JP3088816B2 - Treatment method of decontamination waste liquid - Google Patents

Treatment method of decontamination waste liquid

Info

Publication number
JP3088816B2
JP3088816B2 JP04011810A JP1181092A JP3088816B2 JP 3088816 B2 JP3088816 B2 JP 3088816B2 JP 04011810 A JP04011810 A JP 04011810A JP 1181092 A JP1181092 A JP 1181092A JP 3088816 B2 JP3088816 B2 JP 3088816B2
Authority
JP
Japan
Prior art keywords
waste liquid
decontamination
gas
nitric acid
hydrochloric acid
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 - Fee Related
Application number
JP04011810A
Other languages
Japanese (ja)
Other versions
JPH05203795A (en
Inventor
人志 西脇
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.)
NGK Insulators Ltd
Original Assignee
NGK Insulators 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 NGK Insulators Ltd filed Critical NGK Insulators Ltd
Priority to JP04011810A priority Critical patent/JP3088816B2/en
Publication of JPH05203795A publication Critical patent/JPH05203795A/en
Application granted granted Critical
Publication of JP3088816B2 publication Critical patent/JP3088816B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Landscapes

  • Heat Treatment Of Water, Waste Water Or Sewage (AREA)

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は、原子力発電所等から発
生する放射性金属廃棄物の除染廃液の処理方法に関する
ものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a decontamination waste liquid of radioactive metal waste generated from a nuclear power plant or the like.

【0002】[0002]

【従来の技術】原子力発電所等から発生する放射能によ
り表面が汚染されたステンレススチールのような金属廃
棄物については、表面に付着している放射性物質を化学
除染法により除去したうえで一般廃棄物として処理する
方法が提案されている。上記のような放射性金属廃棄物
の化学除染液としては、硝酸と塩酸との混合酸が使用さ
れる。しかし従来はこの除染廃液の処理方法が確立され
ておらず、そのままタンクに保存する方法が採用されて
いたため、多くの保存スペースを必要とする等の問題が
あった。
2. Description of the Related Art For metal waste such as stainless steel whose surface is contaminated by radioactivity generated from a nuclear power plant, etc., radioactive substances adhering to the surface are removed by a chemical decontamination method. Methods for treating as waste have been proposed. A mixed acid of nitric acid and hydrochloric acid is used as the chemical decontamination liquid for radioactive metal waste as described above. However, conventionally, a method for treating this decontamination waste liquid has not been established, and a method of storing the waste liquid in a tank has been adopted. Therefore, there has been a problem that a large storage space is required.

【0003】[0003]

【発明が解決しようとする課題】本発明は上記した従来
の問題点を解決して、放射性金属廃棄物を化学除染する
工程から排出された硝酸と塩酸とを含む除染廃液を大幅
に減容するとともに、除染廃液の処理工程からの有害な
排出物を最小限とすることができる除染廃液の処理方法
を提供するために完成されたものである。
SUMMARY OF THE INVENTION The present invention solves the above-mentioned conventional problems, and greatly reduces the decontamination waste liquid containing nitric acid and hydrochloric acid discharged from the step of chemically decontaminating radioactive metal waste. The present invention has been completed in order to provide a method for treating a decontamination waste liquid that can minimize harmful discharges from the processing step of the decontamination waste liquid while allowing the processing to be performed.

【0004】[0004]

【課題を解決するための手段】上記の課題を解決するた
めになされた本発明は、放射性金属廃棄物を化学除染す
る工程から排出された硝酸と塩酸とを含む除染廃液を熱
分解炉において熱分解し、残渣をさらに溶融固化する一
方、発生するガスをろ過したうえ冷却塔に導き、硝酸及
び塩酸を回収するとともにスクラバでNaOHと接触させて
NaClとして海水中へ放出し、更にこのガスを脱硝したう
え大気中へ放出することを特徴とするものである。
SUMMARY OF THE INVENTION In order to solve the above-mentioned problems, the present invention provides a pyrolysis furnace for decontaminating waste liquid containing nitric acid and hydrochloric acid discharged from a step of chemically decontaminating radioactive metal waste. While the residue is further melted and solidified, the generated gas is filtered and led to a cooling tower, where nitric acid and hydrochloric acid are recovered and brought into contact with NaOH with a scrubber.
NaCl is released into seawater, and this gas is further denitrated and released into the atmosphere.

【0005】[0005]

【実施例】次に本発明を図1に示す実施例によって更に
詳細に説明する。まず放射性金属廃棄物を化学除染した
除染廃液を熱分解炉1に投入し、100 〜800℃で熱分解
し、生成した残渣を溶融炉で溶融する。これにより放射
性の核種が溶融固化体中に安定に閉じ込められたブロッ
ク状またはペレット状のガラス固化体となる。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The present invention will be described in more detail with reference to the embodiment shown in FIG. First, a decontamination waste liquid obtained by chemically decontaminating radioactive metal waste is put into a pyrolysis furnace 1 and pyrolyzed at 100 to 800 ° C., and the generated residue is melted in a melting furnace. Thereby, a radioactive nuclide becomes a block-like or pellet-like vitrified material stably confined in the molten solidified material.

【0006】ところがこの熱分解炉1で除染廃液を処理
する際に多量のガスが発生する。このガス中には放射性
のダストが含まれているので、まず乾式のセラミックフ
ィルタ3により放射性のダストをろ過して回収する。次
に空気混合器4により空気を混合してガス温度を下げ、
HEPAフィルタ5に通して放射性のダストを完全に除
去する。
However, a large amount of gas is generated when the decontamination waste liquid is treated in the pyrolysis furnace 1. Since this gas contains radioactive dust, the radioactive dust is first filtered and collected by the dry ceramic filter 3. Next, air is mixed by the air mixer 4 to lower the gas temperature,
The radioactive dust is completely removed through the HEPA filter 5.

【0007】このようにして放射性のダストを除去され
たガスは、冷却塔6において冷却水により冷却され、大
部分の塩酸及び硝酸は回収できる。この冷却塔6を通過
したガスは次にスクラバ7に導かれ、水と接触させて残
余の塩酸を回収する。これらの冷却塔6とスクラバ7に
より回収された硝酸及び塩酸は除染工程へ返送されて除
染液として再利用される。
The gas from which the radioactive dust has been removed in this way is cooled by cooling water in the cooling tower 6, and most of the hydrochloric acid and nitric acid can be recovered. The gas that has passed through the cooling tower 6 is then led to a scrubber 7, where it is brought into contact with water to recover the remaining hydrochloric acid. The nitric acid and hydrochloric acid recovered by the cooling tower 6 and the scrubber 7 are returned to the decontamination step and reused as a decontamination liquid.

【0008】スクラバ7を通過したガスは次にスクラバ
8においてNaOHの水溶液と接触し、ガス中のClはNaClと
なる。このようにして生じた食塩は無害なものであるか
ら、放射性物質を含まない事を確認した後、そのまま海
水中へ放出すればよい。
The gas that has passed through the scrubber 7 is then brought into contact with an aqueous solution of NaOH in the scrubber 8 and Cl in the gas becomes NaCl. Since the salt thus generated is harmless, it can be released into seawater as it is after confirming that it does not contain a radioactive substance.

【0009】スクラバ8を通過したガスは塩酸成分をほ
とんど含有しないが、なお硝酸成分を含有している。そ
こで熱風発生器9によりガス温度を上げたうえで乾式脱
硝設備10に導き、硝酸成分をN2、O2に分解する。このよ
うにして硝酸成分を除去されたガスは、大気中へ放出さ
れる。
The gas passing through the scrubber 8 hardly contains a hydrochloric acid component, but still contains a nitric acid component. Then, the gas temperature is raised by the hot-air generator 9 and the gas is led to the dry denitration equipment 10, where the nitric acid component is decomposed into N 2 and O 2 . The gas from which the nitric acid component has been removed in this way is released to the atmosphere.

【0010】[0010]

【発明の効果】以上に説明したように、本発明の除染廃
液の処理方法によれば、放射性金属廃棄物を化学除染す
る工程から排出された放射性物質を含む除染廃液を溶融
固化体中に安定に閉じ込めることができ、大幅な減容を
図ることができる。また熱分解工程において発生する塩
酸と硝酸とを含んだガスは冷却塔6とスクラバ7に導か
れ、硝酸及び塩酸の大部分は回収されて除染液として再
利用され、また残りの塩酸は食塩として海水中へ放出さ
れるので、有害物質を全く発生させることがない。更に
硝酸は乾式脱硝設備10において分解され、N2、O2として
放出できるので、環境への汚染物質の排出は完全に防止
されることとなる。よって本発明は従来の問題点を解消
した除染廃液の処理方法として、産業の発展に寄与する
ところは極めて大きいものである。
As described above, according to the method for treating decontamination waste liquid of the present invention, the decontamination waste liquid containing radioactive substances discharged from the step of chemically decontaminating radioactive metal waste is melted and solidified. It can be stably confined inside, and can greatly reduce the volume. The gas containing hydrochloric acid and nitric acid generated in the thermal decomposition process is led to the cooling tower 6 and the scrubber 7, and most of the nitric acid and hydrochloric acid are recovered and reused as a decontamination solution, and the remaining hydrochloric acid is converted to salt solution. As it is released into seawater, it does not generate any harmful substances. Further, since nitric acid is decomposed in the dry denitration equipment 10 and can be released as N 2 and O 2 , discharge of pollutants to the environment is completely prevented. Therefore, the present invention is extremely significant as a method for treating a decontamination waste solution that has solved the conventional problems and that contributes to industrial development.

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

【図1】本発明の実施例を説明するフローシートであ
る。
FIG. 1 is a flow sheet illustrating an example of the present invention.

【符号の説明】[Explanation of symbols]

1 熱分解炉 2 溶融炉 6 冷却塔 7 スクラバ 8 スクラバ 10 乾式脱硝設備 DESCRIPTION OF SYMBOLS 1 Pyrolysis furnace 2 Melting furnace 6 Cooling tower 7 Scrubber 8 Scrubber 10 Dry denitration equipment

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 放射性金属廃棄物を化学除染する工程か
ら排出された硝酸と塩酸とを含む除染廃液を熱分解炉に
おいて熱分解し、残渣をさらに溶融固化する一方、発生
するガスをろ過したうえ冷却塔に導き、硝酸及び塩酸を
回収するとともにスクラバでNaOHと接触させてNaClとし
て海水中へ放出し、更にこのガスを脱硝したうえ大気中
へ放出することを特徴とする除染廃液の処理方法。
1. A decontamination waste liquid containing nitric acid and hydrochloric acid discharged from a step of chemically decontaminating radioactive metal waste is thermally decomposed in a pyrolysis furnace, and the residue is further melted and solidified, while the generated gas is filtered. The decontamination waste liquid is characterized by recovering nitric acid and hydrochloric acid, contacting it with NaOH with a scrubber, releasing it into seawater as NaCl, denitrifying this gas and releasing it into the atmosphere. Processing method.
JP04011810A 1992-01-27 1992-01-27 Treatment method of decontamination waste liquid Expired - Fee Related JP3088816B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP04011810A JP3088816B2 (en) 1992-01-27 1992-01-27 Treatment method of decontamination waste liquid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP04011810A JP3088816B2 (en) 1992-01-27 1992-01-27 Treatment method of decontamination waste liquid

Publications (2)

Publication Number Publication Date
JPH05203795A JPH05203795A (en) 1993-08-10
JP3088816B2 true JP3088816B2 (en) 2000-09-18

Family

ID=11788179

Family Applications (1)

Application Number Title Priority Date Filing Date
JP04011810A Expired - Fee Related JP3088816B2 (en) 1992-01-27 1992-01-27 Treatment method of decontamination waste liquid

Country Status (1)

Country Link
JP (1) JP3088816B2 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100498881B1 (en) * 2002-06-07 2005-07-04 현대모비스 주식회사 treatment apparatus for destroying by burning up and melting radioactive waste and method the same
JP5997579B2 (en) * 2012-10-19 2016-09-28 日本碍子株式会社 Treatment method of radioactive metal waste
CN106448789A (en) * 2016-10-26 2017-02-22 中广核工程有限公司 Processing method and system of radioactive chemical wastewater in nuclear power plant

Also Published As

Publication number Publication date
JPH05203795A (en) 1993-08-10

Similar Documents

Publication Publication Date Title
KR100369612B1 (en) System and Treatment Method for Low-and Intermediate-Level Radioactive Waste
EP0179994B1 (en) Process for drying a chelating agent
JP3088816B2 (en) Treatment method of decontamination waste liquid
JP4753141B2 (en) Method for dissolving and separating uranium using ionic liquid, and method for recovering uranium using the same
JP2902384B2 (en) Medium and low level radioactive waste treatment equipment
KR100725862B1 (en) Method of treating highly crystalline or glassy, oxidized incinerator ash and method of treating a solid material
JPH0269697A (en) Treatment of used fuel
JPS6331587A (en) Cleaning method for waste
JPH0752234B2 (en) Vitrification method for nuclear fuel reprocessing waste liquid
KR100364379B1 (en) A treatment machine of intermediate and low-level radioactive wastes
US6716402B2 (en) Dissolution and decontamination process
JPS6263898A (en) Method and device for processing chemical decontaminated waste liquor
JPS6252277B2 (en)
US5744020A (en) Process for treatment of radioactive waste
JP3640111B2 (en) Apparatus and method for removing dioxin from ash melting furnace exhaust gas
JP3081526B2 (en) Surface treatment method for non-combustible material and apparatus therefor
JP2005331276A (en) Method for collecting uranium in alumina particle containing uranium and method for decontamination treatment
JP2003207595A (en) Processing system and processing method of used ion exchange resin
JP3302944B2 (en) Method for treating incinerator effluent containing dioxins
JPS59184900A (en) Method of decomposing and volume-decreasing radioactive organic waste containing sulfur
JP2610453B2 (en) Concentration method of nitric acid waste liquid
JPS57129815A (en) Purifying method for activated carbon
CN115537276A (en) Uranium radioactive decontaminant, use method and treatment method of used waste liquid
BRPI0803710B1 (en) radioactive decontamination process of parts, components and metal structures in a molten salt bath
Jouan et al. The development of nuclear waste vitrification in France

Legal Events

Date Code Title Description
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20000630

LAPS Cancellation because of no payment of annual fees