JPS60213892A - Purifying system of high-radioactive solid waste storage pool - Google Patents
Purifying system of high-radioactive solid waste storage poolInfo
- Publication number
- JPS60213892A JPS60213892A JP6903484A JP6903484A JPS60213892A JP S60213892 A JPS60213892 A JP S60213892A JP 6903484 A JP6903484 A JP 6903484A JP 6903484 A JP6903484 A JP 6903484A JP S60213892 A JPS60213892 A JP S60213892A
- Authority
- JP
- Japan
- Prior art keywords
- filter
- activated carbon
- solid waste
- pool
- waste storage
- 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
Landscapes
- Processing Of Solid Wastes (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】
〔発明の利用分野〕
本発明は、原子力発電所の放射性固体廃棄物貯蔵プール
の水浄化に係わり、特に可燃性濾材を使用し、廃滅材の
減容と被曝低減を計った廃滅材処分を行に好適な高放射
能固体廃棄物貯蔵プールの浄化系に関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to water purification of a radioactive solid waste storage pool in a nuclear power plant, and in particular uses a combustible filter medium to reduce the volume of waste material and reduce radiation exposure. This invention relates to a purification system for a highly radioactive solid waste storage pool suitable for disposing of waste materials.
本発明の従来例を第1図に示すサイトバンカ水浄化フロ
ー及び第2図濾過塔詳細にて説明する。A conventional example of the present invention will be explained with reference to the site bunker water purification flow shown in FIG. 1 and the details of the filtration tower shown in FIG.
原子炉内で発生した高放射性固定廃棄物は一旦使用済燃
料プールに貯蔵され、一定量後、当該プール1に貯蔵し
、その後切断されるが、その過程でプール水中に溶出す
る放射性浮遊粒子或いは放射性フラッドでプール水が汚
濁する。プール水の汚濁を浄化するため、スキマサージ
タンク2にプール水をオーバーフローにて導いた後、プ
ール水循環ポンプ3にて、プール1の側壁に、水没の状
態で設置されている多孔管形濾過塔4に導水し、放射性
浮遊粒子を分離する。Highly radioactive fixed waste generated in a nuclear reactor is temporarily stored in a spent fuel pool, and after a certain amount is stored in the pool 1, it is then cut, but in the process, radioactive suspended particles or Radioactive flood pollutes pool water. In order to purify the pool water from contamination, after the pool water is overflowed into the skimmer surge tank 2, the pool water circulation pump 3 is used to filter the porous tubular filtration tower submerged on the side wall of the pool 1. 4 to separate radioactive suspended particles.
濾過器詳細に示す多孔管6は濾過時間の経過で濾過同形
物にて目詰りして行き、最終には通水不能&こ至る。不
能時点で濾過塔4の上蓋7を開設し多孔管を天上クレー
ン5で取り出し固体廃棄物ドラム缶に収納し貯蔵庫に輸
送保管する。The porous tube 6 shown in detail of the filter becomes clogged with filtering substances as the filtration time passes, and eventually becomes unable to pass water. When the filtering tower 4 becomes unavailable, the upper cover 7 is opened, and the perforated pipe is taken out by the overhead crane 5, stored in a solid waste drum, and transported and stored in a storage warehouse.
目詰り後の多孔管6の廃棄は固体廃棄物の増大を来すこ
と及び固体廃棄物用ドラム缶への収納時乾燥状態にしな
い限りドラム缶の腐食損傷を来す危具が欠点としてあっ
た。 −
〔発明の目的〕
本発明の目的は、−濾過塔から発生する二次廃棄物の低
減及び濾過にて除去した放射性固形粒子による作業員の
被曝低減を計り濾過機能に加えて濁度因子のイオウ状粒
子の除去を安価な施設で行うに好適な高放射能固体廃棄
物貯蔵プールの浄化系を提供するにある。Disposal of the perforated tube 6 after clogging has disadvantages in that it increases the amount of solid waste and that unless it is kept dry when stored in a drum for solid waste, there is a risk of corrosion damage to the drum. - [Objective of the Invention] The object of the present invention is to - reduce the secondary waste generated from the filtration tower and reduce the exposure of workers to the radioactive solid particles removed by filtration; An object of the present invention is to provide a purification system for a highly radioactive solid waste storage pool suitable for removing sulfur-like particles in an inexpensive facility.
活性炭は、水のボリッシャとしての機能、濁度粒子の吸
着、活性炭層とした場合の濾過機能を持つこと、導電率
の低いプール中のF e Z++。Activated carbon has the function of water bolizer, adsorption of turbidity particles, filtration function when used as an activated carbon layer, and F e Z++ in pools with low conductivity.
Fe 3+十を電気化学的酸化還元出来る特性、或いは
可燃性である特徴を利用し、従来装置の多孔管廃棄物の
増大、ドラム缶貯蔵までのハンドリング時の被曝、及び
プール水中下での作業時の透明度確保等の難点を流動活
性炭を使って解決策を案出した。Utilizing the electrochemical oxidation-reduction properties or combustibility of Fe 3+, it can be used to reduce the amount of porous pipe waste generated by conventional equipment, the exposure during handling until storage in drums, and when working under water in pools. We devised a solution to problems such as ensuring transparency by using fluidized activated carbon.
本発明の一実施例を第3図及び第4図にて説明する。 An embodiment of the present invention will be described with reference to FIGS. 3 and 4.
通常の濾過運転中はスキマサージタンク2に高放射性固
体廃棄物貯蔵プール1の汚濁水がオーバーフローし取り
入れられる。取り入れられた汚濁水は循環ポンプ3及び
弁4,5を通り活性炭充填形濾過塔に導かれ汚濁水中の
浮遊固形物、Fg2+8.Fe””等のイオンを除去す
る。本通常運転時は弁7,8は閉の状態である。一方、
活性炭充填形濾過塔6は粒径0.5〜51m111の無
煙炭或いは破砕炭を流路長1000m+程度確保し充填
されており、濾過塔ケーシング16及び電極17を十−
の電極とし低導電率のプール水の導電率を活性炭により
高め電極間距離を少さ゛くし濁度イオンの除去を必要と
する際、使用する。尚、濾過を継続してゆき活性炭濾過
層の閉塞が進み、損失水頭が上がり、循環ポンプ3にて
の循環量確保が不可能になった場合、濾過を中止し、活
性炭15の自動搬出を行う。自動搬出は弁4,5を閉止
し弁7゜8を開にし活性炭を水流に乗せて水と活性炭を
分離するストレーナ9に導く2分離後の活性炭は貯留ド
ラム缶10に捕集し再利用するかもしくは焼却炉に輸送
し焼却し極少の放射性廃棄灰とする。During normal filtration operation, polluted water from the highly radioactive solid waste storage pool 1 overflows and is taken into the skimmer surge tank 2. The polluted water taken in is led to an activated carbon-filled filtration tower through a circulation pump 3 and valves 4 and 5, where suspended solids in the polluted water, Fg2+8. Ions such as Fe"" are removed. During normal operation, valves 7 and 8 are closed. on the other hand,
The activated carbon-filled filtration tower 6 is filled with anthracite or crushed coal having a particle size of 0.5 to 51 m111 with a flow path length of about 1000 m+, and the filter tower casing 16 and electrodes 17 are
It is used as an electrode when it is necessary to increase the conductivity of pool water with low conductivity using activated carbon, reduce the distance between the electrodes, and remove turbidity ions. In addition, as the filtration continues, if the activated carbon filtration layer becomes increasingly clogged, the head loss increases, and it becomes impossible to ensure the circulation volume with the circulation pump 3, the filtration is stopped and the activated carbon 15 is automatically discharged. . For automatic unloading, valves 4 and 5 are closed, valves 7 and 8 are opened, and the activated carbon is placed in a water stream and guided to a strainer 9 that separates water and activated carbon.2 The activated carbon after separation is collected in a storage drum 10 and reused. Or transport it to an incinerator and incinerate it to produce a very small amount of radioactive waste ash.
一方、分離後の汚′水は液体廃棄物処理系の廃液集取タ
ンク11に導き処理される。On the other hand, the separated wastewater is led to the waste liquid collection tank 11 of the liquid waste treatment system and treated.
本発明によれば、高放射性固体廃棄物の当該プールへの
搬入、及び当該プールでの切断等プール内での取扱い操
作時にプール水中に懸濁する浮遊固形物(固体廃棄物に
付着して持ち込まれるクラッドや金属イオン粒子)を電
解活性炭濾過等にて濾過、吸着除去するとともに濾過さ
れた高放射性固体物を自動的にドラム缶に移すことによ
り作業員の被曝低減を計り得る。又、廃濾材の活性炭は
焼却炉にて焼却できるので、最終廃棄物の減容大なる効
果がある。According to the present invention, suspended solids suspended in the pool water (adhered to the solid waste and brought in) when highly radioactive solid waste is brought into the pool and handled in the pool such as cutting. The radiation exposure of workers can be reduced by filtering and adsorbing and removing the cladding and metal ion particles) using electrolytic activated carbon filtration, etc., and automatically transferring the filtered highly radioactive solids to drums. Furthermore, since the activated carbon used as waste filter media can be incinerated in an incinerator, there is a great effect of reducing the volume of final waste.
第1図は従来の高放射性固体廃棄物貯蔵プールの浄化フ
ロー図、第2図は従来用いられている多孔管式濾過塔の
構造図、第3図は本発明の高放射性固体廃棄物貯蔵プー
ルの浄化系統図、第4図は本発明の浄化系に用いる電解
活性炭濾過塔の基本構造図である。
l・・・廃棄物貯蔵プール、2・・・スキマサージタン
ク、3・・・循環ポンプ、4,5,7,8・・・濾過工
程と濾材取出切替弁、6・・・電解活性炭濾過塔、9・
・・濾材分離ストレーナ、10・・・固体廃棄物貯留ド
ラム缶、13・・・濾過・濾材取出配管、14・・・濾
液入口ノズ摺3日Fig. 1 is a purification flow diagram of a conventional highly radioactive solid waste storage pool, Fig. 2 is a structural diagram of a conventionally used porous tubular filter tower, and Fig. 3 is a highly radioactive solid waste storage pool of the present invention. Fig. 4 is a basic structural diagram of an electrolytic activated carbon filtration tower used in the purification system of the present invention. 1...Waste storage pool, 2...Skimmer surge tank, 3...Circulation pump, 4, 5, 7, 8...Filtration process and filter medium extraction switching valve, 6...Electrolytic activated carbon filtration tower , 9・
... Filter media separation strainer, 10... Solid waste storage drum, 13... Filtration/filter media extraction piping, 14... Filtrate inlet nozzle 3 days
Claims (1)
り入れるスキマサージタンク、バンカプール水を濾過器
を経て、浄化水をプールに戻す循環ポンプ浮遊粒子を濾
過する活性炭濾過器、濾過器中の活性炭を取り出し廃棄
処分を行う為の活性炭回収器及びこれらの流路となる配
管、弁からなる閉ループ系において、濾過器をプール水
水没の状態のまま廃滅過材のみを自動取り出し出来、作
業員の放射能被曝低減を計るとともに、焼却可能濾過材
を使用した、又、焼却不可能な固体廃棄物の無い濾過器
を特徴とする高放射性固体廃棄物貯蔵ブーツ吹浄化系。1. A skimmer surge tank that takes in the waste storage pool water contaminated with radioactive suspended particles, a circulation pump that passes the banker pool water through a filter and returns purified water to the pool. An activated carbon filter that filters suspended particles, and activated carbon in the filter. In a closed-loop system consisting of an activated carbon recovery device for removal and disposal, and piping and valves that serve as the flow path for these, only the waste materials can be automatically removed while the filter is submerged in pool water, reducing radiation exposure by workers. This highly radioactive solid waste storage boot blow purification system is designed to reduce radiation exposure and is characterized by a filter that uses an incinerator and does not contain solid waste that cannot be incinerated.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6903484A JPS60213892A (en) | 1984-04-09 | 1984-04-09 | Purifying system of high-radioactive solid waste storage pool |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP6903484A JPS60213892A (en) | 1984-04-09 | 1984-04-09 | Purifying system of high-radioactive solid waste storage pool |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS60213892A true JPS60213892A (en) | 1985-10-26 |
Family
ID=13390889
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP6903484A Pending JPS60213892A (en) | 1984-04-09 | 1984-04-09 | Purifying system of high-radioactive solid waste storage pool |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS60213892A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2016065787A (en) * | 2014-09-24 | 2016-04-28 | 株式会社神戸製鋼所 | Contaminated water treatment method and contaminated water treatment system |
-
1984
- 1984-04-09 JP JP6903484A patent/JPS60213892A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2016065787A (en) * | 2014-09-24 | 2016-04-28 | 株式会社神戸製鋼所 | Contaminated water treatment method and contaminated water treatment system |
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