JPS6155079B2 - - Google Patents

Info

Publication number
JPS6155079B2
JPS6155079B2 JP342577A JP342577A JPS6155079B2 JP S6155079 B2 JPS6155079 B2 JP S6155079B2 JP 342577 A JP342577 A JP 342577A JP 342577 A JP342577 A JP 342577A JP S6155079 B2 JPS6155079 B2 JP S6155079B2
Authority
JP
Japan
Prior art keywords
sulfuric acid
hydrogen peroxide
radioactive waste
organic matter
radioactive
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.)
Expired
Application number
JP342577A
Other languages
Japanese (ja)
Other versions
JPS5388500A (en
Inventor
Hiroshi Tanaka
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.)
JGC Corp
Original Assignee
JGC Corp
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 JGC Corp filed Critical JGC Corp
Priority to JP342577A priority Critical patent/JPS5388500A/en
Publication of JPS5388500A publication Critical patent/JPS5388500A/en
Publication of JPS6155079B2 publication Critical patent/JPS6155079B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies
    • Y02W30/62Plastics recycling; Rubber recycling

Description

【発明の詳細な説明】 この発明は原子力発電所などから発生する放射
性廃棄物の容量を減少させる処理方法に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a treatment method for reducing the volume of radioactive waste generated from nuclear power plants and the like.

従来、原子力発電所などの運転により種々の放
射性核種を含む廃水が発生するので、この廃水を
イオン交換樹脂処理、濾過処理あるいは蒸発処理
している。これらの処理で発生する廃イオン交換
樹脂、濾過助剤あるいは蒸発残渣または他の施設
から発生する放射性廃棄物は非常に危険なため、
これらをセメントやアスフアルトと混合してドラ
ム缶中で固化させ、これをそのまま所定の場所に
保管するようにしている。しかしながら、これら
の放射性廃棄物の量は増大する一方であり、その
保管場所の確保および安全性の確保が重大な問題
となつている。したがつて、放射性廃棄物を固化
処理するに際して、固化したものの容量をできる
だけ最少に留めることに重大な関心が払われてき
た。たとえば、廃イオン交換樹脂などを硫酸―硝
酸の混酸を用いて減容する方法がある。しかし、
この場合、硫酸および硝酸を使用するため、次に
示すような CmHn+n/2H2SO4→ nH2O+n/2SO2+mC C +2H2SO4 →2H2O+2SO4+CO2 3C +4HNO3 →4NO+2H2O+3CO2 などの反応が起り、その結果、好ましくないSOx
やNOxが生成する。そこで、これらのSOxやNOx
を硫酸や硝酸として回収するための酸化塔および
吸収塔が必要となり、したがつて回収工程が複難
になるとともに再生回収用液として濃硫酸、濃硝
酸などを用いるので、安全性と設備費などにかな
りの投資を必要とする。また、硝酸を使用するた
めニトロ化合物の副生による爆発の防止について
も対策を講じなければならない。
Conventionally, the operation of nuclear power plants generates wastewater containing various radionuclides, and this wastewater is treated with ion exchange resins, filtered, or evaporated. Waste ion exchange resins, filter aids, or evaporation residues generated in these processes, as well as radioactive wastes generated from other facilities, are extremely dangerous.
These are mixed with cement or asphalt, solidified in drums, and then stored in a designated location. However, the amount of these radioactive wastes continues to increase, and securing storage space and ensuring safety have become serious problems. Therefore, when solidifying radioactive waste, great attention has been paid to minimizing the volume of solidified waste as much as possible. For example, there is a method of reducing the volume of waste ion exchange resin using a mixed acid of sulfuric acid and nitric acid. but,
In this case, since sulfuric acid and nitric acid are used, the following CmHn+n/2H 2 SO 4 → nH 2 O+n/2SO 2 +mC C +2H 2 SO 4 →2H 2 O+2SO 4 +CO 2 3C +4HNO 3 →4NO+2H 2 O+3CO 2 As a result, undesirable SOx
and NOx are generated. Therefore, these SOx and NOx
An oxidation tower and an absorption tower are required to recover the sulfuric acid and nitric acid, which makes the recovery process complicated and requires the use of concentrated sulfuric acid, concentrated nitric acid, etc. as the liquid for regeneration and recovery, which increases safety and equipment costs. requires considerable investment. Additionally, since nitric acid is used, measures must be taken to prevent explosions due to by-products of nitro compounds.

本発明の目的は、厳重な処理及び保管を必要と
する放射性廃有機物を減容処理するに際し、従来
の焼却法によるSOxの発生や硝酸法によるNOxの
発生の恐れが全くなく、そしてこれらの回収工程
も必要とせず、しかも反応制御が容易で装置の腐
食の問題もないプロセス的、装置的及び経済的に
有利な放射性廃有機物の減容処理方法を提供する
ことにある。
The purpose of the present invention is to reduce the volume of radioactive waste organic matter that requires strict treatment and storage, without any fear of generating SOx due to conventional incineration methods or NOx due to nitric acid methods, and to recover these materials. It is an object of the present invention to provide a volume reduction treatment method for radioactive waste organic matter that does not require any steps, is easy to control the reaction, and is advantageous in terms of process, equipment, and economy.

即ち、本発明の方法は、濃硫酸に放射性廃有機
物を仕込み、150〜300℃の温度に維持しつつ、過
酸化水素を添加して放射性廃有機物を分解するこ
とを特徴とするものである。
That is, the method of the present invention is characterized by charging concentrated sulfuric acid with radioactive waste organic matter, and decomposing the radioactive waste organic matter by adding hydrogen peroxide while maintaining the temperature at 150 to 300°C.

この発明において減容処理の対象となる放射性
廃有機物は、原子力施設などから発生する種々の
放射性核種を含む廃水を処理する過程で排出され
るイオン交換樹脂、濾過助剤などのほか、放射能
で汚染された衣服、材料などであり、これらの放
射性有機物は水分を含んでいるものでもよく、ま
た重金属を含んでいてもよい。
In this invention, the radioactive waste organic materials that are subject to volume reduction treatment include ion exchange resins, filter aids, etc. discharged during the process of treating wastewater containing various radionuclides generated from nuclear facilities, etc., as well as radioactive organic materials. Contaminated clothing, materials, etc. These radioactive organic substances may contain moisture or may contain heavy metals.

次にこの発明を添付の図面にもとづいてさらに
詳しく説明する。
Next, the present invention will be explained in more detail based on the accompanying drawings.

図面は本発明実施装置の1例を示したもので、
図において、1は放射性廃有機物タンク、4は撹
拌型反応器である。放射性廃有機物は、タンク1
から二重ダンパを有するホツパ2を経てその下部
に取付けられたフイーダ3によつて撹拌型反応器
4に供給される。撹拌型反応器4はガラスまたは
耐酸性の金属材料で作られており、その中には予
め150〜300℃に維持した濃硫酸が収容されてい
る。撹拌型反応器4に供給された放射性廃有機物
は加熱濃硫酸によつてその一部が分解されるが、
これにタンク5から過酸化水素水溶液を滴下して
添加することにより分解が速かに進む。すなわ
ち、過酸化水素が分解して生じた酸素によつて分
解が促進され、そのため放射性廃有機物は炭酸ガ
スと水蒸気とに分解される。この場合、150℃以
上の温度で分解するので不安定な過酸化物の生成
はなく安全な操作ができ、さらに濃硫酸の蒸発を
抑制するために分解温度は300℃以下とするのが
好ましい。また過酸化水素の添加量は、加熱濃硫
酸中の放射性廃有機物がすべて分解されるまで、
すなわち加熱濃硫酸が透明になるまでとするのが
よい。
The drawing shows an example of the device implementing the present invention.
In the figure, 1 is a radioactive waste organic matter tank, and 4 is a stirred reactor. Radioactive waste organic matter is stored in tank 1.
From there, it is fed to a stirred reactor 4 via a hopper 2 having a double damper and a feeder 3 attached at the bottom of the hopper 2. The stirred reactor 4 is made of glass or acid-resistant metal material, and contains concentrated sulfuric acid previously maintained at 150 to 300°C. A portion of the radioactive waste organic matter supplied to the stirring reactor 4 is decomposed by heated concentrated sulfuric acid;
By adding a hydrogen peroxide aqueous solution dropwise from tank 5 to this, decomposition proceeds rapidly. That is, the decomposition is promoted by the oxygen produced by the decomposition of hydrogen peroxide, and therefore the radioactive waste organic matter is decomposed into carbon dioxide gas and water vapor. In this case, since the decomposition occurs at a temperature of 150° C. or higher, there is no generation of unstable peroxides and safe operation is possible, and the decomposition temperature is preferably 300° C. or lower to suppress evaporation of concentrated sulfuric acid. In addition, the amount of hydrogen peroxide added should be adjusted until all the radioactive waste organic matter in the heated concentrated sulfuric acid is decomposed.
That is, it is preferable to heat the concentrated sulfuric acid until it becomes transparent.

上記の化学分解で生成した炭酸ガスと水蒸気お
よび過酸化水素の分解で発生した酸素ガスは撹拌
型反応器4から冷却吸収塔6に入り、ここで水蒸
気は冷却水により冷却されて回収水となる。冷却
吸収水はポンプ7によつて循環されながらその一
部は蒸留塔8から除去され、残りの大部分は蒸留
塔8で蒸留されたのち冷却器9を通りセパレータ
10を経て循環水槽11に貯留され、ポンプ12
によつて冷却吸収塔6に再循環させる。蒸留塔8
の残渣は場合によつては放射性物質を含むので固
化処理などによつて安全対策を施す。冷却吸収塔
6を出たガスは活性炭吸収塔13に入り、微量の
放射性ヨードなどがあればそれを除去し、清浄な
許容濃度以下の廃ガスとしてブロワ14により排
出される。
The carbon dioxide gas and water vapor produced by the above chemical decomposition and the oxygen gas produced by the decomposition of hydrogen peroxide enter the cooling absorption tower 6 from the stirred reactor 4, where the water vapor is cooled by cooling water and becomes recovered water. . While the cooled absorption water is circulated by the pump 7, a part of it is removed from the distillation column 8, and most of the remaining water is distilled in the distillation column 8, passes through the cooler 9, passes through the separator 10, and is stored in the circulating water tank 11. and pump 12
is recycled to the cooling absorption tower 6. Distillation column 8
The residue may contain radioactive substances, so safety measures must be taken such as solidification. The gas leaving the cooling absorption tower 6 enters the activated carbon absorption tower 13, where trace amounts of radioactive iodine and the like are removed, and the gas is discharged by the blower 14 as clean waste gas with a concentration below the allowable concentration.

一方、放射性廃有機物中に重金属などの無機物
が含まれている場合には、無機物はその一部が硫
酸塩となり、残りの大部分は分解されずに濃硫酸
中に残る。したがつて、これらの無機物が反応器
内に蓄積してくる場合は、反応器の撹拌を止め反
応液を静置して沈殿物質を除去したり、また反応
器を冷却して沈殿物質を除去してもよく、または
反応器内の濃硫酸を抜出し同様の処理をして沈殿
物質を除去することもできる。なお、除去した沈
殿物質は固化処理を施す。
On the other hand, when radioactive organic waste contains inorganic substances such as heavy metals, some of the inorganic substances turn into sulfates, and most of the remaining remains in concentrated sulfuric acid without being decomposed. Therefore, if these inorganic substances accumulate in the reactor, stop stirring the reactor and let the reaction liquid stand still to remove the precipitated substances, or cool the reactor to remove the precipitated substances. Alternatively, the concentrated sulfuric acid in the reactor can be extracted and subjected to similar treatment to remove precipitated substances. Note that the removed precipitate is subjected to solidification treatment.

上記のような処理を行うことにより、放射性廃
有機物は完全に酸化されて炭酸ガスと水蒸気とに
なる。そして、このような方法によれば、酸化剤
として濃硫酸と過酸化水素を用いるので、硝酸を
用いるときのようなNOxの生成がなく、SO2も過
剰の過酸化水素と反応して硫酸に再生される。ま
た硝酸酸化の場合のように爆発性ニトロ化合物の
生成がないので安全対策が容易であり、分解反応
も急激でないから反応制御が容易である。さらに
硫酸―過酸化水素による反応系であるから、装置
の腐食が軽減され、安価な使用材料を選択でき
る。
By performing the above-mentioned treatment, the radioactive waste organic matter is completely oxidized and becomes carbon dioxide gas and water vapor. According to this method, concentrated sulfuric acid and hydrogen peroxide are used as oxidizing agents, so NOx is not produced as is the case when nitric acid is used, and SO 2 also reacts with excess hydrogen peroxide to form sulfuric acid. will be played. Furthermore, unlike in the case of nitric acid oxidation, there is no generation of explosive nitro compounds, so safety measures are easy, and the decomposition reaction is not rapid, making it easy to control the reaction. Furthermore, since the reaction system uses sulfuric acid and hydrogen peroxide, corrosion of the equipment is reduced and inexpensive materials can be selected.

実施例 1 イオン交換樹脂1.0055grを97wt%H2SO460mlの
入つたガラス製反応器に仕込み、加熱昇温させ硫
酸液温200℃より30wt%過酸化水素を滴下し反応
温度200乃至240℃で化学分解を行つた。過酸化水
素滴下量16.3ml、滴下時間60分で液色は黒色より
淡黄色透明になつた。この間発生したガス量は
1481c.c.で初期の生成ガスは、容積パーセントで
O254.82、N220.60、CO2.78、CO221.80、反応中
期の生成ガスはO234.00、N216.68、CO8.78、
CO240.54、末期の生成ガスはO259.99、
N216.26、CO3.00、CO220.75であつた。また処理
速度は反応容積100ml当り1.01gr/hrであつた。
Example 1 1.0055g of ion exchange resin was charged into a glass reactor containing 60ml of 97wt% H 2 SO 4 and the temperature was raised, and 30wt% hydrogen peroxide was added dropwise from the sulfuric acid solution temperature of 200°C to a reaction temperature of 200 to 240°C. Chemical decomposition was carried out. When the amount of hydrogen peroxide dropped was 16.3 ml and the dropping time was 60 minutes, the color of the liquid changed from black to pale yellow and transparent. The amount of gas generated during this period is
At 1481 c.c., the initial produced gas is
O 2 54.82, N 2 20.60, CO2.78, CO 2 21.80, the gas produced in the middle of the reaction is O 2 34.00, N 2 16.68, CO 8.78,
CO 2 40.54, the final product gas is O 2 59.99,
N 2 16.26, CO 3.00, CO 2 20.75. The treatment rate was 1.01 gr/hr per 100 ml of reaction volume.

実施例 2 安息香酸1.0035grを97wt%H2SO470mlの入つた
ガラス製反応器に仕込み、加熱昇温させ硫酸液温
210℃より30wt%過酸化水素を滴下し、反応温度
230乃至240℃で化学分解を行つた。過酸化水素滴
下量15ml滴下時間70分で液色は黒色より淡黄色透
明になつた。この間発生したガス量は、1594c.c.
で、平均ガス組成は容積パーセントでO232.90、
N27.06、CO7.73、CO252.31であつた。また処理
速度は、反応容積100ml当り0.86gr/hrであつ
た。
Example 2 1.0035g of benzoic acid was charged into a glass reactor containing 70ml of 97wt% H 2 SO 4 and heated to raise the temperature of the sulfuric acid solution.
30wt% hydrogen peroxide was added dropwise from 210℃, and the reaction temperature
Chemical decomposition was carried out at 230-240°C. After 70 minutes of dropping 15ml of hydrogen peroxide, the color of the liquid changed from black to pale yellow and transparent. The amount of gas generated during this period was 1594c.c.
and the average gas composition is O 2 32.90 in volume percent,
N 2 7.06, CO 7.73, CO 2 52.31. The processing rate was 0.86 gr/hr per 100 ml of reaction volume.

実施例 3 濾過助剤―フロツク1.0013grを97wt%H2SO460
mlにて加熱溶解した黒色液を反応容積100mlの反
応器に濃硫酸20mlを入れて加熱昇温させ、硫酸液
温220℃より30wt%過酸化水素を滴下し、反応温
度220乃至240℃で化学分解を行つた。過酸化水素
滴下量19.3ml滴下時間41分で液色は黒色透明にな
つた。この間発生したガス量は1995c.c.で平均ガス
組成は、容積パーセントでO276.32、N20.85、
CO6.55、CO216.28であつた。また処理速度は反
応容積100ml当り1.58gr/hrであつた。
Example 3 Filter aid - floc 1.0013gr 97wt%H 2 SO 4 60
Pour 20 ml of concentrated sulfuric acid into a reactor with a reaction volume of 100 ml, heat and raise the temperature of the black liquid, and add 30 wt% hydrogen peroxide dropwise from the sulfuric acid solution temperature of 220°C. I did the disassembly. The amount of hydrogen peroxide dropped was 19.3 ml.The liquid color became black and transparent after dropping time of 41 minutes. The amount of gas generated during this period was 1995 c.c., and the average gas composition was O 2 76.32, N 2 0.85,
CO6.55, CO2 16.28. The processing rate was 1.58 gr/hr per 100 ml of reaction volume.

参考例 1 濾過助剤―フロツク1.5300grを97wt%H2SO480
mlの入つたガラス製反応器に仕込み、加熱昇温さ
せ硫酸液温220℃より70wt%硝酸を滴下し反応温
度220乃至230℃で化学分解を行つた。硝酸滴下量
8.2ml滴下時間41分で液色は黒色より無色透明に
なつた。この間発生したガス量は2658c.c.で平均ガ
ス組成は容積パーセントでCO265.82、N217.50、
SO27.00、NO3.70、CO3.00、N2O1.98であつた。
また処理速度は反応容積100ml当り2.24gr/hrで
あつた。
Reference example 1 Filter aid - floc 1.5300gr 97wt%H 2 SO 4 80
ml of the solution was placed in a glass reactor, the temperature was raised, and 70 wt% nitric acid was added dropwise from the sulfuric acid solution temperature of 220°C to carry out chemical decomposition at a reaction temperature of 220 to 230°C. Nitric acid dripping amount
After 41 minutes of dropping 8.2ml, the color of the liquid changed from black to colorless and transparent. The amount of gas generated during this period was 2658c.c., and the average gas composition was 65.82 % by volume, 17.50% N2 ,
SO 2 7.00, NO 3.70, CO 3.00, N 2 O 1.98.
The processing rate was 2.24 gr/hr per 100 ml of reaction volume.

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

図面は本発明実施装置の概略図である。 1…放射性廃有機物タンク、4…撹拌型反応
器、5…過酸化水素タンク。
The drawing is a schematic diagram of an apparatus for implementing the present invention. 1... Radioactive waste organic matter tank, 4... Stirring type reactor, 5... Hydrogen peroxide tank.

Claims (1)

【特許請求の範囲】[Claims] 1 濃硫酸に放射性廃有機物を仕込み、150〜300
℃の温度に維持しつつ、過酸化水素を添加して放
射性廃有機物を分解することを特徴とする放射性
廃有機物の減容処理方法。
1. Add radioactive waste organic matter to concentrated sulfuric acid, 150 to 300
A method for reducing the volume of radioactive waste organic matter, characterized by decomposing the radioactive waste organic matter by adding hydrogen peroxide while maintaining the temperature at ℃.
JP342577A 1977-01-14 1977-01-14 Method of decreasing volume of radioactive organic waste Granted JPS5388500A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP342577A JPS5388500A (en) 1977-01-14 1977-01-14 Method of decreasing volume of radioactive organic waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP342577A JPS5388500A (en) 1977-01-14 1977-01-14 Method of decreasing volume of radioactive organic waste

Publications (2)

Publication Number Publication Date
JPS5388500A JPS5388500A (en) 1978-08-03
JPS6155079B2 true JPS6155079B2 (en) 1986-11-26

Family

ID=11557012

Family Applications (1)

Application Number Title Priority Date Filing Date
JP342577A Granted JPS5388500A (en) 1977-01-14 1977-01-14 Method of decreasing volume of radioactive organic waste

Country Status (1)

Country Link
JP (1) JPS5388500A (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5543430A (en) * 1978-09-25 1980-03-27 Japan Atomic Energy Res Inst Treating radioactively polluted organic high molecular material
JPS55106399A (en) * 1978-12-22 1980-08-15 Alkem Gmbh Radioactive waste processing method
JPS55129798A (en) * 1979-03-29 1980-10-07 Toyo Engineering Corp Heating method in oxidative decomposition of radioactive organic material
JPH0631866B2 (en) * 1983-09-09 1994-04-27 株式会社東芝 Volume reduction solidification method of radioactive metal-containing organic waste decomposition solution
JPS6127412A (en) * 1984-07-18 1986-02-06 Ebara Corp Method of thermally disposition of waste containing ion exchange resin and apparatus thereof
DE19536934A1 (en) * 1995-10-04 1997-04-10 Weiss Gmbh & Co Leonhard Process for working up acid resins

Also Published As

Publication number Publication date
JPS5388500A (en) 1978-08-03

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