JPS6243520B2 - - Google Patents
Info
- Publication number
- JPS6243520B2 JPS6243520B2 JP12941179A JP12941179A JPS6243520B2 JP S6243520 B2 JPS6243520 B2 JP S6243520B2 JP 12941179 A JP12941179 A JP 12941179A JP 12941179 A JP12941179 A JP 12941179A JP S6243520 B2 JPS6243520 B2 JP S6243520B2
- Authority
- JP
- Japan
- Prior art keywords
- drum
- radioactive waste
- slurry
- pump
- drain pipe
- 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
Links
- 239000002901 radioactive waste Substances 0.000 claims description 23
- 239000002002 slurry Substances 0.000 claims description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 11
- 238000003860 storage Methods 0.000 claims description 8
- 238000012856 packing Methods 0.000 claims description 3
- 230000018044 dehydration Effects 0.000 description 9
- 238000006297 dehydration reaction Methods 0.000 description 9
- 239000003456 ion exchange resin Substances 0.000 description 4
- 229920003303 ion-exchange polymer Polymers 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 3
- 239000011347 resin Substances 0.000 description 3
- 229920005989 resin Polymers 0.000 description 3
- 238000004891 communication Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000001035 drying Methods 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000002203 pretreatment Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 238000004064 recycling Methods 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000012798 spherical particle Substances 0.000 description 1
- 238000011282 treatment Methods 0.000 description 1
- 239000011800 void material Substances 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
Description
【発明の詳細な説明】
本発明は放射性廃棄物スラリーの脱水ドラム詰
法に係る。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for packing a radioactive waste slurry into a dewatering drum.
従来、例えば使用ずみイオン交換樹脂の如き放
射性廃棄物を処理するには、遠心脱水処理による
水分の除去、加熱乾燥処理による脱水等の前処理
を行うことが必要であり、そのための遠心分離機
薄膜式乾燥機等の特別の機器を必要とし、その上
それらの乾燥手段から廃棄用のドラム缶に脱水ず
みの放射性廃棄物を移す作業が必要であつた。ま
た脱水した放射性廃棄物の廃棄用のドラムに移す
作業中に、廃棄物を散乱させるおそれがあつた。 Conventionally, in order to treat radioactive waste such as used ion exchange resin, it has been necessary to perform pre-treatments such as removing water by centrifugal dehydration and dehydration by heating and drying. This required special equipment such as dryers, and it was also necessary to transfer the dehydrated radioactive waste from these drying means to drums for disposal. Additionally, there was a risk of scattering waste during the process of transferring dehydrated radioactive waste to a drum for disposal.
本発明は上記の事情に基きなされたもので、脱
水のための特別の機器を必要とせず、廃棄用のド
ラム缶への放射性廃棄物の充填と脱水とを同時に
行うことができる放射性廃棄物のスラリの脱水ド
ラム詰装置を得ることを目的としている。 The present invention has been made based on the above circumstances, and is a slurry of radioactive waste that does not require special equipment for dewatering and can simultaneously perform the filling of radioactive waste into drums for disposal and dewatering. The purpose of this project is to obtain a dehydration drum filling device.
以下本発明の詳細を説明する。第１図において
放射性廃棄物貯蔵タンク１内には、放射性廃棄物
スラリＳが貯蔵されており、このスラリは、ポン
プ２により管路３を経由して飛散防止カバー４に
開口端を係合させたドラム缶５に供給されてい
る。 The details of the present invention will be explained below. In FIG. 1, a radioactive waste slurry S is stored in a radioactive waste storage tank 1, and this slurry is passed through a pipe line 3 by a pump 2 and its open end is brought into engagement with a scattering prevention cover 4. It is supplied to a drum can 5.
ドラム缶５からは、端末にスラリ中の固形分を
通さないフイルタ６を有する排水管７を介してポ
ンプ８によりスラリ中の移送水が除去されてい
る。除去された移送水はタンク１に環流される。
而して、前記供給される放射性廃棄物スラリ流量
を一定とし、除去される移送水流量を前記スラリ
流量中の移送水流量より大としてある。 Transfer water in the slurry is removed from the drum 5 by a pump 8 via a drain pipe 7 having a filter 6 at its end that does not allow solids in the slurry to pass through. The removed transfer water is recycled to tank 1.
The flow rate of the supplied radioactive waste slurry is kept constant, and the flow rate of the transferred water to be removed is set to be larger than the flow rate of the transferred water in the slurry flow rate.
上記の如くすれば、放射性廃棄物スラリはドラ
ム缶中に投入されるにつれその中の移送水を除去
されるから、放射性廃棄物スラリの脱水と脱水ず
みの放射性廃棄物のドラム缶充填とを同時に進行
させることができる。 By doing the above, since the transferred water in the radioactive waste slurry is removed as it is put into the drum, the dehydration of the radioactive waste slurry and the filling of the dehydrated radioactive waste into the drum can proceed simultaneously. be able to.
上記の如くして放射性廃棄物の充填を完了した
ドラム缶５は、カバー４の大気連通バルブ９を開
いてドラム缶内を大気圧とした後、ドラム缶昇降
台１０により下降され、排水管７はドラム缶中に
充填された放射性廃棄物中から引抜かれる。 The drum 5, which has been filled with radioactive waste as described above, opens the atmosphere communication valve 9 of the cover 4 to bring the inside of the drum to atmospheric pressure, and then is lowered by the drum lifting platform 10, and the drain pipe 7 is opened inside the drum. extracted from radioactive waste filled in
次いで、昇降台１０の車輪１１により昇降台１
０と共にドラム缶５を図示しないキヤツピング装
置を設置した場所に移し、ドラム缶５にキヤツプ
シールを施し、保管場所に運び保管する。 Next, the elevator platform 1 is lifted up by the wheels 11 of the elevator platform 10.
0 and the drum 5 are moved to a location where a capping device (not shown) is installed, a cap seal is applied to the drum 5, and the drum 5 is transported to a storage location and stored.
上記のように本発明によれば、脱水のための特
別の機器を必要とせず、またそれらの機器からの
脱水ずみ放射性廃棄物のドラム缶への移行を行う
ことなく、脱水と充填とを同時に行うことができ
る。なお、排水管７を上昇させることによつても
排水管の引抜きを行うことができる。 As described above, according to the present invention, dehydration and filling can be performed simultaneously without requiring special equipment for dehydration and without transferring dehydrated radioactive waste from such equipment to drums. be able to. Note that the drain pipe can also be pulled out by raising the drain pipe 7.
以下に実際例について説明する。原子力発電所
から発生する主な廃棄物の一つとして、イオン交
換樹脂があるが、これは現在スラリー状としてタ
ンク貯蔵されている。しかし、より安定な貯蔵手
段としては脱水してドラム缶詰にして貯蔵するこ
とが考らられる。 An actual example will be explained below. One of the main wastes generated from nuclear power plants is ion exchange resin, which is currently stored in tanks as a slurry. However, as a more stable storage method, dehydration and storage in drum cans may be considered.
このようなイオン交換樹脂の貯蔵に上記本発明
の脱水、ドラム詰法を適用すれば次の通りであ
る。この場合、処理の律速はドラム缶一ぽいに樹
脂が充填された状態での樹脂層を通じての水の流
量となる。 The dehydration and drum packing method of the present invention described above is applied to the storage of such ion exchange resins as follows. In this case, the rate determining factor for the treatment is the flow rate of water through the resin layer when the entire drum is filled with resin.
イオン交換樹脂は平均粒径が0.7mmの球形粒子
で、容器に充填した場合の空間率は約0.38程度と
なり、樹脂の圧力損失△Ｐは、例えばスラリー流
量５m3／hrの場合につき算出すれば、
△Ｐ＝６ｆμ２（１−ε）／ｇｃφｃＤｐε２
ｆ＝５／Ｒ＝５．６（１−ε）μ／φｃＤｐμ
から、△Ｐ＝1104Kg／m2＝0.11Kg／cm2
が得られる。すなわち、移送水を除去するポンプ
８の吸込み揚程の圧力損失負担分は上記の0.11
Kg／cmであり、特別に大きな吸込み揚程のポンプ
を準備する必要はない。 The ion exchange resin is a spherical particle with an average particle size of 0.7 mm, and the void ratio when filled in a container is approximately 0.38.The pressure loss △P of the resin is calculated for a slurry flow rate of 5 m 3 /hr, for example. , △P=6fμ 2 (1-ε)/gcφcD p ε 2 f=5/R=5.6(1-ε)μ/φ c D p μ , △P=1104Kg/m 2 =0.11Kg/ cm 2 is obtained. In other words, the pressure loss burden of the suction head of the pump 8 that removes the transferred water is 0.11 above.
Kg/cm, so there is no need to prepare a pump with a particularly large suction head.
第２図は本発明により構成した連続的に脱水を
実施するための装置を示している。 FIG. 2 shows an apparatus for carrying out continuous dewatering constructed according to the invention.
この図において、第１図のカバー４および昇降
台１０に相当するカバーおよび昇降台が図には３
箇のみ４ａ〜４ｃ，１０ａ〜１０ｃとして示すよ
うにそれぞれ複数箇設けられている。この数は、
キヤツピング装置においてキヤツプシールが施さ
れるのに必要な時間と、脱水充填に必要な時間と
を考慮して定める。１２ａ〜１２ｃはスラリー供
給開閉弁１３ａ〜１３ｃは排水管開閉弁を示す。 In this figure, a cover and a platform corresponding to the cover 4 and platform 10 in FIG.
A plurality of parts are respectively provided as shown as 4a to 4c and 10a to 10c. This number is
It is determined by considering the time required for sealing the cap in the capping device and the time required for dewatering and filling. 12a to 12c are slurry supply on-off valves 13a to 13c are drain pipe on-off valves.
上記構成の装置においては、カバー４ａ〜４ｃ
の何れか一つによつて脱水を行い、他の一つにお
いてドラム缶のセツテイングを行い、さらに他の
一つにおいては脱水充填ずみのドラム缶の離脱が
行われる。離脱させたドラム缶は移動させてキヤ
ツプシールが施される、第２図において、５ａは
セツテイング中のドラム缶、５ｂは脱水充填中の
ドラム缶、５ｃは離脱され移動中のドラム缶をそ
れぞれ示している。 In the device with the above configuration, the covers 4a to 4c
Dehydration is carried out in one of these, setting of the drum is carried out in the other, and removal of the dehydrated and filled drum is carried out in the other one. The removed drum is moved and a cap seal is applied. In FIG. 2, 5a shows the drum being set up, 5b shows the drum being dehydrated and filled, and 5c shows the drum being removed and being moved.
なお、本発明は上記実施例のみに限定されな
い。すなわち、脱水した移送水のタンク１への環
流は処理水量を減じるためであるが、必ずしも行
う必要はない。 Note that the present invention is not limited to the above embodiments. That is, although the purpose of recycling the dehydrated transferred water to the tank 1 is to reduce the amount of water to be treated, it is not necessarily necessary.
第１図は本発明一実施例の模式図、第２図は他
の実施例の模式図である。
１……放射性廃棄物貯蔵タンク、３……管路、
４……カバー、５……ドラム缶、６……フイル
タ、７……排水管、８……ポンプ、９……大気連
通弁、１０……昇降台。
FIG. 1 is a schematic diagram of one embodiment of the present invention, and FIG. 2 is a schematic diagram of another embodiment. 1...Radioactive waste storage tank, 3...Pipeline,
4... Cover, 5... Drum, 6... Filter, 7... Drain pipe, 8... Pump, 9... Atmospheric communication valve, 10... Lifting platform.
Claims (1)
放射性廃棄物をドラム缶に供給するポンプと、前
記ドラム缶中にドラム缶に対しその軸方向に相対
変位可能に設置され下端にフイルタをそなえた排
水管と、この排水管に連通された排水用のポンプ
とを有する放射性廃棄物スラリーの脱水ドラム詰
装置。 ２ 前記タンクからドラム缶に放射性廃棄物を供
給する管路端末には、ドラム缶開口部に係合装着
されるカバーを取付けたことを特徴とする特許請
求の範囲第１項記載の放射性廃棄物スラリー脱水
ドラム詰装置。 ３ 前記排水用ポンプの吐出側を前記放射性廃棄
物貯蔵タンクに連通させたことを特徴とする特許
請求の範囲第１項又は第２項記載の放射性廃棄物
スラリー脱水ドラム詰装置。[Scope of Claims] 1. A radioactive waste storage tank, a pump for supplying radioactive waste from the tank to a drum, and a filter installed in the drum so that it can be displaced relative to the drum in the axial direction, and a filter is provided at the lower end of the drum. A dewatering drum filling device for radioactive waste slurry, which has a drain pipe and a pump for draining water that is connected to the drain pipe. 2. The radioactive waste slurry dewatering device according to claim 1, wherein a cover is attached to the end of the pipe for supplying radioactive waste from the tank to the drum, which is engaged with and attached to the opening of the drum. Drum filling device. 3. The radioactive waste slurry dewatering drum packing apparatus according to claim 1 or 2, wherein the discharge side of the drainage pump is communicated with the radioactive waste storage tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12941179A JPS5653498A (en) | 1979-10-09 | 1979-10-09 | Dehydrating and canning device for radioactive waste slurry |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP12941179A JPS5653498A (en) | 1979-10-09 | 1979-10-09 | Dehydrating and canning device for radioactive waste slurry |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5653498A JPS5653498A (en) | 1981-05-13 |
| JPS6243520B2 true JPS6243520B2 (en) | 1987-09-14 |
Family
ID=15008869
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP12941179A Granted JPS5653498A (en) | 1979-10-09 | 1979-10-09 | Dehydrating and canning device for radioactive waste slurry |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5653498A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2816006B2 (en) * | 1990-09-26 | 1998-10-27 | 株式会社東芝 | Solidification of radioactive waste |
-
1979
- 1979-10-09 JP JP12941179A patent/JPS5653498A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5653498A (en) | 1981-05-13 |
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