JPS589100A - Method of making radioactive waste solidified with resin - Google Patents

Method of making radioactive waste solidified with resin

Info

Publication number
JPS589100A
JPS589100A JP10769181A JP10769181A JPS589100A JP S589100 A JPS589100 A JP S589100A JP 10769181 A JP10769181 A JP 10769181A JP 10769181 A JP10769181 A JP 10769181A JP S589100 A JPS589100 A JP S589100A
Authority
JP
Japan
Prior art keywords
thermosetting resin
radioactive waste
resin
curing
container
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
JP10769181A
Other languages
Japanese (ja)
Inventor
進 高橋
和田 幹雄
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP10769181A priority Critical patent/JPS589100A/en
Publication of JPS589100A publication Critical patent/JPS589100A/en
Pending legal-status Critical Current

Links

Landscapes

  • Processing And Handling Of Plastics And Other Materials For Molding In General (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】 本発明は放射性廃棄物の樹脂同化体を製造する方法に関
する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for producing a resin assimilate of radioactive waste.

一般に原子力発電設備等で発生した放射性廃棄物は種々
の地理が加えられたのち、最終的には固化体内に永久的
に封じ込めて海洋投棄尋の処分がなされる.ζの固化体
は従来セメント中に放射性廃棄物を混入して固めたいわ
ゆるセメント固化体やアスファルト中に放射性廃棄物を
混入して固めたいわゆごアスファルト固化体が用いられ
ていえ.とζろで、最近では樹脂中に放射性廃棄物を混
入して固めたいわゆる樹脂同化体が開発されつつある.
仁のような樹脂同化体は放射性廃棄物の封じ込め能力が
大であり、オた放射性廃棄物の減容性にもすぐれている
勢の長所がある.そして、従来このような樹脂固化体を
製造するには、まず未硬化の熱硬化性樹脂に放射性廃棄
物を混入し、次いでζれに重合開始剤、重合促進剤岬の
触媒を添加し、ζれをドラ▲缶勢の容器に充填して常温
で重合硬化させるものであり九。
In general, radioactive waste generated from nuclear power generation facilities, etc. is subjected to various geological processes, and is finally permanently contained in a solidified body and disposed of by dumping in the ocean. Conventionally, the solidified material of ζ is a so-called solidified cement, which is made by mixing radioactive waste into cement and solidified, or a solidified asphalt, which is made by mixing radioactive waste into asphalt and hardened. Recently, so-called resin assimilates, which are made by mixing radioactive waste into resin and solidifying it, are being developed.
Resin assimilates like Jin have the advantage of having a great ability to contain radioactive waste, and are also excellent at reducing the volume of radioactive waste. Conventionally, in order to produce such a solidified resin, radioactive waste is first mixed into an uncured thermosetting resin, then a polymerization initiator and a polymerization accelerator catalyst are added to the ζ layer. This is filled into a can-type container and allowed to polymerize and harden at room temperature.9.

ところで、ζのような本のでは上記容器の封じ込め能力
は無視し、同化体自体の封じ込め能力だけで必要々封じ
込め能力を得るように設計される.ζのため、樹脂同化
体の強度、特にその表面部分の強度が重要視され、たと
えばその表11O強度はl5Ok#la7の圧力に耐え
るように保証されなければならない、この場合、上記*
aをIF閉形OもOとし、この容器内に放射性廃棄物を
混入した熱硬化性樹脂を充填するととO熱硬化性樹脂が
硬化し九のちその表面の強度等を検査することができな
くなる。このため、容器九とえばドラム缶の蓋を取外し
て放射性廃棄物を混入した熱硬化性樹脂を充填し、蓋を
取外したまtζO熱硬化性樹脂を硬化し、硬化完了後に
熱硬化性樹脂の表面の強ml!勢を測定してその強度を
保証し、こののちドラム缶に蓋を取付け、熱硬化性樹脂
OS面と蓋との間の間隙に充填材を充填することが考え
られた。しかし、ζOようなものでは熱硬化性樹脂の表
面が空気と接触するため空気中O酸素によりて熱硬化性
樹脂O1!面部分01!化が遅れる。この丸め、中心部
O熱硬化性樹脂の硬化の進行によル体積が変化し、 *
*化OIl!!面が局部的に凹陥tたは膨出することが
ある。そして、このように表面部分が硬化の完了する前
に変形するとこの表面部分の、強度が低下する不具合を
生じる。
By the way, books like ζ ignore the containment capacity of the container mentioned above and are designed to obtain the necessary containment capacity only from the containment capacity of the assimilate itself. ζ, emphasis is placed on the strength of the resin assimilate, especially the strength of its surface parts, for example its Table 11O strength must be ensured to withstand the pressure of 15Ok#la7, in this case the above *
If a is an IF closed type O and a thermosetting resin mixed with radioactive waste is filled into this container, the thermosetting resin will harden and it will no longer be possible to inspect the strength of its surface. For this purpose, the lid of a container (for example, a drum can) is removed, the thermosetting resin mixed with radioactive waste is filled, the ζO thermosetting resin is cured while the lid is removed, and the surface of the thermosetting resin is cured after curing is completed. Strong ml! One idea was to measure the strength of the drum to ensure its strength, then attach a lid to the drum and fill the gap between the thermosetting resin OS surface and the lid with a filler. However, in the case of ζO, the surface of the thermosetting resin comes into contact with air, so the thermosetting resin O1! Face part 01! development is delayed. Due to this rounding, the volume of the core changes as the thermosetting resin in the center hardens.
*KoIl! ! The surface may be locally depressed or bulged. If the surface portion is deformed before the curing is completed, the strength of the surface portion may be reduced.

本発明は以上の事情にもとすいてなされたもので、その
目的とするとζろは表面部分の強度を低下させずに熱硬
化性樹脂の硬化を完了することができる放射性廃棄物の
樹1irti!iI化体の製造方法を得ることにある。
The present invention was made in view of the above-mentioned circumstances, and its purpose is to create a radioactive waste material that can complete the curing of thermosetting resin without reducing the strength of the surface portion. ! The object of the present invention is to obtain a method for producing an iI compound.

以下本発明を一実施例にしたがうて説明する。The present invention will be explained below based on one embodiment.

まず、第1図に示す如く未硬化O熱硬化性樹脂lに放射
性廃棄物2を混入するとともに重合開始剤、重合促進剤
等の触媒を添加し、仁れをドラム缶等の容器J内に充填
する。そしてこの場合の容@Iは上端が開放され、よっ
て熱硬化性樹脂lの自由表面紘外部に露出している6次
にこの容器jt−第2図に示す如き養生i14に収察す
る。この養生室4は外気と完全に遮断され1そO内部に
は非酸化性ガスたとえば窒素、不活性ガスが流通される
ように構成されている。そして、この養生wi4内は加
熱機構(図示せず)によって高温たとえば30℃以上に
維持され、また高周波加熱装置jFcよって上記の容器
Jを加熱するヒとかで龜るように構成されている。
First, as shown in Figure 1, radioactive waste 2 is mixed into uncured O thermosetting resin L, catalysts such as polymerization initiators and polymerization accelerators are added, and the core is filled into a container J such as a drum. do. In this case, the container @I is opened at the upper end, so that the free surface of the thermosetting resin I is exposed to the outside.Then, this container jt is collected in a curing i14 as shown in FIG. The curing chamber 4 is completely isolated from the outside air and is configured so that a non-oxidizing gas such as nitrogen or an inert gas can flow inside the curing chamber 4. The inside of this curing wi4 is maintained at a high temperature, for example, 30° C. or higher, by a heating mechanism (not shown), and is also configured to be heated by a high-frequency heating device jFc that heats the container J.

そして、ヒの養生室4内の温度および容器1の温IIL
#i温度検出@#、7によって検出され、これら温度検
出@g、yからの信号状制御装置aに送られて温度の制
御、監視がなされるように構成されていゐ、そして、上
記容器Iは仁の養生室4内に一定時間収容され、熱硬化
性樹脂が硬化して容I11と一体化した軛脂固化体りが
形成される。そして、この場合、この養生室4内紘非酸
化性雰囲気九とえば窒素ガス雰囲気に表うているので、
熱硬化性樹脂lの自由表面に酸素−接触すること#iな
く、この自I!1表面付近の硬化−fi凪書されること
妹ない、よりて熱硬化性樹脂lll1そ0@面部分およ
び内部でO硬化が等しく進行する。よって硬化が進行し
て内部の体積が羨りてもこの時点では表面付近もすでに
硬化が進行しているのでこの表面近傍が局部的に変形し
てしt5ことがなく、表面部分の強度低下を招くことが
ない、tた、ヒの一夾施例轄養生宣4内は高温に維持さ
れ、を大容器1自体も加熱されるので熱硬化性樹脂10
表面近傍O硬化が一層促進されるので表面近傍の局部的
錠形が一層効果的に防止される。そして硬化が完了した
らこの容器1を養生114から取り出し、自由表面の強
度、状態を検査し、この樹脂同化体Jの品質を保証する
。そして次に第3図に示す如く容器1に蓋体1#を取付
け、仁の蓋体1#に設けられた充填口11から樹脂固化
体!の表面上蓋体10との間の隙間にセメントモルタ羨
勢の充填材12を充填する。
Then, the temperature inside the curing chamber 4 and the temperature IIL of the container 1 are determined.
The temperature is detected by #i temperature detection @#, 7, and the signal from these temperature detection @g, y is sent to a control device a for temperature control and monitoring. is stored in the grain curing chamber 4 for a certain period of time, and the thermosetting resin is cured to form a solidified grain that is integrated with the grain I11. In this case, since the non-oxidizing atmosphere inside the curing chamber 4 is represented by, for example, a nitrogen gas atmosphere,
Without any oxygen contact with the free surface of the thermosetting resin, this self! Curing in the vicinity of the surface of the thermosetting resin does not occur at the same rate; therefore, the O curing progresses equally in the surface area and inside the thermosetting resin. Therefore, even if hardening progresses and the internal volume increases, at this point the hardening has already progressed near the surface, so there will be no local deformation t5 in the vicinity of the surface, which will prevent the strength of the surface area from decreasing. The inside of the curing container 4 is maintained at a high temperature, and the large container 1 itself is also heated, so the thermosetting resin 10
Since the O curing near the surface is further promoted, localized tablet formation near the surface is more effectively prevented. After curing is completed, the container 1 is taken out from the curing 114 and the strength and condition of the free surface are inspected to ensure the quality of the resin assimilate J. Then, as shown in FIG. 3, the lid 1# is attached to the container 1, and the solidified resin is poured from the filling port 11 provided in the lid 1#. A filler material 12 similar to cement mortar is filled into the gap between the top surface and the lid body 10.

なお、本発明は上記の一実施例には限定されない・ たとえば養生家内は必らずし4高温雰囲気にしなくても
よい。
Note that the present invention is not limited to the above-mentioned embodiment. For example, the inside of the curing house does not necessarily have to be in a high-temperature atmosphere.

また、との養生室内に流通するガスは必らずしも窒素、
不活性ガス等に限らず、要は熱硬化性樹脂の硬化を阻害
しないような非酸化性のガスであればよい。
In addition, the gas flowing in the curing chamber is not necessarily nitrogen,
The gas is not limited to an inert gas, but any non-oxidizing gas that does not inhibit the curing of the thermosetting resin may be used.

上述の如く本発明状放射性廃棄物を未硬化の熱硬化性樹
脂に混入し、この熱硬化性樹脂を非酸化性雰囲気内で硬
化させるものである。よってこの熱硬化性樹脂の表面近
傍の硬化が遅れるようなことがなく、体積の変化によっ
てこの表両近傍が硬化途中で変形して強度の低下を招く
ことがない等その効果は大である。
As described above, the radioactive waste of the present invention is mixed into an uncured thermosetting resin, and the thermosetting resin is cured in a non-oxidizing atmosphere. Therefore, there is no delay in the curing of the thermosetting resin near the surface, and there is no possibility that the areas near the surface will be deformed during curing due to changes in volume, resulting in a decrease in strength.

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

図は本発明の一実施例の工程を説明する図でありて、第
1図は容器内に未硬化の熱硬化性樹脂を充填した状態の
縦断面図、第2図は容器を費生宸内に収容した状態の縦
断面図、第3図は容器に蓋体を取付けた状態の縦断面図
である。 1−熱硬化性樹脂、2・−放射性廃棄物、1−容器、4
−養生室、1#−蓋体、12−充填材・出願人代理人 
 弁理士 鈴 江 武 彦第1図 第31 9 ノ1 ゝ−2 3
The figures are diagrams illustrating the steps of an embodiment of the present invention, in which Figure 1 is a vertical cross-sectional view of a container filled with uncured thermosetting resin, and Figure 2 is a vertical cross-sectional view of a container filled with uncured thermosetting resin. FIG. 3 is a vertical cross-sectional view of the container with the lid attached. 1-thermosetting resin, 2.-radioactive waste, 1-container, 4
-Curing room, 1#-Lid body, 12-Filling material/Applicant's representative
Patent Attorney Takehiko Suzue Figure 1 Figure 31 9 No. 1 ゝ-2 3

Claims (2)

【特許請求の範囲】[Claims] (1)  放射性廃棄物を未硬化の熱硬化性樹脂に混合
する工種と、この放射性廃棄物を混合した熱硬化性樹脂
を非酸化性雰囲気内で硬化させるl1とを具備したとと
を特徴とする放射性廃集物O樹脂園化体製造方法。
(1) It is characterized by comprising a process for mixing radioactive waste into an uncured thermosetting resin, and a process for curing the thermosetting resin mixed with the radioactive waste in a non-oxidizing atmosphere. A method for producing a radioactive waste O resin garden.
(2)  前記放射性廃棄物を混合し良熱硬化性樹脂を
非酸化性雰囲気で硬化させる際にこの熱硬化性樹脂を周
卸から加熱することを特徴とする特許 O樹脂固化体製造方法。
(2) A patented method for producing a solidified O resin, characterized in that when the radioactive waste is mixed and the thermosetting resin is cured in a non-oxidizing atmosphere, the thermosetting resin is heated from the outside.
JP10769181A 1981-07-10 1981-07-10 Method of making radioactive waste solidified with resin Pending JPS589100A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP10769181A JPS589100A (en) 1981-07-10 1981-07-10 Method of making radioactive waste solidified with resin

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP10769181A JPS589100A (en) 1981-07-10 1981-07-10 Method of making radioactive waste solidified with resin

Publications (1)

Publication Number Publication Date
JPS589100A true JPS589100A (en) 1983-01-19

Family

ID=14465512

Family Applications (1)

Application Number Title Priority Date Filing Date
JP10769181A Pending JPS589100A (en) 1981-07-10 1981-07-10 Method of making radioactive waste solidified with resin

Country Status (1)

Country Link
JP (1) JPS589100A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6324628A (en) * 1986-07-16 1988-02-02 Mitsubishi Electric Corp Manufacture of semiconductor device and equipment therefor

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5658000A (en) * 1979-10-16 1981-05-20 Nippon Atomic Ind Group Co System for solidifying radioactive waste with plastics

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5658000A (en) * 1979-10-16 1981-05-20 Nippon Atomic Ind Group Co System for solidifying radioactive waste with plastics

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6324628A (en) * 1986-07-16 1988-02-02 Mitsubishi Electric Corp Manufacture of semiconductor device and equipment therefor

Similar Documents

Publication Publication Date Title
US4174293A (en) Process for disposal of aqueous solutions containing radioactive isotopes
JPH03146310A (en) Concrete manufacturing method
WO1989000753A1 (en) Method and apparatus for solidifying radioactive waste
JPS589100A (en) Method of making radioactive waste solidified with resin
EP2620231B1 (en) Inorganic waste solid shield structure and method for manufacturing inorganic waste solid shield structure
JPS63195598A (en) Solidifying processor for radioactive waste
JPH0475966B2 (en)
JPS61178698A (en) Method for curing water glass for radioactive waste treatment
JPH032280B2 (en)
JPS62151799A (en) Transport-treating vessel having improved shock resistance and manufacture thereof
JPS63227330A (en) Manufacture of concrete product having water permeability
JPS5912999B2 (en) How to dispose of radioactive waste
JPS611443A (en) Manufacturing method of refractory mold
JPH03183507A (en) Method for producing concrete with high moisture content
JPH03150499A (en) Solidification of radioactive waste
JPS6236052A (en) Radiation-shielding sound-insulating concrete
JPS5951386B2 (en) Method for forming filling structure of filling material in sliding nozzle hole
JPS60154198A (en) How to create solidified radioactive waste
JPH0616389Y2 (en) lid
JPS6137600B2 (en)
JPH0648477Y2 (en) Storage container for radioactive waste
JPH073000U (en) Treatment container for radioactive waste
JPH0453716A (en) Casting material for simplified resin mold
JPS6238399A (en) Method of sealing waste
JPS637498A (en) Concrete pouring method for steel concrete composite segment