JPS63113398A - Solidification equipment for radioactive waste liquor - Google Patents
Solidification equipment for radioactive waste liquorInfo
- Publication number
- JPS63113398A JPS63113398A JP25836086A JP25836086A JPS63113398A JP S63113398 A JPS63113398 A JP S63113398A JP 25836086 A JP25836086 A JP 25836086A JP 25836086 A JP25836086 A JP 25836086A JP S63113398 A JPS63113398 A JP S63113398A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- polymerization
- tank
- waste liquid
- polymerization initiator
- 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.)
- Granted
Links
- 239000002901 radioactive waste Substances 0.000 title claims description 31
- 238000007711 solidification Methods 0.000 title claims description 16
- 230000008023 solidification Effects 0.000 title claims description 16
- 239000007788 liquid Substances 0.000 claims description 52
- 239000003505 polymerization initiator Substances 0.000 claims description 37
- 239000000126 substance Substances 0.000 claims description 33
- 238000006116 polymerization reaction Methods 0.000 claims description 32
- 239000003814 drug Substances 0.000 claims description 14
- 239000011261 inert gas Substances 0.000 claims description 13
- 239000003112 inhibitor Substances 0.000 claims description 13
- 238000002347 injection Methods 0.000 claims description 13
- 239000007924 injection Substances 0.000 claims description 13
- 229940079593 drug Drugs 0.000 claims description 11
- 239000011347 resin Substances 0.000 claims description 11
- 229920005989 resin Polymers 0.000 claims description 11
- 239000000243 solution Substances 0.000 claims description 10
- 229920001187 thermosetting polymer Polymers 0.000 claims description 8
- 230000005855 radiation Effects 0.000 claims description 3
- 238000001035 drying Methods 0.000 claims 1
- 238000010298 pulverizing process Methods 0.000 claims 1
- 238000011144 upstream manufacturing Methods 0.000 claims 1
- 238000010586 diagram Methods 0.000 description 7
- 238000000034 method Methods 0.000 description 7
- 239000000843 powder Substances 0.000 description 7
- 239000003507 refrigerant Substances 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- 239000003999 initiator Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000002542 deteriorative effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
Landscapes
- Feeding, Discharge, Calcimining, Fusing, And Gas-Generation Devices (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【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、放射性廃液の同化装置ｄに関する。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to an assimilation device d for radioactive waste liquid.
（従来の技術）
近年、原子力発電所における放射性廃液の固化処理は、
放射性廃棄物の減溶性が優れている理由からプラスチッ
ク同化法が採用されている。ここで第２図及び第３図を
参照して、従来のプラスチツク同化法を採用した放射性
廃液の固化装置について説明する。第２図において、放
射性廃液は放射性廃液貯蔵タンク１内に貯蔵されている
。この放射性廃液貯蔵タンク１内から導かれた放射性廃
液は乾燥機２にて乾燥粉体化される。この粉体化された
放射性廃液は粉体移送機３を介して粉体貯蔵槽４に貯蔵
され、この粉体貯蔵槽４から一定量の粉体が粉体移送機
５．粉体移送配管５ａを介して混合槽６に導かわている
にの混合槽６には熱硬化性樹脂が熱硬化性樹脂タンク７
から樹脂移送配管８を介して導かれる。そして、この熱
硬化性樹脂と前記放射性粉体は前記混合槽６内で混合さ
れる。この混合体はまず重合開始剤貯蔵タンク９から第
１の薬剤注入配管１０を介して供給される重合開始剤に
よって開始され、さらに重合促進剤貯蔵タンク１１から
第２の薬剤注入配管１２を介して供給される重合促進剤
によって促進される。また、何らかの事情により重合反
応を中止させる場合には、重合禁止剤貯蔵タンク１３に
貯蔵される重合禁止剤を第３の薬剤注入配管１４を介し
て混合槽６に供給する。そして、重合されたプラスチッ
ク混合体はドラムカン１５に充填され放射性廃棄物とし
て貯蔵される。(Conventional technology) In recent years, the solidification treatment of radioactive waste liquid at nuclear power plants has been
The plastic assimilation method is used because it has an excellent ability to reduce the solubility of radioactive waste. Here, with reference to FIGS. 2 and 3, a radioactive waste liquid solidification apparatus employing the conventional plastic assimilation method will be described. In FIG. 2, radioactive waste liquid is stored in a radioactive waste liquid storage tank 1. The radioactive waste liquid led from the inside of the radioactive waste liquid storage tank 1 is dried and powdered in a dryer 2. This powdered radioactive waste liquid is stored in a powder storage tank 4 via a powder transfer machine 3, and a certain amount of powder is transferred from this powder storage tank 4 to a powder transfer machine 5. The thermosetting resin is introduced into the mixing tank 6 via the powder transfer pipe 5a, and the thermosetting resin is fed into the mixing tank 6 through the thermosetting resin tank 7.
from there through the resin transfer pipe 8. Then, this thermosetting resin and the radioactive powder are mixed in the mixing tank 6. This mixture is first initiated by a polymerization initiator supplied from a polymerization initiator storage tank 9 through a first chemical injection pipe 10, and then supplied from a polymerization accelerator storage tank 11 through a second chemical injection pipe 12. It is promoted by the supplied polymerization accelerator. If the polymerization reaction is to be stopped for some reason, the polymerization inhibitor stored in the polymerization inhibitor storage tank 13 is supplied to the mixing tank 6 via the third chemical injection pipe 14. The polymerized plastic mixture is then filled into a drum can 15 and stored as radioactive waste.
以上の構成において、前述の各種薬剤を供給する方法と
しては一般に各種薬剤貯蔵タンクと混合槽との間に移送
用のポンプを設けて実施している。In the above configuration, the method for supplying the various chemicals described above is generally carried out by providing a pump for transfer between the various medicine storage tanks and the mixing tank.
ここで第３図に従来の薬剤供給装置の概略構成図を示す
。なお、第３図において、第２図と同一部分には同一符
号を付しその構成の説明は省略する。Here, FIG. 3 shows a schematic configuration diagram of a conventional drug supply device. In FIG. 3, the same parts as in FIG. 2 are designated by the same reference numerals, and the explanation of the structure will be omitted.
また、重合開始剤２重合促進剤２重合禁止剤ともに同様
の注入方法であるので、以下開始剤の移送装置を例にし
て説明し、他の移送装置と同一部分には同一符号を付し
、その説明は省略する。第３図において、重合開始剤は
重合開始剤貯蔵タンク９から移送ポンプ１６によって第
１の自動操作弁１７を介して計量管１８へ導かれる。こ
のとき計量管１８の下流に設けられた第２の自動操作弁
１９は閉じており、三方弁である第３の自動操作弁２０
は計量管１８と重合開始剤貯蔵タンク９との間が導通し
ている構成になっている。計量管１８の液位が上昇して
あらかじめ設定された液位に達すると計量管１８に設け
られた液位計２１によって検出され、その液位４Ｗ号２
１ａによって一第１の自動操作弁１７が閉じる。In addition, since the injection method is the same for both the polymerization initiator, polymerization accelerator, and polymerization inhibitor, the initiator transfer device will be explained below as an example, and the same parts as other transfer devices will be given the same reference numerals. The explanation will be omitted. In FIG. 3, the polymerization initiator is conducted from the polymerization initiator storage tank 9 by a transfer pump 16 via a first automatically operated valve 17 into a metering tube 18. At this time, the second automatic operation valve 19 provided downstream of the metering pipe 18 is closed, and the third automatic operation valve 20, which is a three-way valve, is closed.
The measuring tube 18 and the polymerization initiator storage tank 9 are electrically connected to each other. When the liquid level in the measuring tube 18 rises and reaches a preset liquid level, it is detected by the liquid level gauge 21 provided in the measuring tube 18, and the liquid level No. 4W 2
1a, the first automatic operation valve 17 is closed.
そして前記第２の自動操作弁１９が開し、第３の自動操
作弁２０は計量管１８と不活性ガス供給袋ｆｆｆｉ２２
との間を導通させている。これにより計量管１８内の重
合開始剤は不活性ガスによって圧送され第２の自動操作
弁１９を経て混合槽６に供給される。重合開始剤の供給
は、不活性ガス供給袋ｒｍ２２と第３の自動操作弁２０
との間に設けられた流量計２３によって不活性ガスの流
通が検知されることにより完了する。そして、重合促進
剤９重合禁止剤の各薬剤も同様の方法によって混合槽へ
定量供給される構造になっている。なお、前記計量管１
８は計量管１８内に速やかに薬剤を導入させるために上
方向から導通配管２４を介して貯蔵タンク９の気相部に
開放している。また、各薬剤が供給される間、重合反応
の進行を抑制するために混合槽は冷媒によって冷却され
ている。この冷媒は冷媒の貯蔵タンク２５から移送用の
ポンプ２Ｇによって冷凍機２７を介して混合槽の周囲に
導びかれ、この後、再び冷媒の貯蔵タンク５に導びかれ
る様に＠環している。さらに、重合開始剤の貯蔵タンク
は、重合開始剤の品質保持のため冷媒により冷却されて
いる。Then, the second automatic operation valve 19 opens, and the third automatic operation valve 20 connects the metering pipe 18 and the inert gas supply bag fffi22.
It provides continuity between the As a result, the polymerization initiator in the metering tube 18 is pumped by the inert gas and supplied to the mixing tank 6 via the second automatically operated valve 19. The polymerization initiator is supplied through an inert gas supply bag rm22 and a third automatic operation valve 20.
The process is completed when the flow of the inert gas is detected by the flow meter 23 provided between the two. The structure is such that each of the polymerization accelerators and polymerization inhibitors is also supplied in fixed quantities to the mixing tank in the same manner. Note that the measuring tube 1
8 opens into the gas phase portion of the storage tank 9 from above via a conduction pipe 24 in order to quickly introduce the medicine into the metering tube 18. Further, while each chemical is being supplied, the mixing tank is cooled with a refrigerant in order to suppress the progress of the polymerization reaction. This refrigerant is guided from the refrigerant storage tank 25 to the surroundings of the mixing tank via the refrigerator 27 by the transfer pump 2G, and is then guided again to the refrigerant storage tank 5. . Furthermore, the storage tank for the polymerization initiator is cooled with a refrigerant to maintain the quality of the polymerization initiator.
（発明が解決しようとする問題点）
以上の構成において、従来の放射性廃液の同化装置は構
造が複雑なため設備のメンテナンスに多くの労力がかか
っていた。さらに、各々の薬剤貯蔵タンクは放射線管理
区域内に設置されており、薬剤自身が危険物であるため
薬液の補給作業も制約されるばかりでなく、多くの二次
廃棄物が発生していた。(Problems to be Solved by the Invention) In the above-described configuration, the conventional radioactive waste liquid assimilation device has a complicated structure and requires a lot of effort to maintain the equipment. Furthermore, each drug storage tank was installed in a radiation-controlled area, and the drugs themselves were dangerous, which not only restricted the replenishment of drug solutions, but also generated a lot of secondary waste.
このため、第４図に示す様に貯蔵タンクのみを放射線非
管理区域に設置した例が示されている。For this reason, as shown in FIG. 4, an example is shown in which only the storage tank is installed in a radiation-free area.
ここで第４図に第３図に示した放射性廃液の同化装置の
従来例の改良例を示す。なお、第４図において、第３図
と同一部分に同一符号を付しその部分の構成の説明は省
略する。第４図において、貯蔵タンク９から薬液を混合
槽に導びく薬剤注入配管１０が従来より長くなるため、
配管中に滞留する薬剤が多くなる。そして、この配管内
にて滞留する薬剤は冷却不足となるため変質するおそれ
がある。このため、この薬剤の変質を防止するために前
部薬剤注入配管１０から貯蔵タンク９に滞留した薬剤を
再び導びく循環ライン２８が制御弁２９を介して設けら
れている。このため、これらの配管スペースが前記従来
例と比較して増加し、多くのスペースが必要となってい
る。FIG. 4 shows an improved example of the conventional radioactive waste liquid assimilation apparatus shown in FIG. 3. In FIG. 4, the same parts as those in FIG. 3 are given the same reference numerals, and the explanation of the structure of those parts will be omitted. In FIG. 4, the drug injection pipe 10 that leads the drug solution from the storage tank 9 to the mixing tank is longer than before.
More chemicals stay in the pipes. There is a risk that the chemicals remaining in this pipe may deteriorate due to insufficient cooling. Therefore, in order to prevent this drug from deteriorating in quality, a circulation line 28 is provided via a control valve 29 to guide the drug stagnant in the storage tank 9 from the front drug injection pipe 10 again. Therefore, the space for these piping is increased compared to the conventional example, and a large amount of space is required.
しかしながら、ＴＱ在の原子力発電所においては各機器
のコンパクト化が望まれており、より簡単でコンパクト
な放射性廃液の固化装置が望まれていた。However, at TQ's nuclear power plant, it is desired that each device be made more compact, and a simpler and more compact solidification device for radioactive waste liquid has been desired.
本発明の目的は、上記事情に鑑み、コンパクトでかつメ
ンテナンス性の優れた放射性廃液の同化装置を得ること
にある。In view of the above circumstances, an object of the present invention is to obtain a radioactive waste liquid assimilation device that is compact and easy to maintain.
（問題点を解決するための手段）
上記目的を達成するために、本発明においては、放射性
廃液を乾燥粉体化させた後に熱硬化性樹脂、重合開始剤
、重合促進剤を順次混合させプラスチックの固化体を形
成し１重合反応を中止させる場合は重合禁止剤を供給し
て成る放射性廃液の固化装置において、前記重合開始剤
１重合促進剤９重合禁止剤の各々の貯蔵タンクを前記熱
硬化樹脂。(Means for Solving the Problems) In order to achieve the above object, in the present invention, radioactive waste liquid is dried and powdered, and then a thermosetting resin, a polymerization initiator, and a polymerization accelerator are sequentially mixed to form a plastic. 1. When stopping the polymerization reaction by forming a solidified body of 1, in a radioactive waste liquid solidification apparatus which supplies a polymerization inhibitor, each storage tank of the polymerization initiator, 1 polymerization accelerator, and 9 polymerization inhibitor is heated to harden it. resin.
重合開始剤９重合促進剤１重合禁止剤とを混合させる混
合槽の上方に配置させ、かつ前記各々の貯蔵タンクの上
方に各々の薬剤に対応する補給タンクを配置させ、この
補給タンクと前記各々の貯蔵タンクを上り勾配の無い薬
液補給配管にて結合させ、前記貯蔵タンクと混合槽を薬
液計量装置を介して上り勾配の無い薬液注入配管にて結
合させて成ることを特徴とする放射性廃液の固化装置を
提供する。A polymerization initiator, a polymerization accelerator, and a polymerization inhibitor are disposed above a mixing tank for mixing, and a supply tank corresponding to each chemical is disposed above each of the storage tanks, and this supply tank and each of the above-mentioned A storage tank for radioactive waste liquid is connected with a chemical solution supply pipe having no upward slope, and the storage tank and the mixing tank are connected via a chemical liquid measuring device with a chemical liquid injection pipe having no upward slope. Provide solidification equipment.
（作 用）
この様に構成された放射性廃液の固化装置においては、
各種薬剤タンクを混合槽の上方に配置させ、自然な流れ
と不活性ガスによる圧送によって各種薬剤を混合槽に導
びく様にしたので動的機器である移送ポンプが削除でき
、メンテナンス性を向上させることができ、さらにポン
プスペースの削減から設備利用率をも向上させることが
できる。(Function) In the radioactive waste liquid solidification device configured in this way,
The various chemical tanks are placed above the mixing tank, and the various chemicals are guided to the mixing tank by natural flow and pressure-feeding with inert gas, which eliminates the need for a transfer pump, which is a dynamic device, and improves maintenance. Furthermore, the equipment utilization rate can be improved by reducing the pump space.
そして、薬剤の補給を放射線非管理区域内にて実施でき
るので、二次廃棄物の発生がなく、作業者の作業性を向
上させることができる。Furthermore, since the medicine can be replenished in a radiation-free area, no secondary waste is generated, and the work efficiency of the worker can be improved.
（実施例） 以下、本発明の一実施例を第１図を参照して説明する。(Example) An embodiment of the present invention will be described below with reference to FIG.
ここで第１図に本発明の放射性廃液の同化装置の要部を
示す系統図を示す。なお、第１図において、第３図と同
一部分には同一符号を付し、その部分の構成の説明は省
略する。また、重合開始剤１重合促進剤８重合禁止剤と
ともに同様の注入方法であるので、以下重合開始前の移
送装置を例にして説明し、他の移送装置と同一部分には
同一符号を付し、その説明は省略する。重合開始剤は重
合開始剤貯蔵タンク９からその下方に配置される計量管
１８へ１第１の自動操作弁１７を介して導かれる。この
とき前記計量管１８の下流に設けられた第２の自動操作
弁１９は閉じており、三方弁である第３の自動操作弁２
０は計量管１８と重合開始剤貯蔵タンク９との間を導通
させている。計量管１８の液位が上昇してあらかじめ設
定された液位に達すると液位針２１によって検出され、
その液位信号２１ａによって第１の自動操作弁１７が閉
じるように構成されている。次に、第２の自動操作弁１
９が開し、第３の自動操作弁２０は計量管１８と不活性
ガス供給装置２２との間が導通する。これにより計量管
１８内の重合開始剤は計量管１８のさらに下方に配置さ
れる混合槽６へ供給され、不活性ガス供給装置２２と第
３の自動操作弁２０との間に設けられた流量計２３によ
って不活性ガスの流通が検知されることにより重合開始
剤の供給は完了する。Here, FIG. 1 shows a system diagram showing the main parts of the radioactive waste liquid assimilation apparatus of the present invention. In FIG. 1, the same parts as in FIG. 3 are given the same reference numerals, and the explanation of the structure of the parts will be omitted. In addition, since the injection method is the same as that of the polymerization initiator, polymerization accelerator, and polymerization inhibitor, we will explain the transfer device before the start of polymerization as an example, and the same parts as other transfer devices will be given the same reference numerals. , the explanation thereof will be omitted. The polymerization initiator is led from the polymerization initiator storage tank 9 to a metering tube 18 disposed below it via a first automatic valve 17. At this time, the second automatic operation valve 19 provided downstream of the metering pipe 18 is closed, and the third automatic operation valve 2, which is a three-way valve, is closed.
0 establishes continuity between the metering tube 18 and the polymerization initiator storage tank 9. When the liquid level in the measuring tube 18 rises and reaches a preset liquid level, it is detected by the liquid level needle 21,
The first automatically operated valve 17 is configured to close in response to the liquid level signal 21a. Next, the second automatic operation valve 1
9 opens, and the third automatically operated valve 20 establishes continuity between the metering pipe 18 and the inert gas supply device 22. As a result, the polymerization initiator in the metering tube 18 is supplied to the mixing tank 6 located further below the metering tube 18, and the flow rate provided between the inert gas supply device 22 and the third automatic operation valve 20 is increased. The supply of the polymerization initiator is completed when the flow of the inert gas is detected by the total 23.
なお、前記重合開始剤貯蔵タンク９１重合促進剤貯蔵タ
ンク１１９重合禁止剤貯蔵タンク１３と混合槽６とを結
合する第１〜第３の薬剤注入配管１０゜１２、１４は各
種薬剤を移送ポンプなしに前記混合槽に移送させるため
に、上り勾配が無いように構成されている。また、重合
開始剤貯蔵タンク９に重合開始剤を補給するには、放射
線非管理区域内で重合開始剤補給タンク３１内に必要量
の重合開始剤を投入した後、重合開始剤補給タンク３１
の下流側の自動操作弁３２を開けると、重合開始剤は、
流量計３３を経由して重合開始剤貯蔵タンク９内に補給
される。このとき、流量計３３の検出により重合υＮ始
剤の補給が完了すると重合開始剤補給完了（８号３３Ω
が流量計３３から発信し、自動操作弁３２が閉する。Note that the first to third chemical injection pipes 10° 12, 14 connecting the polymerization initiator storage tank 91, polymerization accelerator storage tank 119, polymerization inhibitor storage tank 13, and mixing tank 6 do not have pumps for transferring various chemicals. In order to transfer the liquid to the mixing tank, the structure is such that there is no upward slope. In addition, in order to replenish the polymerization initiator storage tank 9 with the polymerization initiator, after putting the necessary amount of polymerization initiator into the polymerization initiator replenishment tank 31 in the non-radiation controlled area,
When the automatic operation valve 32 on the downstream side of is opened, the polymerization initiator is
The polymerization initiator storage tank 9 is replenished via the flow meter 33. At this time, when the supply of the polymerization υN initiator is completed as detected by the flow meter 33, the supply of the polymerization initiator is completed (No. 8 33Ω
is transmitted from the flow meter 33, and the automatic operation valve 32 closes.
なお、前記重合開始剤補給タンク３１１重合開始剤貯蔵
タンク９とを結合する薬液補給配管３４は薬液移送ポン
プなしに前記重合開始剤貯蔵タンクに移送させるために
、上り勾配が無いように構成されている。Note that the chemical solution supply pipe 34 connecting the polymerization initiator supply tank 311 to the polymerization initiator storage tank 9 is configured to have no upward slope in order to transfer the chemical solution to the polymerization initiator storage tank without using a chemical transfer pump. There is.
また、前記重合開始剤貯蔵タンク９には液位計３５が設
けられており、薬液の過剰な補給を防止するために、重
合開始剤貯蔵タンク９の液位が一定値以上では液位計３
５から制御信号３５ａが発信し、薬液補給配管３４の自
動操作弁３２が開しないよう制御されている。Further, the polymerization initiator storage tank 9 is provided with a liquid level gauge 35, and in order to prevent excessive replenishment of the chemical solution, the liquid level gauge 35
A control signal 35a is transmitted from 5, and the automatic operation valve 32 of the chemical solution supply pipe 34 is controlled not to open.
以上の構成によって１本発明に係る放射性廃液の固化装
置によれば、移送ポンプを削除したことによってよりコ
ンパクトになり、設備利用率を向上させることができる
。さらには各種薬剤注入配管の上り勾配をなくし、さら
に不活性ガスによる圧送も従来と同様に実施できるので
、確実に各種薬液を混合槽内に注入させることができる
。また、機器がコンパクトになり、動的機器を削減させ
たのでメンテナンス性をより向上させることができる。With the above configuration, the radioactive waste liquid solidification apparatus according to the present invention can be made more compact by eliminating the transfer pump, and the equipment utilization rate can be improved. Furthermore, the upward slope of the various chemical injection piping is eliminated, and furthermore, the inert gas can be used for pressure feeding in the same manner as before, so that various chemical solutions can be reliably injected into the mixing tank. Furthermore, since the equipment has become more compact and the number of moving equipment has been reduced, maintainability can be further improved.
また薬液の補給も放射線非管理区域でできるので、二次
廃棄物の発生もなく、作業を容易にすることができる。In addition, replenishment of chemical solutions can be done in radiation-free areas, so no secondary waste is generated, making work easier.
本発明によれば各種薬液タンクを混合槽の上方に配置さ
せ、移送ポンプを削除して薬液の移送を。According to the present invention, the various chemical liquid tanks are placed above the mixing tank, and the transfer pump is eliminated to transfer the chemical liquid.
液体の自然な流れと不活性ガスによる圧送によって実施
したので、放射性廃液の固化装置がコンパクトになり設
備利用率が向上でき、さらには動的機器を削減させたの
でメンテナンス性をも向上させることができる。また、
薬剤の補給も放射線非管理区域内でできるため、二次廃
棄物の発生もなく、作業性を向上させることができる。Because the process was carried out using a natural flow of liquid and pressure-feeding using inert gas, the radioactive waste liquid solidification equipment was made more compact and the equipment utilization rate was improved.Furthermore, the number of moving equipment was reduced, which also improved maintainability. can. Also,
Since medicines can be replenished in a radiation-free area, no secondary waste is generated and work efficiency can be improved.
第１図は本発明の一実施例に係る放射性廃液の固化装置
の要部を示す概略系統図、第２図は従来の放射性廃液の
固化装置を示す概略系統図、第３図は従来の放射性廃液
の同化装置に設けられている各種薬液移送装置を示す概
略系統図、第４図は第３図に示した放射性廃液の固化装
置の改良例を示す概略系統図である。
６・・・混合槽 ７・・・熱硬化性樹脂
タンク８・・・樹脂移送配管 ９・・・重合開
始剤貯蔵タンク１１・・・重合促進剤貯蔵タンク １３
・・・重合禁止剤貯蔵タンク１７・・・第１の自動操作
弁 】８・・・計量管１９・・・第２の自動操作弁
２０・・・第３の自動操作弁２１・・・液位計
２２・・・不活性ガス供給装置３１・・
・重合開始剤補給タンク ３３・・・流量計３４・・・
重合開始剤補給管
代理人 弁理士 則 近 憲 缶
周 三俣弘文
第１図
第２図
第３図Fig. 1 is a schematic system diagram showing the main parts of a radioactive waste liquid solidification device according to an embodiment of the present invention, Fig. 2 is a schematic system diagram showing a conventional radioactive waste liquid solidification device, and Fig. 3 is a schematic system diagram showing the main parts of a radioactive waste liquid solidification device according to an embodiment of the present invention. A schematic system diagram showing various chemical liquid transfer devices provided in the waste liquid assimilation device, and FIG. 4 is a schematic system diagram showing an improved example of the radioactive waste liquid solidification device shown in FIG. 3. 6...Mixing tank 7...Thermosetting resin tank 8...Resin transfer piping 9...Polymerization initiator storage tank 11...Polymerization accelerator storage tank 13
...Polymerization inhibitor storage tank 17...First automatic operation valve ]8...Measuring tube 19...Second automatic operation valve 20...Third automatic operation valve 21...Liquid position meter
22...Inert gas supply device 31...
・Polymerization initiator supply tank 33...Flow meter 34...
Polymerization initiator supply agent Patent attorney Nori Chika Hirofumi Mitsumata Figure 1 Figure 2 Figure 3
Claims (3)
、重合開始剤、重合促進剤を順次混合させプラスチック
の固化体を形成し、重合反応を中止させる場合は重合禁
止剤を供給して成る放射性廃液の固化装置において、前
記重合開始剤、重合促進剤、重合禁止剤の各々の貯蔵タ
ンクを前記熱硬化樹脂、重合開始剤、重合促進剤、重合
禁止剤とを混合させる混合槽の上方に配置させ、かつ前
記各々の貯蔵タンクの上方に各々の薬剤に対応する補給
タンクを配置させ、この補給タンクと前記各々の貯蔵タ
ンクを上り勾配の無い薬液補給配管にて結合させ、前記
貯蔵タンクと混合槽を薬液計量装置を介して上り勾配の
無い薬液注入配管にて結合させて成ることを特徴とする
放射性廃液の固化装置。(1) After drying and pulverizing the radioactive waste liquid, a thermosetting resin, a polymerization initiator, and a polymerization accelerator are sequentially mixed to form a solidified plastic, and if the polymerization reaction is to be stopped, a polymerization inhibitor is supplied. In a radioactive waste liquid solidification device consisting of a storage tank for each of the polymerization initiator, polymerization accelerator, and polymerization inhibitor, a mixing tank for mixing the thermosetting resin, polymerization initiator, polymerization accelerator, and polymerization inhibitor; A replenishment tank corresponding to each drug is disposed above each of the storage tanks, and this replenishment tank and each of the storage tanks are connected by a chemical replenishment piping with no upward slope, A solidification device for radioactive waste liquid, characterized in that a tank and a mixing tank are connected through a chemical liquid metering device and a chemical liquid injection pipe with no upward slope.
とを特徴とする特許請求の範囲第１項記載の放射性廃液
の固化装置。(2) The radioactive waste liquid solidification apparatus according to claim 1, wherein the supply tank is installed in a non-radiation controlled area.
管と、この計量管の上流側に設けられた計量管内に貯留
する薬液が一定量になると閉動作する第１の弁と、前記
計量管の下流側に設けられ計量管内に貯留する薬液が一
定量になると開動作する第２の弁と、第２の弁が開動作
した後に不活性ガスを前記計量管内に注入する不活性ガ
ス注入装置とから成ることを特徴とする特許請求の範囲
第１項または第２項記載の放射性廃液の固化装置。(3) The chemical liquid metering device includes a measuring pipe connected to the chemical liquid injection pipe, a first valve that closes when a certain amount of chemical liquid stored in the measuring pipe is provided on the upstream side of the measuring pipe, and the above-mentioned. a second valve provided on the downstream side of the metering tube that opens when a certain amount of chemical solution stored in the metering tube is reached; and an inert gas that injects inert gas into the metering tube after the second valve opens. An apparatus for solidifying radioactive waste liquid according to claim 1 or 2, characterized in that it comprises an injection device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61258360A JPH0812276B2 (en) | 1986-10-31 | 1986-10-31 | Device for solidifying radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61258360A JPH0812276B2 (en) | 1986-10-31 | 1986-10-31 | Device for solidifying radioactive waste liquid |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63113398A true JPS63113398A (en) | 1988-05-18 |
| JPH0812276B2 JPH0812276B2 (en) | 1996-02-07 |
Family
ID=17319152
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61258360A Expired - Lifetime JPH0812276B2 (en) | 1986-10-31 | 1986-10-31 | Device for solidifying radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0812276B2 (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5696300A (en) * | 1979-12-28 | 1981-08-04 | Ebara Mfg | Method and apparatus for solidifying radioactive waste |
-
1986
- 1986-10-31 JP JP61258360A patent/JPH0812276B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5696300A (en) * | 1979-12-28 | 1981-08-04 | Ebara Mfg | Method and apparatus for solidifying radioactive waste |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0812276B2 (en) | 1996-02-07 |
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