し得る廃棄物のセメント
に対する相対量は少なくせざるを得ないものであった。
Conventionally, there is a technology to cover and store radioactive waste with assimilated substances such as κ cement in containers such as drums to improve the quality of the garden.
This cement cement is highly stable because it is mixed with an inorganic agent, but due to the poke-like nature of cement, the relative amount of solidified waste to cement is generally small in consideration of water permeability. It was something I had no choice but to do.

本発明の目的は、容器内に収容する放射性廃棄物の固化
体に対する相対収容量を安価な手段で拡大できる放射性
廃棄物の固化処理体を提供することにある。
An object of the present invention is to provide a radioactive waste solidification treatment body that can expand the relative capacity of the radioactive waste solidified body contained in a container at low cost.

本発明は、同化層の嵌面に水不魂過性の層を形成するこ
とによシ、浸水による放射性吻質の漏洩を確実に防止し
つつ固化層自身の肉薄化を可能とすることによp前記目
的を達成するものである。
The present invention makes it possible to thin the solidified layer itself while reliably preventing the leakage of radioactive proboscis due to flooding by forming a water-permeable layer on the fitting surface of the assimilated layer. This is to achieve the above objectives.

なお、この種の放射性廃棄物の同化剤として現在までセ
メントの他、アスファルト、、プラスチック等奄検討さ
れてお9、減容能力の点では、プラスチックが望まれ、
また、安定性の点では、セメントがすでκ広範な分野で
実績をもっている。本発明はさらに安定で、かつ減容能
力の大きな同化剤として、ケイ酸アルカリ溶液等の無機
材の使用まで可能とし、この場合に問題となるポーラス
性で6ることによる厚肉化を防止して効率より収容を可
能とするものである。
In addition to cement, asphalt, plastic, and other materials have been considered as assimilating agents for this type of radioactive waste.9 In terms of volume reduction capacity, plastic is preferred;
In addition, in terms of stability, cement already has a proven track record in a wide range of fields. The present invention also enables the use of inorganic materials such as alkaline silicate solutions as an assimilating agent that is stable and has a large capacity for volume reduction, and prevents thickening due to porous properties, which is a problem in this case. This makes it possible to accommodate more efficiently.

以下、本発明の一5j!施例を図面を参照して、製作手
順に従い説明する。
The following is part 5j of the present invention! An embodiment will be described in accordance with the manufacturing procedure with reference to the drawings.

一端が開口したドラム缶lを開口面を上向きとして軸心
回りに回転させながら、その内部に、ケイ酸アルカリ溶
液を含浸させたガラス繊維2を流入し、遠心力によって
そのドラム缶1の内側面に密着させる。この際、ケイ酸
アルカリ#I液を含浸したガラス繊維2は、そのケイ酸
アルカリ溶液に基づく粘性によってドラム缶の内側壁に
害鳥に密着する。なお、密着し次ガラス繊維2の内周側
においては、ケイ酸アルカリS*が重力によp下部へ流
下し、そのガラス繊維の内局iut面には、このガラス
繊維自体に沿う粗面が現われる。
A drum 1 with an open end is rotated around its axis with the opening facing upward, and glass fibers 2 impregnated with an alkaline silicate solution are introduced into the drum 1 and tightly adhered to the inner surface of the drum 1 by centrifugal force. let At this time, the glass fiber 2 impregnated with the alkali silicate #I solution adheres to the inner wall of the drum and the harmful birds due to its viscosity based on the alkali silicate solution. In addition, on the inner peripheral side of the glass fiber 2 after being in close contact with each other, the alkali silicate S* flows down to the lower part due to gravity, and the inner iut surface of the glass fiber has a rough surface along the glass fiber itself. appear.

次にドラム缶1の内局面にガラス繊維2人を敷設し、側
面部のガラス繊維から流下したケイ酸アルカリ溶液をこ
の底部ガラス繊維に含浸させ、側面部と共に、乾燥固化
させる。
Next, two glass fibers are laid on the inner surface of the drum 1, and the bottom glass fiber is impregnated with the alkali silicate solution that has flowed down from the glass fibers on the side surface, and is dried and solidified together with the side surface.

そして、水不透過性の物質として、無機材であるセ2建
ツク系の素材、例えば8i0t61%。
As a water-impermeable substance, an inorganic double building material such as 8i0t61% is used.

B鵞0a14 %*  At1O@  1 0 %、N
O,08%。
B goose 0a14%* At1O@1 0%, N
O, 08%.

K107%の成分の釉を選定し、前記ガラス繊維の粗面
となった内表面部上に焼成することにより水不透過性の
層4t−形成する。
A water-impermeable layer 4t is formed by selecting a glaze containing 107% K and firing it on the rough inner surface of the glass fiber.

このようにして得られた、いわば固化容器中に、放射性
廃棄物を圧縮成形したベレット状廃棄物を挿入した後、
ケイ酸アルカリ溶液をベレットすべてに被覆する如く注
入し、その上面に、ガラス繊m5を乗せて、ケイ酸アル
カリ溶液を含浸させて固化し、側面及び下面と同様に水
不透過性の層4を焼成し、さらにその上部にケイ酸アル
カリ溶液単独の層6を設け、最終的にfllAによって
容器全体を密封する。
After inserting the pellet-shaped waste obtained by compression molding radioactive waste into the solidification container obtained in this way,
The alkaline silicate solution is injected so as to cover the entire pellet, and the glass fiber M5 is placed on the top surface, impregnated with the alkaline silicate solution and solidified, and a water-impermeable layer 4 is formed on the side and bottom surfaces as well. After firing, a layer 6 of an alkali silicate solution alone is provided on top of the firing, and finally the entire container is sealed with fl1A.

このようにして形成された放射性廃棄物の固化処理体に
よると、ケイ酸アルカリ溶液によってガラス繊維はドラ
ム缶1に密着し、また、水不透過層4は、ガラス繊m表
市に沿う粗園部に水ガラスを介して密着したものとな9
、ドラム缶外部からの耐水性の高い固化体が得られる。
According to the radioactive waste solidified body thus formed, the glass fibers adhere to the drum 1 due to the alkaline silicate solution, and the water-impermeable layer 4 is formed in the rough areas along the surface of the glass fibers. It's like something that's in close contact with water glass.9
, a solidified material with high water resistance from the outside of the drum can is obtained.

従って固化体層を比較的肉薄にしても、十分な耐水性を
得られるものとな9、従来の固化層のみによυ廃秦物管
被覆したものに比べて固化層に対する廃棄物の相対収容
量を増大させることができ、効率よい廃集処埴が可能と
なる。
Therefore, even if the solidified material layer is made relatively thin, sufficient water resistance can be obtained. The amount can be increased, making it possible to efficiently collect and dispose of waste.

なお、水不透過層4として、前記材料を用vh九場合は
、融点が低いことから作業性のよVh4のとなるが、本
発明はそのようなものに限らず、容器及び同化層との密
着性の良−ものであれば各種の耐水性樹脂(耐水塗料等
を含む)、釉、セラミック材料が適用で龜る。
If the above-mentioned material is used as the water-impermeable layer 4, the workability will be Vh4 due to its low melting point. Various water-resistant resins (including water-resistant paints, etc.), glazes, and ceramic materials can be used as long as they have good adhesion.

また、前記実施例の如くガラス繊ea*t−固化剤吸収
層として用い九もので参ると、コスト的な有利性を保持
しつつ、水不透過性の確実なものが作業性よく得られる
という利点を有する。
In addition, when glass fibers are used as the solidifying agent absorbing layer as in the above-mentioned embodiment, it is possible to obtain a reliable water-impermeable material with good workability while maintaining cost advantages. has advantages.

なお、前記実施例では廃棄物tべVット化して収容した
が、本発明はそのような4t)に限らず廃棄物をベレッ
ト化せず、粉体化後、水ガラスと混練して同様に固化し
てもよく、このようなものでも耐水性の高い固化体か得
られる。
In the above embodiments, the waste was made into t-vets and stored, but the present invention is not limited to such 4 t-sized wastes, but the waste is not made into pellets, but after being pulverized, it is kneaded with water glass and stored in the same way. It may be solidified into a solidified material with high water resistance.

tた、本発明は同化層として、有機材、無機材な問わず
実施できることは勿論である。
It goes without saying that the present invention can be implemented using any organic or inorganic material as the assimilation layer.

以上のように、本発明によれば、使用実績のめるケイ酸
アルカリat等の、ポーラス性固化剤を用いて、耐水性
のある経済性に優れた同化体を得ることができ、これに
よって、放射性廃棄物の同化体に対する相対収容量の拡
大が図れる4のでるる。
As described above, according to the present invention, by using a porous solidifying agent such as alkali silicate at which has been used successfully, it is possible to obtain a water-resistant assimilate with excellent economic efficiency. 4, which can expand the relative capacity of waste to assimilate.

【図面の簡単な説明】[Brief explanation of drawings]

図は本発明の一実施例を示す断面図でめる。 The figure is a sectional view showing one embodiment of the present invention.

Claims (1)

【特許請求の範囲】 1、密對容器内に、放射性g*物を外表部を無機又は有
機材料からなる固化層によシ複榎させて収容してなる放
射性廃棄物の固化処理体にお−て、前記固化層#l!園
部に水不透過性の層を有することを特徴とする放射性廃
棄物の固化処理体。 2、水不透過性の層は、耐水性樹脂、釉、若しくはセラ
ミックであることを特徴とする特許請求の範囲第1項記
載の放射!廃棄物の固化処理体。 3、同化層はガラス繊維であシ、水ガラスを介して、水
不透過性の層及び容器に密着して−ることを特徴とする
特許請求の範囲第1項記載の放射性廃秦−の固化処理体
[Scope of Claims] 1. A radioactive waste solidification treatment body comprising a radioactive substance contained in a sealed container with the outer surface covered with a solidification layer made of an inorganic or organic material. -The solidified layer #l! A solidified body of radioactive waste characterized by having a water-impermeable layer in the garden part. 2. The radiation according to claim 1, wherein the water-impermeable layer is made of water-resistant resin, glaze, or ceramic! Solidification of waste. 3. The assimilation layer is made of glass fiber and is in close contact with the water-impermeable layer and the container through water glass. Solidified body.
JP20710781A 1981-12-23 1981-12-23 Solidified material of radioactive waste Granted JPS58109895A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP20710781A JPS58109895A (en) 1981-12-23 1981-12-23 Solidified material of radioactive waste
EP82111669A EP0082483A1 (en) 1981-12-23 1982-12-16 Solidified product of radioactive waste for disposal thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP20710781A JPS58109895A (en) 1981-12-23 1981-12-23 Solidified material of radioactive waste

Publications (2)

Publication Number Publication Date
JPS58109895A true JPS58109895A (en) 1983-06-30
JPS6137600B2 JPS6137600B2 (en) 1986-08-25

Family

ID=16534310

Family Applications (1)

Application Number Title Priority Date Filing Date
JP20710781A Granted JPS58109895A (en) 1981-12-23 1981-12-23 Solidified material of radioactive waste

Country Status (2)

Country Link
EP (1) EP0082483A1 (en)
JP (1) JPS58109895A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6238399A (en) * 1985-08-13 1987-02-19 三菱マテリアル株式会社 Method of sealing waste
JP2016515915A (en) * 2013-02-14 2016-06-02 アレヴァ・エンセ Glass fiber container and waste incineration method

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5985999A (en) * 1982-11-08 1984-05-18 秩父セメント株式会社 Multiple container and its manufacture
JPS59220695A (en) * 1983-05-30 1984-12-12 株式会社日立製作所 Container for solidifying and processing radioactive waste

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1173998B (en) * 1961-10-10 1964-07-16 Dr Guenter Friese Procedures for the disposal of radioactive waste
US4058479A (en) * 1975-05-12 1977-11-15 Aerojet-General Corporation Filter-lined container for hazardous solids
DE2628286C2 (en) * 1976-06-24 1986-04-10 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process to improve the leaching resistance of bitumen solidification products from radioactive substances
FR2473213B1 (en) * 1980-01-07 1986-03-21 Ecopo LONG-TERM CONTAINMENT DEVICE FOR RADIOACTIVE OR TOXIC WASTE AND ITS MANUFACTURING METHOD

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6238399A (en) * 1985-08-13 1987-02-19 三菱マテリアル株式会社 Method of sealing waste
JP2016515915A (en) * 2013-02-14 2016-06-02 アレヴァ・エンセ Glass fiber container and waste incineration method

Also Published As

Publication number Publication date
JPS6137600B2 (en) 1986-08-25
EP0082483A1 (en) 1983-06-29

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