JPS59116100A - Method of sealing radioactive waste by artificial - Google Patents
Method of sealing radioactive waste by artificialInfo
- Publication number
- JPS59116100A JPS59116100A JP23125082A JP23125082A JPS59116100A JP S59116100 A JPS59116100 A JP S59116100A JP 23125082 A JP23125082 A JP 23125082A JP 23125082 A JP23125082 A JP 23125082A JP S59116100 A JPS59116100 A JP S59116100A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- artificial
- waste
- rock
- hardened
- 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
Links
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】
との発明は熱水条件下で放射性廃棄物をケイ酸塩粉末と
共に硬化、岩石化せしめ、環境を汚染することなしに土
中あるいは海中に投入廃棄処理せしめることができるよ
うにする人造岩石にまる放射性廃棄物の封じ込め方法に
関するものである。[Detailed Description of the Invention] The invention enables radioactive waste to be hardened and rocked together with silicate powder under hydrothermal conditions, and then disposed of by being thrown into the ground or the sea without polluting the environment. This concerns a method for containing radioactive waste contained in artificial rocks.
従来放射性廃棄物処理はコンクリートあるいはガラスに
よる同化封じ込めによって海洋底、土中に投入または埋
没処理する形として実施、あるいは実施が検討されてき
た。しかしセメントによる硬化体であるコンクリートは
反応の過渡的々ものであシ、反応が完結すると硬化体は
崩壊する。すなわちコンクリートには寿命があり５０〜
１５０年といわれている。したがってコンクリート以上
の長寿命の放射性同位元素を含む廃棄物の処理について
は環境を汚染する危険性が高い。！、たガラスと共に高
温で溶融して封じ込める方法に関しては、ガラスの結晶
化と放射線による劣化によってガラスの強度が低下する
ばかりでなく、溶融封じ込めの際に高温下で放射性物質
が逃散する恐れがある等問題点が多〈実施されていない
。Conventionally, radioactive waste treatment has been carried out, or considered, by assimilation containment using concrete or glass, which involves dumping or burying the waste on the ocean floor or in the soil. However, concrete, which is a hardened body made of cement, undergoes only a transient reaction, and when the reaction is completed, the hardened body collapses. In other words, concrete has a lifespan of 50~
It is said to be 150 years old. Therefore, there is a high risk of environmental pollution when processing waste containing radioactive isotopes that have a longer lifespan than concrete. ! Regarding the method of sealing the glass by melting it at high temperatures, there is a risk that not only the strength of the glass will decrease due to crystallization of the glass and deterioration due to radiation, but also that radioactive substances may escape at high temperatures during the melting and containment. There are many problems (not implemented).
この発明はケイ酸塩（シリカ、ケイ酸カルシウム、ゼオ
ライト、長石、粘土等を含む）粉末を熱水条件下で放射
性廃棄物と共に硬化せしめ、岩石状のものとし、土中あ
るいは深海中で溶出あるいは破壊の生じない形で封じ込
めることによって安全に放射性廃棄物を処理することを
目的とする。In this invention, silicate powder (including silica, calcium silicate, zeolite, feldspar, clay, etc.) is hardened together with radioactive waste under hydrothermal conditions to form a rock-like material that can be dissolved in the soil or deep sea. The purpose is to safely dispose of radioactive waste by containing it in a non-destructive manner.
この発明の詳細な説明する。放射性廃棄物はその形態と
放射能強度によって３つのランクに分けられる。第１の
ランクは、使用済核燃料に由来する高放射性廃棄物であ
る。多種多様の核種を含み、その放射能も高く、発熱の
危険性もある。この踵の廃棄物の処理をこの発明による
方法で行えば以下のような手順になる。すなわちケイ石
あるいは白土のようなケイ酸塩粉末を放射性廃棄物と混
合する。これをアルカリ水溶液でねシ合わせ、図面に示
した熱水圧縮整形器のシリンダ１の反応室４に押し込む
。ついでピストン２．３によって圧縮しながら外部から
加熱する。２５０’ ｃ 、３０分間の反応で４５０〜
５００に／ｄの耐圧強度の硬化体ベレットが得られる。This invention will be explained in detail. Radioactive waste is divided into three ranks depending on its form and radioactivity intensity. The first rank is highly radioactive waste derived from spent nuclear fuel. It contains a wide variety of nuclides, is highly radioactive, and poses a risk of generating heat. If this heel waste is disposed of using the method according to the present invention, the procedure will be as follows. That is, silicate powder, such as silica or clay, is mixed with radioactive waste. This is combined with an alkaline aqueous solution and pushed into the reaction chamber 4 of the cylinder 1 of the hot water compression shaping machine shown in the drawing. It is then heated externally while being compressed by the piston 2.3. 250'C, 450~ for 30 minutes reaction
A cured pellet having a compressive strength of 500/d is obtained.
こうしてできたベレットをアルカリ水溶液でねり合わせ
たケイ石末で包み、これをさらに大型の熱水圧縮整形器
で整形硬化させる。The pellet thus made is wrapped in silica powder kneaded with an alkaline aqueous solution, and then shaped and hardened using a large hot water compression shaping machine.
この整形体の外部をさらにコンクリートで包み、ピンチ
をまいて土中めるいは深海に投入処理する。The outside of this shaped body is further wrapped in concrete, sprinkled with concrete, and placed into the ground or into the deep sea.
第２のランクで示される原−力発電等の原子炉の１次冷
却水等に含まれる放射性物質については、ゼオライトに
吸着させる方法があるが、本発明ではこの吸着済みのゼ
オライトを図面で示した熱水圧縮整形器で第１の場合と
同様に硬化させる。ついでこれをケイ石粉末と消石灰の
混合粉末を少量のアルカリ水でねったもので包み込み大
型熱水圧縮整形器で硬化整形する。この場合の外部硬化
体は不溶性ケイ酸カルシウム（トバモライト）トナり内
部を保護する。There is a method of adsorbing radioactive substances in the primary cooling water of nuclear reactors, etc. in nuclear power plants, etc., which is shown in the second rank, to zeolite, but in the present invention, this adsorbed zeolite is shown in the drawing. The mixture is cured in the same manner as in the first case using a hot water compression shaping machine. Next, this is wrapped in a mixed powder of silica powder and slaked lime mixed with a small amount of alkaline water, and hardened and shaped using a large hot water compression shaping machine. The outer hardened body in this case protects the interior of the insoluble calcium silicate (tobermorite) toner.
第３のランクで示される場合は、汚染除去等の作業によ
るものや放射線取扱施設からの排気排水を起源とするよ
うな低レベルの放射性廃棄物で、これらの処理に関して
は一般に燃焼による灰を処理することになる。ボロ切れ
、紙類の燃焼灰はシリカ、アルミナ、カルシアを主成分
とするためにアルカリ水溶液でねシ合わせば図面に示し
た熱水、圧縮整形器で容易に硬化整形することができる
。The third rank refers to low-level radioactive waste, such as those originating from decontamination work or exhaust wastewater from radiation handling facilities, and the treatment of these wastes is generally the ash from combustion. I will do it. Combustion ash from rags and paper mainly consists of silica, alumina, and calcia, so if it is mixed with an alkaline aqueous solution, it can be easily hardened and shaped using the hot water and compression shaping machine shown in the drawing.
これにさらにケイ石消石灰をアルカリ水でねったものて
包み込み第２のレベルの場合と同様に処理することがで
きる。In addition, slaked silica lime mixed with alkaline water can be wrapped and treated in the same manner as in the second level.
第１、第２、第３のどのランクの放射性廃棄物の場合も
自然界に存在する強固で安定な岩石２様のもので３重に
固めておシ、それらの鉱物上の分析では、チャートやト
バモライトであった。古代文明の遺跡で現代になお存続
するものは大理石等の石材である。チャート、トバモラ
イトは天然の大理石や石灰岩と比較してよシ大きな機械
的強度、耐化学強度（風化し難さ）を有しているので、
数千年を経過してなお存続する大理石以上の安定な存続
ｆｉｆ保証できる。またガラス融解封入法等に比較して
本発明による硬化体はいわゆる多結晶体で多くの粒界を
有しており放射性物質の捕獲能力が太き−く、かつ強度
を下げない。In the case of radioactive waste of any rank 1, 2, or 3, it is triple-solidified with strong and stable rocks that exist in nature. It was tobermorite. The remains of ancient civilizations that still exist today are stone materials such as marble. Chert and tobermorite have greater mechanical strength and chemical resistance (difficulty weathering) compared to natural marble and limestone.
We can guarantee a more stable existence than marble, which has survived for thousands of years. Furthermore, compared to the glass melting and encapsulation method, the cured product according to the present invention is a so-called polycrystalline material having many grain boundaries, has a greater ability to capture radioactive substances, and does not reduce its strength.
この発明は以上説明したように熱水条件を利用した人造
岩石中に放射性廃棄物を閉じ込め、地中あるいは海洋底
に安全に投棄処理し、かつ放射能強度によって岩石種を
選べるため、どのような放射能強度の廃棄物にも適用で
きる点に特徴がある。As explained above, this invention confines radioactive waste in artificial rocks using hydrothermal conditions, safely dumps them underground or on the ocean floor, and allows rock types to be selected depending on radioactivity intensity. The feature is that it can also be applied to radioactive waste.
原子力発電所で代表される原子力施設や関連する放射性
物質取扱施設は廃棄物処理が困難な為に建設を抑制せざ
るを得ないという現状である。本発明の実用化は石油の
代替エネルギーである原子力エネルギー開発のために大
きな意味を持つものであシ社会的効果が大きいものであ
る。The current situation is that the construction of nuclear power facilities, such as nuclear power plants, and related radioactive material handling facilities has to be curtailed due to the difficulty of waste disposal. The practical application of the present invention is of great significance for the development of nuclear energy, which is an alternative energy to petroleum, and has great social effects.
【図面の簡単な説明】
図面は本発明に使用した熱水圧縮整形器の断面溝造園で
ある。
１・・・ シリンダ、２．３・・・・・圧縮ピストン、
４・・・・反応室。[BRIEF DESCRIPTION OF THE DRAWINGS] The drawing shows the cross-sectional groove landscaping of the hot water compression shaping device used in the present invention. 1... Cylinder, 2.3... Compression piston,
4...Reaction chamber.
Claims (3)
硬化、岩石状とすることを特徴とする人造岩石による放
射性廃棄物の封じ込め方法。(1) A method for containing radioactive waste using artificial rock, which is characterized by hardening radioactive waste together with silicate powder under hydrothermal conditions to form a rock.
応室を形成して、該圧縮ピストンで圧縮しながら外部か
ら加熱する熱水圧縮整形器で放射性廃棄物をケイ酸塩粉
末と共に硬化、岩石状とする特許請求の範囲第１項記載
の人造岩石による放射性廃棄物の封じ込め方法。(2) Compression pistons are inserted into both ends of the cylinder to form a reaction chamber, and the radioactive waste is hardened together with silicate powder using a hot water compression shaping machine that heats it from the outside while being compressed by the compression piston. A method for containing radioactive waste using artificial rock according to claim 1.
をさらにアルカリ水溶液でねり合わせ、熱水圧縮整形器
で硬化、岩石状とする特許請求の範囲第２項記載の人造
岩石による放射性廃棄物の封じ込め方法。(3) Radioactivity caused by the artificial rock described in claim 2, in which radioactive waste and silicate powder are mixed, the mixture is further kneaded with an alkaline aqueous solution, and hardened in a hot water compression shaping machine to form a rock shape. Waste containment methods.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP23125082A JPS59116100A (en) | 1982-12-23 | 1982-12-23 | Method of sealing radioactive waste by artificial |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP23125082A JPS59116100A (en) | 1982-12-23 | 1982-12-23 | Method of sealing radioactive waste by artificial |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59116100A true JPS59116100A (en) | 1984-07-04 |
Family
ID=16920669
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP23125082A Pending JPS59116100A (en) | 1982-12-23 | 1982-12-23 | Method of sealing radioactive waste by artificial |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59116100A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6178483A (en) * | 1984-09-25 | 1986-04-22 | Mitsui Eng & Shipbuild Co Ltd | Solidification of incineration ash |
| JPS61216000A (en) * | 1984-12-21 | 1986-09-25 | ソシエテ ジエネラル プ−ル レ テクニ−ク ヌ−ベル エス．ジエ．エヌ． | Method of packaging noxious product container |
| JPS61260198A (en) * | 1985-05-14 | 1986-11-18 | 株式会社新来島どっく | Hydrothermal solidifying treating method of inorganic group waste |
| JPS61274299A (en) * | 1985-05-30 | 1986-12-04 | 三菱重工業株式会社 | Solidification of radioactive waste |
| JPS6242100U (en) * | 1985-08-30 | 1987-03-13 | ||
| JP2018112554A (en) * | 2018-02-07 | 2018-07-19 | Ｎｅｘｔ Ｉｎｎｏｖａｔｉｏｎ合同会社 | Crustal composition manufacturing method |
-
1982
- 1982-12-23 JP JP23125082A patent/JPS59116100A/en active Pending
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6178483A (en) * | 1984-09-25 | 1986-04-22 | Mitsui Eng & Shipbuild Co Ltd | Solidification of incineration ash |
| JPH0460712B2 (en) * | 1984-09-25 | 1992-09-28 | Mitsui Shipbuilding Eng | |
| JPS61216000A (en) * | 1984-12-21 | 1986-09-25 | ソシエテ ジエネラル プ−ル レ テクニ−ク ヌ−ベル エス．ジエ．エヌ． | Method of packaging noxious product container |
| JPS61260198A (en) * | 1985-05-14 | 1986-11-18 | 株式会社新来島どっく | Hydrothermal solidifying treating method of inorganic group waste |
| JPS61274299A (en) * | 1985-05-30 | 1986-12-04 | 三菱重工業株式会社 | Solidification of radioactive waste |
| JPS6242100U (en) * | 1985-08-30 | 1987-03-13 | ||
| JP2018112554A (en) * | 2018-02-07 | 2018-07-19 | Ｎｅｘｔ Ｉｎｎｏｖａｔｉｏｎ合同会社 | Crustal composition manufacturing method |
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