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JPS6296899A - Method of solidifying radioactive waste - Google Patents

Method of solidifying radioactive waste

Info

Publication number
JPS6296899A
JPS6296899A JP23629985A JP23629985A JPS6296899A JP S6296899 A JPS6296899 A JP S6296899A JP 23629985 A JP23629985 A JP 23629985A JP 23629985 A JP23629985 A JP 23629985A JP S6296899 A JPS6296899 A JP S6296899A
Authority
JP
Japan
Prior art keywords
container
drum
radioactive
radioactive waste
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.)
Pending
Application number
JP23629985A
Other languages
Japanese (ja)
Inventor
督 村上
幸孝 石田
弘毅 木下
真也 清水
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
Mitsubishi Heavy Industries 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 Mitsubishi Atomic Power Industries Inc, Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP23629985A priority Critical patent/JPS6296899A/en
Publication of JPS6296899A publication Critical patent/JPS6296899A/en
Pending legal-status Critical Current

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  • 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】 (産業上の利用分野) 本発明は原子力施設から排出される放射性廃棄物の処理
方法に関し、特に該施設から排出される放射性廃液ばか
りでなく、該施設の■焼、焼却設備からの放射性粉粒体
、ペレット状廃棄物、原子力発電所から排出される空調
用フィルタ、保温材、使用済樹脂、金属パイプ、弁類な
どの放射性固体廃棄物に対する固化方法に関する。
DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a method for treating radioactive waste discharged from a nuclear facility, and in particular to a method for treating radioactive waste discharged from the facility, as well as incineration of the facility, The present invention relates to solidification methods for radioactive solid waste such as radioactive powder and pellet waste from incineration facilities, air conditioning filters, heat insulating materials, used resins, metal pipes, and valves discharged from nuclear power plants.

(従来の技術) 従来、放射性廃液は容器内で固化されて保存していたが
、施設の■焼、焼却設備からの放射性粉粒体、ペレット
状廃棄物、原子力発電所から排出される空調用フィルタ
、保温材、使用済樹脂、金属パイプ、弁類などの放射性
固体廃棄物は、容器中に充填したま\密封されて保存さ
れていた。
(Conventional technology) Conventionally, radioactive waste liquid was solidified and stored in containers, but radioactive powder and granules from facility incineration, incinerator equipment, pelleted waste, and air conditioning waste discharged from nuclear power plants are used for air conditioning. Radioactive solid waste such as filters, heat insulators, used resin, metal pipes, and valves were stored in sealed containers.

(発明が解決しようとする問題点) 放射性固体廃棄物を容器に充填してそのま\密封して保
存してbると容器内に存在する空気によシ放射性固体廃
棄物が酸化すると共に容器自体も酸化し、容器に孔がお
いて放射能が洩れるおそ、れがあった。
(Problem to be Solved by the Invention) If radioactive solid waste is filled into a container and stored in a sealed state, the radioactive solid waste will be oxidized by the air present in the container and the container will be damaged. There was a risk that the container itself would oxidize, creating holes in the container and allowing radioactivity to leak out.

本発明は、特に放射性固体廃棄物の、今後生ずる海中投
棄の場合を考慮し、海中投棄しても放射能が洩れること
がないような放射性廃棄物の処理方法を提供しようとす
るものである。
The present invention is intended to provide a method for disposing of radioactive waste that will not leak radioactivity even if it is dumped in the sea, especially considering the future dumping of radioactive solid waste into the sea.

(問題点を解決するための手段) 本発明は放射性廃棄物を予め容器内に充填した後、該容
器を負圧にし、該容器上部から底部に直接注入物が達す
るように先端を位置させた注入器よシ固化剤を該容器に
注入することを特徴とする放射性廃棄物の固化方法であ
る。
(Means for Solving the Problems) The present invention involves filling a container with radioactive waste in advance, applying negative pressure to the container, and positioning the tip of the container so that the injected material directly reaches the bottom from the top of the container. This method of solidifying radioactive waste is characterized by injecting a solidifying agent into the container using a syringe.

(作用) 放射性固体廃棄物を充填した容器に、そのま\固化剤を
注入する時には、エアベントが必要でちシ、エアベント
接続口に固化剤が付着するばかりでなく、固化剤の注入
に時間がか\るという問題があるが、負圧にしておくこ
とによってエアベントと設置が不要になるばかシでなく
、固化剤の注入が短時間ですむ。又、固化剤を容器上部
から散布するようにして注入すると、内容物が固体廃棄
物であるので、注入された固化剤はこれに衝突して左右
に拡がり十分底部近くにある固体廃棄物まで浸透せず、
完全に固化剤で被覆されない固体廃棄物が存在するとと
くなるばかシでなく、空隙が多く残存することになり、
空隙に残存する空気によって竣化が進行する可能性があ
るが、固化剤を底部よシ順次上方に注入できるようにし
たため、このような欠点が解消しうる。
(Function) When directly injecting solidification agent into a container filled with radioactive solid waste, an air vent is required. Not only will the solidification agent adhere to the air vent connection port, but it will also take time to inject the solidification agent. Although there is a problem of heating, by keeping the pressure negative, there is no need for an air vent and installation, and the injection of the solidifying agent can be done in a short time. Also, if the solidifying agent is sprayed from the top of the container and injected, since the contents are solid waste, the injected solidifying agent will collide with the solid waste and spread from side to side, sufficiently penetrating into the solid waste near the bottom. Without,
This is not a problem if there is solid waste that is not completely covered with the solidifying agent, but many voids will remain.
Although there is a possibility that the solidification progresses due to the air remaining in the voids, this drawback can be overcome by making it possible to inject the solidifying agent from the bottom upwards.

(実施例) 以下、本発明の一具体例を、第1図〜第3図によシ、■
焼、焼却設備からの放射性ペレット生成物(以下、単に
生成物という)を固化する場合について説明する。第1
図はその概略フロー、第2図はドラムの構造、第3図は
ドラムの注入器ヘッダの詳細を説明する図である。
(Example) Hereinafter, a specific example of the present invention will be described with reference to FIGS. 1 to 3.
A case will be described in which a radioactive pellet product (hereinafter simply referred to as a product) from an incineration facility is solidified. 1st
The figure is a schematic flowchart, FIG. 2 is a diagram illustrating the structure of the drum, and FIG. 3 is a diagram explaining details of the syringe header of the drum.

生成物2を充填するドラム1は、その中央に固化剤(セ
メントミルク)を注入するための注入器3を設置したも
のを用いる。この注入器3の出口端はドラム1の底部近
くになるように設定されておシ、その形状を第2図に示
す。
The drum 1 to be filled with the product 2 is equipped with a syringe 3 in the center for injecting a solidifying agent (cement milk). The outlet end of this syringe 3 is set near the bottom of the drum 1, and its shape is shown in FIG.

生成物2のドラム缶1内への充填は、同化剤注入位置の
上流設備で行い、その後にドラム台車4を用いて搬入し
、所定の場所に固定する。
The product 2 is filled into the drum 1 at a facility upstream of the assimilate injection position, and then carried in using the drum truck 4 and fixed at a predetermined location.

ドラム缶1上ブタ60口金7から注入ヘッダ5(第2図
参照)を挿入してドラム缶1中夫に固定された注入器3
と接続させる。ドラム缶10口金7と注入ヘッダ5外筒
部先端のつばは、接着ガスケット14(第3図参照)を
介して圧着しておシ、気密性を保つ。
The injection header 5 (see Fig. 2) is inserted through the upper lid 60 of the drum 1 and the cap 7, and the syringe 3 is fixed to the inner shaft of the drum 1.
Connect with. The cap 7 of the drum 10 and the flange at the tip of the outer cylinder of the injection header 5 are pressed together via an adhesive gasket 14 (see FIG. 3) to maintain airtightness.

次に真空弁8及び注入弁9等の開閉状態を確認した後、
真空ポンプ10を起動させる。圧力計11が規定の真空
度(−560■llig)達するまで吸引して真空弁8
を閉じる。
Next, after checking the opening/closing status of the vacuum valve 8, injection valve 9, etc.,
Start the vacuum pump 10. Suction until the pressure gauge 11 reaches the specified degree of vacuum (-560 llig) and then close the vacuum valve 8.
Close.

ベレット詰ドラム缶IKセメントミルク12を注入する
場合は、ミキサ13にて、セメントとミルク水を所定の
割合で混練して、セメントミルク12を製造する。
When injecting pelleted drum IK cement milk 12, cement and milk water are kneaded in a predetermined ratio in mixer 13 to produce cement milk 12.

セメントミルク12の作成量は1バッチ当り約70〜8
0/とし、ドラム缶1(2GC1j)1個の充填に最低
限必要な量とする。
The amount of cement milk 12 made is approximately 70 to 8 per batch.
0/, which is the minimum amount required to fill one drum 1 (2GC1j).

セメントミルク12を注入する場合、注入弁9を開にし
て注入を開始すると圧力計11の指示値が一560sa
Hgから徐々に零(大気圧)の方向に動き始める。圧力
計11指示値の動きが停止した後、注入弁9を閉じるこ
とにより、注入処理は完了する。
When injecting cement milk 12, when the injection valve 9 is opened and injection is started, the indicated value of the pressure gauge 11 is 1560 sa.
From Hg, it gradually begins to move towards zero (atmospheric pressure). After the movement of the indicated value of the pressure gauge 11 has stopped, the injection valve 9 is closed, thereby completing the injection process.

固化剤12の注入が完了したドラム缶1から注入ヘッダ
5を離脱させた後、キャッピング装置によりドラム缶口
金7をキャッピングしてドラム缶1を仮貯蔵室へ搬出す
る。
After the injection header 5 is removed from the drum 1 in which the solidifying agent 12 has been injected, the drum mouthpiece 7 is capped by a capping device and the drum 1 is transported to a temporary storage room.

セメントミルク12を注入した後の各機器及び配管等に
付着しているセメントミルク12は、紙ウェスでふきと
り、要すれば水洗して清浄化する。これら各機器に付着
したセメントミルク12は非放射性物質であり、注入ヘ
ッダ5もドラム缶1内で放射性物質と接触することはほ
とんど無く、紙ウェスでのふきとり作業に被曝対策上特
に問題はない。
After the cement milk 12 is injected, the cement milk 12 adhering to each device, piping, etc. is wiped off with a paper rag and, if necessary, washed with water to clean it. The cement milk 12 attached to each of these devices is a non-radioactive substance, and the injection header 5 hardly comes into contact with radioactive substances in the drum 1, so there is no particular problem in terms of radiation exposure when wiping with paper rags.

(発明の効果) (1)固化剤(セメントミルク等)の注入を容易にし、
良好な固化体が得られる。
(Effects of the invention) (1) Easily inject a solidifying agent (cement milk, etc.),
A good solidified product can be obtained.

(2)エアベント等の装置が不要で、シンプルかつ安価
な固化装置で目的が達成できる。
(2) Devices such as air vents are not required, and the purpose can be achieved with a simple and inexpensive solidification device.

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

第1図は本発明の一実施例の概略フロー、第2図はドラ
ム(容器)の構造、第5図はドラムの注入器ヘッダの詳
細と説明する図である。 復代理人  内 1)  明 復代理人  伝 原 亮 − 復代理人  安 西 篤 夫 第2図
FIG. 1 is a schematic flowchart of an embodiment of the present invention, FIG. 2 is a structure of a drum (container), and FIG. 5 is a diagram illustrating details of a syringe header of the drum. Sub-Agents 1) Meifuku Agent Ryo Hara - Sub-Agent Atsushi Anzai Figure 2

Claims (1)

【特許請求の範囲】[Claims] 放射性廃棄物を予め容器内に充填した後、該容器を負圧
にし、該容器上部から底部に直接注入物が達するように
先端を位置させた注入器より固化剤を該容器に注入する
ことを特徴とする放射性廃棄物の固化方法。
After filling a container with radioactive waste in advance, the container is brought to negative pressure, and the solidifying agent is injected into the container using a syringe whose tip is positioned so that the injected material directly reaches the bottom from the top of the container. A distinctive method of solidifying radioactive waste.
JP23629985A 1985-10-24 1985-10-24 Method of solidifying radioactive waste Pending JPS6296899A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP23629985A JPS6296899A (en) 1985-10-24 1985-10-24 Method of solidifying radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP23629985A JPS6296899A (en) 1985-10-24 1985-10-24 Method of solidifying radioactive waste

Publications (1)

Publication Number Publication Date
JPS6296899A true JPS6296899A (en) 1987-05-06

Family

ID=16998734

Family Applications (1)

Application Number Title Priority Date Filing Date
JP23629985A Pending JPS6296899A (en) 1985-10-24 1985-10-24 Method of solidifying radioactive waste

Country Status (1)

Country Link
JP (1) JPS6296899A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH04106799U (en) * 1991-02-25 1992-09-14 三菱重工業株式会社 Radioactive miscellaneous solid waste solidification processing equipment
WO2003056571A3 (en) * 2001-12-21 2004-06-17 British Nuclear Fuels Plc Treatment of waste products

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH04106799U (en) * 1991-02-25 1992-09-14 三菱重工業株式会社 Radioactive miscellaneous solid waste solidification processing equipment
WO2003056571A3 (en) * 2001-12-21 2004-06-17 British Nuclear Fuels Plc Treatment of waste products
US7445591B2 (en) 2001-12-21 2008-11-04 British Nuclear Fuels Plc Treatment of waste products

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