JPH02287298A - Solidification treatment for radioactive waste - Google Patents
Solidification treatment for radioactive wasteInfo
- Publication number
- JPH02287298A JPH02287298A JP11058689A JP11058689A JPH02287298A JP H02287298 A JPH02287298 A JP H02287298A JP 11058689 A JP11058689 A JP 11058689A JP 11058689 A JP11058689 A JP 11058689A JP H02287298 A JPH02287298 A JP H02287298A
- Authority
- JP
- Japan
- Prior art keywords
- waste
- mixer
- water
- solidification
- component
- 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
- 238000007711 solidification Methods 0.000 title claims abstract description 33
- 230000008023 solidification Effects 0.000 title claims abstract description 33
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 43
- 239000002699 waste material Substances 0.000 claims abstract description 34
- 239000007788 liquid Substances 0.000 claims abstract description 25
- 239000000463 material Substances 0.000 claims abstract description 24
- 239000000945 filler Substances 0.000 claims abstract description 16
- 238000004898 kneading Methods 0.000 claims abstract description 13
- 239000006185 dispersion Substances 0.000 claims abstract description 7
- 238000004140 cleaning Methods 0.000 claims description 29
- 238000012545 processing Methods 0.000 claims description 12
- 238000000926 separation method Methods 0.000 claims description 4
- 238000005406 washing Methods 0.000 abstract description 13
- 238000000034 method Methods 0.000 description 9
- 239000002270 dispersing agent Substances 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000004568 cement Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 150000002484 inorganic compounds Chemical class 0.000 description 1
- 229910010272 inorganic material Inorganic materials 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002683 reaction inhibitor Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
Abstract
Description
【発明の詳細な説明】
[発明の目的コ
(産業上の利用分野)
本発明は、放射性廃棄物の固化装置に関するものである
。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention (Field of Industrial Application) The present invention relates to a radioactive waste solidification device.
(従来の技術)
従来より、原子力発電所や核燃料再処理施設等の放射性
物質取扱い施設で発生する、例えば放射性濃縮廃液等の
放射性廃棄物を処理する方法として、この放射性廃棄物
を安定に固化する固化処理方法が考えられている。(Prior art) Conventionally, as a method for processing radioactive waste such as radioactive concentrated waste liquid generated in facilities handling radioactive materials such as nuclear power plants and nuclear fuel reprocessing facilities, this radioactive waste is stably solidified. Solidification treatment methods are being considered.
この固化処理方法は、処理容器内に例えばペレット等の
放射性廃棄物を収容し、該処理容器内に固化材と分散材
等からなる固化充填材を充填して固化する方法である。This solidification treatment method is a method in which radioactive waste such as pellets is stored in a processing container, and a solidification filler consisting of a solidification material, a dispersion material, etc. is filled into the processing container and solidified.
このような固化方法に用いる固化充填材の供給装置とし
ては、従来より、固化材ホッパ部と、水と分散耐雪から
なる混練水のホッパ部、これら固化材と混練水を混合し
て固化充填材を作り廃棄物収容容器内へ供給する混合機
から構成されたものが知られている。Conventionally, the supply device for the solidified filler used in such a solidification method includes a solidification material hopper section, a hopper section for kneading water made of water and dispersed snow, and a hopper section for mixing these solidification materials and kneading water to supply the solidified filler. A mixer is known that includes a mixer that produces and supplies waste into a waste storage container.
この固化処理方法では、固化材として水硬性無機化合物
、骨剤、無機質流動化材、反応抑制剤等を含有するもの
を用いることにより、特に充填率か高く、かつ長期にわ
たる安定性、耐久性、耐火性に優れた放射性廃棄物の処
理か可能である。In this solidification treatment method, by using a solidification material containing a hydraulic inorganic compound, an aggregate, an inorganic fluidizing agent, a reaction inhibitor, etc., the filling rate is particularly high, and long-term stability, durability, and It is possible to dispose of radioactive waste with excellent fire resistance.
(発明が解決しようとする課題)
ところで、上述した固化装置における固化充填材供給装
置では、固化充填作業終了後、混合機内に付着残存した
固化充填材を洗浄液により洗浄することが行われている
。(Problems to be Solved by the Invention) By the way, in the solidified filler supply device in the solidification apparatus described above, after the solidification and filling operation is completed, the solidified filler remaining attached to the mixer is cleaned with a cleaning liquid.
このように原子力発電所等の放射性物質取扱い施設内で
発生した廃液は、放射性廃l[kとして扱われることか
ら、このような廃液には放射性廃棄物処理を施す必要が
あり、廃液量を減らすことは、設備コストの低下、作業
効率の観点から有利なことである。In this way, waste liquid generated in facilities that handle radioactive materials such as nuclear power plants is treated as radioactive waste l[k, so such waste liquid must be treated as radioactive waste, and the amount of waste liquid must be reduced. This is advantageous from the viewpoint of lower equipment costs and work efficiency.
しかしながら、従来の固化処理装置においては、混合機
を洗浄した廃液はそのまま廃液として排出されるため、
長期使用において、その廃液量は膨大なものとなり、廃
液処理のための設備や処理作業に多くの費用や時間を費
してしまうという問題があった。However, in conventional solidification processing equipment, the waste liquid from cleaning the mixer is discharged as waste liquid, so
In long-term use, the amount of waste liquid becomes enormous, and there is a problem in that a lot of money and time are spent on equipment and processing operations for waste liquid treatment.
本発明は、このような従来の問題点を解決するためにな
されたもので、混合機からの洗浄廃液を減少して、洗浄
廃lfM処理に関わる設備や労力を最少にできる放射性
廃棄物の固化装置を提供することを1]的とするもので
ある。The present invention was made in order to solve these conventional problems, and is a solidification method for radioactive waste that can reduce the cleaning waste liquid from the mixer and minimize the equipment and labor involved in cleaning waste lfM treatment. 1] The purpose is to provide a device.
[発明の構成〕
(課題を解決するための手段)
本発明の放射性廃棄物の固化装置は、固化材と混練水と
を混合して固化充填材を作成する混合機と、固化作業終
了時に前記混合機内に洗浄液を供給して前記混合機内に
付着した固化充填材を洗浄除去する洗浄機構とを備え、
前シ己固化充jJ’↓材を放射性廃棄物に加えて放射性
廃棄物の固化処理を行う装置において、前記混合機から
の洗浄廃液を洗浄水液成分と前記固化)」中の骨材成分
とに分離する分離機構と、この分離された洗浄水液成分
に所定量の分散材を加えて前記混線材を作成する洗浄水
液成分再使用機構とを具備したことを特徴とするもので
ある。[Structure of the Invention] (Means for Solving the Problems) The radioactive waste solidification apparatus of the present invention includes a mixer that mixes a solidification material and kneading water to create a solidified filler, and a a cleaning mechanism that supplies a cleaning liquid into the mixer to clean and remove solidified filler adhering to the mixer;
In an apparatus that performs solidification treatment of radioactive waste by adding pre-filling material to radioactive waste, the cleaning waste liquid from the mixer is combined with the cleaning water component and the aggregate component in the solidification). The present invention is characterized by comprising a separation mechanism for separating into two, and a cleaning water component reuse mechanism for adding a predetermined amount of dispersing material to the separated cleaning water component to create the mixed wire material.
(作 用)
本発明は、混合機を洗浄した後の洗浄廃液中に含まれる
骨材成分と洗浄水液成分とを分離し、この洗浄水液成分
に分散材を添加して、混練水として再使用するように構
成したことで、固化処理装置から排出される廃棄物は骨
材成分のみとなり、廃棄物量を大幅に低減することがで
き、洗浄廃液処理に関わる設備や労力の縮小化が可能と
なる。(Function) The present invention separates the aggregate component and the washing water component contained in the washing waste liquid after washing the mixer, adds a dispersant to this washing water liquid component, and uses the mixture as kneading water. By configuring it to be reused, the waste discharged from the solidification treatment equipment is only the aggregate component, making it possible to significantly reduce the amount of waste and downsizing the equipment and labor involved in processing cleaning waste liquid. becomes.
(実施例)
以下、本発明を原子力発電所内に設置される放射性廃棄
物セメント充填固化処理装置に適用した一実施例につい
て図を参照して説明する。(Example) Hereinafter, an example in which the present invention is applied to a radioactive waste cement filling and solidification processing apparatus installed in a nuclear power plant will be described with reference to the drawings.
第1図は実施例の固化処理装置における固化充填材供給
機構の構成を示す図で、固化材ホッパ1内に収容された
固化材は、計量器2により所定量計量されて混合機3へ
と送られる。一方混練水ホツバ4内に収容された分散材
と水等からなる混練水も計量器5により所定量計量され
て混合機3へと送られる。こうして混合機3内に送られ
た固化材と混練水は、混合されて固化充填材として廃棄
物を収容した例えばドラム缶等の廃棄物処理容器6に充
填される。FIG. 1 is a diagram showing the configuration of the solidified filler supply mechanism in the solidification processing apparatus of the embodiment, in which the solidified material accommodated in the solidified material hopper 1 is measured in a predetermined amount by a measuring device 2 and then transferred to a mixer 3. Sent. On the other hand, a predetermined amount of kneading water made up of a dispersant, water, etc. contained in the kneading water hopper 4 is also measured by a measuring device 5 and sent to the mixer 3. The solidified material and kneading water thus sent into the mixer 3 are mixed and filled as a solidified filler into a waste treatment container 6, such as a drum, containing waste.
固化処理作業終了後は、洗浄水ホッパ7内に収容された
洗浄水を計量器8により所定量計量して混合機3へと送
り込み混合機3内に付着した固化充填材を除去する。そ
して洗浄後の洗浄廃液は、分離装置9へと送られて、こ
こで骨材成分と洗浄水液成分の分離が行われる。After the solidification process is completed, a predetermined amount of the cleaning water contained in the cleaning water hopper 7 is measured by the measuring device 8 and sent to the mixer 3 to remove the solidified filler that has adhered to the inside of the mixer 3. The washing waste liquid after washing is sent to the separation device 9, where the aggregate component and the washing water component are separated.
分離装置9で分離された洗浄水液成分は、計量器10に
より所定量計量されて洗浄水ホッパ7へと送り込まれる
。洗浄水ホッパ7に送り込まれた洗浄水液成分は、ここ
で分散材ホッパ11から計量器12により所定量計量さ
れて送り込まれた分散材および水13と混合されて、次
の固化処理作業時に再び混練水として混合機3内へと送
り込まれる。The cleaning water component separated by the separator 9 is measured in a predetermined amount by a measuring device 10 and sent to the cleaning water hopper 7. The cleaning water component sent to the cleaning water hopper 7 is mixed with the dispersion material and water 13 that have been metered in a predetermined amount by the measuring device 12 from the dispersion material hopper 11 and fed therein, and then used again during the next solidification process. The water is sent into the mixer 3 as kneading water.
一方、分離装置9で分離された骨材成分は、放射性廃棄
物として処理機構14へと送られ処理される。On the other hand, the aggregate components separated by the separation device 9 are sent to the processing mechanism 14 and processed as radioactive waste.
このように、混合機3を洗浄した後の洗浄廃液中に含ま
れる骨材成分と洗浄水液成分とを分離し、この洗浄水液
成分に分散材を添加して、混練水として再使用するよう
に構成したことて、固化処理装置から排出される廃棄物
は骨材成分のみとなり、廃棄物量を大幅に低減すること
ができ、洗浄廃液処理に関わる設備や労力の縮小化が可
能となる。In this way, the aggregate component and the cleaning water component contained in the cleaning waste liquid after cleaning the mixer 3 are separated, and the dispersant is added to this cleaning water component to be reused as kneading water. With this configuration, the waste discharged from the solidification treatment device is only aggregate components, and the amount of waste can be significantly reduced, making it possible to downsize the equipment and labor involved in processing cleaning waste liquid.
[発明の効果]
以上説明したように本発明の放射性廃棄物の固化処理装
置によれば、固化処理時に排出される廃棄物量を大幅に
低減することができ、洗浄廃液処理に関わる設備や労力
の縮小化が可能となる。[Effects of the Invention] As explained above, according to the radioactive waste solidification treatment apparatus of the present invention, the amount of waste discharged during solidification treatment can be significantly reduced, and the equipment and labor involved in cleaning waste liquid treatment can be reduced. It becomes possible to downsize.
第1図は実施例の放射性廃棄物の固化処理装置における
固化充填材供給機構の構成を示す図である。FIG. 1 is a diagram showing the configuration of a solidified filler supply mechanism in a radioactive waste solidification processing apparatus according to an embodiment.
Claims (1)
機と、固化作業終了時に前記混合機内に洗浄液を供給し
て前記混合機内に付着した固化充填材を洗浄除去する洗
浄機構とを備え、前記固化充填材を放射性廃棄物に加え
て放射性廃棄物の固化処理を行う装置において、 前記混合機からの洗浄廃液を洗浄水液成分と前記固化材
中の骨材成分とに分離する分離機構と、この分離された
洗浄水液成分に所定量の分散材を加えて前記混線材を作
成する洗浄水液成分再使用機構とを具備したことを特徴
とする放射性廃棄物の固化処理装置。[Scope of Claims] A mixer that mixes a solidifying material and kneading water to create a solidified filler, and a cleaning liquid that is supplied into the mixer at the end of solidification work to clean the solidified filler that has adhered to the inside of the mixer. an apparatus for solidifying radioactive waste by adding the solidified filler to the radioactive waste, wherein the cleaning waste liquid from the mixer is combined with the cleaning water component and the aggregate in the solidifying material. Radioactive waste comprising: a separation mechanism that separates the separated cleaning water components; and a cleaning water component reuse mechanism that adds a predetermined amount of dispersion material to the separated cleaning water components to create the mixed wire component. Material solidification processing equipment.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP11058689A JPH02287298A (en) | 1989-04-28 | 1989-04-28 | Solidification treatment for radioactive waste |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP11058689A JPH02287298A (en) | 1989-04-28 | 1989-04-28 | Solidification treatment for radioactive waste |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH02287298A true JPH02287298A (en) | 1990-11-27 |
Family
ID=14539608
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP11058689A Pending JPH02287298A (en) | 1989-04-28 | 1989-04-28 | Solidification treatment for radioactive waste |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH02287298A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH07120595A (en) * | 1993-10-22 | 1995-05-12 | Chichibu Onoda Cement Corp | Device and method for processing radioactive waste |
-
1989
- 1989-04-28 JP JP11058689A patent/JPH02287298A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH07120595A (en) * | 1993-10-22 | 1995-05-12 | Chichibu Onoda Cement Corp | Device and method for processing radioactive waste |
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