JPS62299798A - Radioactive waste liquor processor - Google Patents
Radioactive waste liquor processorInfo
- Publication number
- JPS62299798A JPS62299798A JP14436086A JP14436086A JPS62299798A JP S62299798 A JPS62299798 A JP S62299798A JP 14436086 A JP14436086 A JP 14436086A JP 14436086 A JP14436086 A JP 14436086A JP S62299798 A JPS62299798 A JP S62299798A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- radioactive waste
- radioactive
- assimilation
- dryer
- 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
- 239000002901 radioactive waste Substances 0.000 title claims description 33
- 239000007788 liquid Substances 0.000 claims description 54
- 239000002699 waste material Substances 0.000 claims description 20
- 238000002156 mixing Methods 0.000 claims description 12
- 239000004033 plastic Substances 0.000 claims description 12
- 239000000843 powder Substances 0.000 claims description 12
- 239000000463 material Substances 0.000 claims description 10
- 230000002285 radioactive effect Effects 0.000 claims description 8
- 239000003795 chemical substances by application Substances 0.000 claims description 5
- 238000012545 processing Methods 0.000 claims description 5
- 239000003999 initiator Substances 0.000 description 11
- 230000001603 reducing effect Effects 0.000 description 10
- 238000007711 solidification Methods 0.000 description 9
- 230000008023 solidification Effects 0.000 description 9
- 239000000126 substance Substances 0.000 description 9
- 238000000034 method Methods 0.000 description 5
- 238000010586 diagram Methods 0.000 description 4
- 230000005684 electric field Effects 0.000 description 4
- 150000001451 organic peroxides Chemical class 0.000 description 4
- 239000003638 chemical reducing agent Substances 0.000 description 3
- 238000001035 drying Methods 0.000 description 3
- 239000012857 radioactive material Substances 0.000 description 3
- PPBRXRYQALVLMV-UHFFFAOYSA-N Styrene Chemical compound C=CC1=CC=CC=C1 PPBRXRYQALVLMV-UHFFFAOYSA-N 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 150000002978 peroxides Chemical class 0.000 description 1
- 238000010587 phase diagram Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 235000010344 sodium nitrate Nutrition 0.000 description 1
- 239000004317 sodium nitrate Substances 0.000 description 1
- 229910052938 sodium sulfate Inorganic materials 0.000 description 1
- 235000011152 sodium sulphate Nutrition 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000010409 thin film Substances 0.000 description 1
- 229920006337 unsaturated polyester resin Polymers 0.000 description 1
Landscapes
- External Artificial Organs (AREA)
- Paper (AREA)
- Treatment Of Liquids With Adsorbents In General (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】
３、発明の詳細な説明
［発明の目的］
（産業上の利用分野）
本発明は原子力発電所等の放射性物質取扱い施設におい
て発生する放射性廃液を処理する放射性廃液処１！ｌ装
置に係り、特に放射性廃液を乾燥処理した後プラスデッ
ク固化処理する方法に用いる放射性廃液処理装置に関す
る。Detailed Description of the Invention 3. Detailed Description of the Invention [Purpose of the Invention] (Field of Industrial Application) The present invention provides a radioactive waste liquid treatment system 1 for treating radioactive waste liquid generated in facilities handling radioactive materials such as nuclear power plants. ! The present invention relates to a radioactive waste liquid processing apparatus, and more particularly to a radioactive waste liquid processing apparatus used in a method of drying radioactive waste liquid and then solidifying it with a plus deck.
（従来の技術）
一般に沸１１を水型原子力発電所、核燃料再処理工場等
の放躬性物ｖｉ取扱い施設で発生する放射性廃液は、溢
縮乾燥され主として硫酸ナトリウムや硝酸ナトリウムか
らなる粉体とされた後同化材により固化される。(Prior art) Generally, radioactive waste liquid generated at facilities that handle radioactive materials such as water-type nuclear power plants and nuclear fuel reprocessing plants is flooded and dried to form a powder mainly consisting of sodium sulfate and sodium nitrate. After that, it is solidified with assimilated material.
この同化処理方法としては、硬化性プラスチックからな
る固化材により同化処理を行うプラスチック同化処理方
法が、軽■で機械的衝撃に強い固化体パッケージが得ら
れるところから近時有望視されている。As this assimilation treatment method, a plastic assimilation treatment method in which the assimilation treatment is performed using a solidification material made of curable plastic has recently been viewed as promising because it provides a solidified package that is lightweight and resistant to mechanical shock.
このプラスチック固化処理方法に用いる装置は、放射性
廃液を貯蔵する廃液貯蔵タンクと、放射性廃液を放射性
粉体とする竪型）速成乾燥機等の乾燥機と、この放射性
粉体とプラスチック固化側とを混合する混合装置とを協
えている。そして廃液貯蔵タンクから送られた放射性廃
液は、乾燥機にて放射性粉体とされた後混合装置内に移
送され、この放射性粉体は混合装置内にて硬化性プラス
チック固化材と混合され、この混合物がドラム出簀の容
器内に充填されて一体に固化され固化体パッケージに形
成される。The equipment used in this plastic solidification treatment method includes a waste liquid storage tank that stores radioactive waste liquid, a dryer such as a vertical type quick dryer that converts the radioactive waste liquid into radioactive powder, and a side for solidifying the radioactive powder and plastic. It is equipped with a mixing device for mixing. The radioactive waste liquid sent from the waste liquid storage tank is turned into radioactive powder in a dryer and then transferred to a mixing device.This radioactive powder is mixed with a curable plastic solidifying material in the mixing device. The mixture is filled into a drum container and solidified into a solid package.
プラスチック同化材としてはスヂレンで希釈した不飽和
ポリエステル樹脂等が用いられ、有機過酸化物を同化開
始剤として使用し、同化材を重合固化させる方法が一般
的に採用されている。An unsaturated polyester resin diluted with styrene is used as the plastic assimilation material, and a method is generally adopted in which the assimilation material is polymerized and solidified using an organic peroxide as an assimilation initiator.
（発明が解決しようとする問題点）
しかし放射性廃液中に還元性物質、例えば、Ｆｅ２＋、
Ｃｕ＋、５Ｏ３２−１ＮＯ２−等が多量に含まれている
と、これらの還元性物質が有機過酸化物等の固化開始剤
の分解により生じたラジカルを消費して固化開始剤とし
ての効ツノを失わせるため、同化材の硬化が妨害され、
形成された固化体パッケージの硬度が低く、従って固化
体パック−−ジの機械的強度や安定性が低くなるという
問題があった。(Problem to be solved by the invention) However, there are reducing substances in the radioactive waste liquid, such as Fe2+,
If a large amount of Cu+, 5O32-1NO2-, etc. is contained, these reducing substances will consume the radicals generated by the decomposition of solidification initiators such as organic peroxides and lose their effectiveness as solidification initiators. hardening of the assimilated material is hindered,
There is a problem in that the hardness of the formed solidified package is low, and therefore the mechanical strength and stability of the solidified package are low.
本発明は、このような従来の問題に対処するためになさ
れたもので、放射性廃液中の還元性物質により同化材の
硬化が妨げられることなく、機械的強度、安定性を向上
させた同化体パッケージを形成する放射性廃液処理装置
を提供することを目的とする。The present invention was made in order to address these conventional problems, and it is an assimilate that has improved mechanical strength and stability without hindering the curing of the assimilate due to reducing substances in radioactive waste fluid. The object of the present invention is to provide a radioactive waste liquid treatment device that forms a package.
［発明の構成］
（問題点を解決するための手段〉
本発明の放射性廃液処理装置は、放射性廃液を貯蔵Ｊ８
廃液貯蔵タンクと、この廃液貯蔵タンクから送られた放
射性廃液を乾燥して１ｊＩｉ則性扮体とする乾燥機と、
この乾燥機から送られた前記放射性粉体と硬化性プラス
チック月利とを混合する混合装置とをｂｊｎえた放射性
廃液処理装置において、前記廃液貯蔵タンクと前記乾燥
機との間に電解槽を設置したものである。[Structure of the invention] (Means for solving the problem) The radioactive waste liquid treatment device of the present invention stores radioactive waste liquid J8
a waste liquid storage tank; a dryer that dries the radioactive waste liquid sent from the waste liquid storage tank into a 1jIi regular body;
In a radioactive waste liquid processing apparatus equipped with a mixing device for mixing the radioactive powder sent from the dryer and the curable plastic monthly charge, an electrolytic cell was installed between the waste liquid storage tank and the dryer. It is something.
（作用）
本発明の放射性廃液処理装置において、電解層にて放射
性廃液に電圧が加えられることにより、放射性廃液中の
還元性物質は酸化されて還元性を失い、有機過酸化物等
の同化開始剤と反応しなくなる。(Function) In the radioactive waste liquid treatment device of the present invention, by applying voltage to the radioactive waste liquid in the electrolytic layer, the reducing substances in the radioactive waste liquid are oxidized and lose their reducing properties, and assimilation of organic peroxides etc. starts. No longer reacts with the agent.
従って固化開始剤の効力が失われないため同化体パッケ
ージ形成時に同化材の硬化が妨害されることがなく、機
械的強度、安定性を向上させた固化体パッケージを形成
することができる。Therefore, since the effectiveness of the solidification initiator is not lost, the curing of the assimilant is not hindered during the formation of the assimilate package, and a solidified package with improved mechanical strength and stability can be formed.
（実施例） 次に本発明の実施例について説明する。(Example) Next, examples of the present invention will be described.
本発明の実施例の放射性廃液処理装置は第１図に示ず構
成となっている。A radioactive waste liquid treatment apparatus according to an embodiment of the present invention has a configuration not shown in FIG.
原子力発電所等で発生した放射性廃液は、廃液貯蔵タン
ク１に一旦貯留された後、給液ポンプ２により例えば竪
型薄膜乾燥機等の乾燥機３に導かれる。Radioactive waste liquid generated at a nuclear power plant or the like is once stored in a waste liquid storage tank 1 and then guided by a liquid supply pump 2 to a dryer 3 such as a vertical thin film dryer.
廃液貯蔵タンク１と給液ポンプ２との間には電解槽４が
設置され、廃液貯蔵タンク１から送られた放射性廃液は
この電解槽４を通過する際に電圧を加えられ、乾燥機３
へ移送される。An electrolytic cell 4 is installed between the waste liquid storage tank 1 and the liquid supply pump 2, and when the radioactive waste liquid sent from the waste liquid storage tank 1 passes through this electrolytic cell 4, a voltage is applied to it, and the dryer 3
will be transferred to.
電解槽４は第２図、第３図に示すように構成されている
。放射性廃液は、電解槽４内を移動する際に、アノード
５と隔膜６を隔てたカソード７により電圧をかけられ、
メツシュ型アノード８を通過して乾燥機３へ移送される
。図中９は参照電極である。The electrolytic cell 4 is constructed as shown in FIGS. 2 and 3. When the radioactive waste liquid moves within the electrolytic cell 4, a voltage is applied to it by the cathode 7 separated by the anode 5 and the diaphragm 6.
It passes through a mesh type anode 8 and is transferred to the dryer 3. 9 in the figure is a reference electrode.
乾燥機３で乾燥され粉体化された放射性物質は一旦粉体
貯蔵タンク１０に貯蔵されある一定ｍ溜まったところで
混合装置」１内に送られる。そしてプラスチックタンク
１２、同化開始剤クンク１３、同化促進剤タンク１４か
ら、移送ポンプ１５．１６．１７によりプラスチック同
化材、同化開始剤、同化促進剤が混合装置１１内に送り
込まれて上記の放射性粉体と混合される。そして攪拌機
１８によって充分混合されたこの混合物は、ドラム缶１
９に収容され同化体パッケージに形成される。The radioactive material dried and powdered in the dryer 3 is temporarily stored in a powder storage tank 10, and when a certain amount of m is accumulated, it is sent into the mixing device 1. Then, from the plastic tank 12, the assimilation initiator Kunku 13, and the assimilation accelerator tank 14, the plastic assimilation agent, assimilation initiator, and assimilation accelerator are fed into the mixing device 11 by transfer pumps 15, 16, and 17, and the radioactive powder is mixed with the body. Then, this mixture sufficiently mixed by the stirrer 18 is transferred to the drum can 1.
9 and formed into an assimilate package.
プラスチック同化材としては、例えば不飽和ポリニスデ
ル樹脂、同化開始剤としては例えば有機過酸化物が使用
可能である。As the plastic assimilation agent, for example, an unsaturated polynisderian resin can be used, and as the assimilation initiator, for example, an organic peroxide can be used.
図中、２０は流量計、２１はモータ、２２は冷却水、２
３はコンデンサー、２４はサンプルタンク、２５は排気
装置、２６．２７は排気口である。In the figure, 20 is a flow meter, 21 is a motor, 22 is a cooling water, 2
3 is a condenser, 24 is a sample tank, 25 is an exhaust device, and 26.27 is an exhaust port.
このように構成された放射性廃液処理装置を使用するに
あたり、Ｎ’ａ２ＳＯ４を２０ｗｔ％含み、同化材の硬
化妨害物質としてＮａ、＋ ＮＯ２が２０００ｐｐｍ存
在する溶液を模擬廃液として用いて、実施例の装置によ
り乾燥処理、同化処理を行なった。When using the radioactive waste liquid treatment apparatus configured as described above, a solution containing 20 wt% of N'a2SO4 and 2000 ppm of Na, + NO2 as substances that inhibit the hardening of the assimilate was used as a simulated waste liquid, and the apparatus of the example was used. Drying treatment and assimilation treatment were performed.
より模擬廃液に電圧を７Ｊ［＋えた。これとは別に比較
のため上記の模擬廃液に従来の成用性廃液処理装置を用
いて乾燥処理、固化処理を行なった。尚このとき用いた
固化月、固化開始剤、同化促進剤および模擬廃液の粉体
の重帛比は次のとおりである。A voltage of 7 J was applied to the simulated waste liquid. Separately, for comparison, the above simulated waste liquid was subjected to drying and solidification using a conventional synthetic waste liquid processing apparatus. The weight ratios of the solidification agent, solidification initiator, assimilation accelerator, and simulated waste liquid powder used at this time were as follows.
この結果、実施例の装置を用いて形成した固化体は硬化
が完全であり、同化体の一軸圧縮強度は２ｏｏ ｋｇ
／ｃｉで機械的強度が良好であった。一方従米の装置を
用いて形成した固化体は硬化が不完全であった。As a result, the solidified body formed using the apparatus of the example was completely hardened, and the unconfined compressive strength of the assimilated body was 2oo kg.
/ci, the mechanical strength was good. On the other hand, the solidified material formed using Jubei's equipment was incompletely cured.
この結果かられかるように、実施例において、放射性廃
液が電界槽４内にて電圧を加えられることにより、放射
外廓液中の還元性物質は酸化されて還元性を失う。As can be seen from this result, in the example, when a voltage is applied to the radioactive waste liquid in the electric field bath 4, the reducing substance in the radiation outer liquid is oxidized and loses its reducibility.
第４図はＦｅの水中における状態図であるが、この図か
られかるように、Ｆ ｅ ２＋は還元性物貿であり仙の
物質を還元する性質が大きいが、ある一定の値以上の電
圧が加えられると酸化されて電子がうばわれ、はとんど
還元性のないＦｅＺ＋になる。同様に放ｑ″３性廃液中
の還元性物質、例えばＣｕ” 、ＳＯ３２−、ＮＯ２−
等は電圧を加えられると酸化されＣｕ２”、ＳＯ４２−
１ＮＯ３−等になり還元性を失う。そのため上記の還元
性物質は右は過酸化物などの同化開始剤と反応しなくな
るので、同化開始剤の効力が失われず、同化材の硬化が
妨害されない。Figure 4 is a phase diagram of Fe in water. As can be seen from this diagram, Fe 2+ is a reducing substance and has a strong property of reducing other substances, but when the voltage exceeds a certain value, When added, it is oxidized and loses electrons, becoming FeZ+, which has almost no reducibility. Similarly, reducing substances in the oxidized waste liquid, such as Cu'', SO32-, NO2-
etc. are oxidized when a voltage is applied to Cu2'', SO42-
1NO3- etc. and loses its reducing property. Therefore, the above-mentioned reducing substance no longer reacts with the assimilation initiator such as peroxide, so the effectiveness of the assimilation initiator is not lost and the curing of the assimilation material is not hindered.
従ってこの散開性廃液処理装置を用いれば、還元性物質
が存在する１ｉＩｉ割性廃液を、機械的強度、安定性を
向上させた固化体パッケージとして処理することができ
る。Therefore, by using this dispersible waste liquid treatment device, it is possible to treat the 1iIi split waste liquid in which reducing substances are present as a solidified package with improved mechanical strength and stability.
［発明の効果１
以上説明したように、本発明の放射性廃液処理装置を用
いれば、放射性廃液中の還元性物貿によって同化材の硬
化が妨害されることがなく、放射性廃液を機械的強度、
安定性を向上させた固化体として処理することができる
。[Effects of the Invention 1] As explained above, by using the radioactive waste liquid treatment apparatus of the present invention, the curing of the assimilation material is not hindered by the reducing substances in the radioactive waste liquid, and the radioactive waste liquid has a high mechanical strength,
It can be processed as a solidified product with improved stability.
第１図は、本発明の実施例の放射性廃液処理装置の配管
系統図、第２図は本発明の実施例における電界槽の平面
図、第３図は本発明の実施例にあける電界槽の断面図、
第４図はＦｅの水中における状態図である。
１・・・・・・・・・廃液貯蔵タンク
３・・・・・・・・・乾燥機
４・・・・・・・・・電界槽
１０・・・・・・・・・粉体貯蔵タンク１１・・・・・
・・・・混合装置
１２・・・・・・・・・プラスチックタンク１３・・・
・・・・・・同化開始剤タンク１４・・・・・・・・・
固化促進剤タンク１９・・・・・・・・・ドラム缶
出願人 日本原子力事業株式会社同
株式会社 東芝Fig. 1 is a piping system diagram of a radioactive waste liquid treatment equipment according to an embodiment of the present invention, Fig. 2 is a plan view of an electric field tank according to an embodiment of the present invention, and Fig. 3 is a diagram of an electric field tank according to an embodiment of the present invention. cross section,
FIG. 4 is a state diagram of Fe in water. 1...... Waste liquid storage tank 3... Dryer 4... Electric field tank 10... Powder storage Tank 11...
...Mixing device 12...Plastic tank 13...
...Assimilation initiator tank 14...
Solidification accelerator tank 19...Drum Applicant: Japan Atomic Energy Corporation
Toshiba Corporation
Claims (1)
液貯蔵タンクから送られた放射性廃液を乾燥して放射性
粉体とする乾燥機と、この乾燥機から送られた前記放射
性粉体と硬化性プラスチック材料とを混合する混合装置
とを備えた放射性廃液処理装置において、前記廃液貯蔵
タンクと前記乾燥機との間に電解槽を設置したことを特
徴とする放射性廃液処理装置。(1) A waste liquid storage tank that stores radioactive waste liquid, a dryer that dries the radioactive waste liquid sent from the waste liquid storage tank to turn it into radioactive powder, and a curing agent for the radioactive powder sent from this dryer. What is claimed is: 1. A radioactive waste liquid processing apparatus comprising a mixing device for mixing a plastic material with a mixing device, characterized in that an electrolytic cell is installed between the waste liquid storage tank and the dryer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14436086A JPS62299798A (en) | 1986-06-20 | 1986-06-20 | Radioactive waste liquor processor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14436086A JPS62299798A (en) | 1986-06-20 | 1986-06-20 | Radioactive waste liquor processor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62299798A true JPS62299798A (en) | 1987-12-26 |
Family
ID=15360290
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP14436086A Pending JPS62299798A (en) | 1986-06-20 | 1986-06-20 | Radioactive waste liquor processor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62299798A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10082318B2 (en) | 2012-03-02 | 2018-09-25 | Beijing Terasolar Energy Technologies Co., Ltd. | Linear fresnel light concentrating device with high multiplying power |
-
1986
- 1986-06-20 JP JP14436086A patent/JPS62299798A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US10082318B2 (en) | 2012-03-02 | 2018-09-25 | Beijing Terasolar Energy Technologies Co., Ltd. | Linear fresnel light concentrating device with high multiplying power |
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