JPS5926099A - Heating and drying for radioactive waste treating equipment - Google Patents

Heating and drying for radioactive waste treating equipment

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Publication number
JPS5926099A
JPS5926099A JP57135173A JP13517382A JPS5926099A JP S5926099 A JPS5926099 A JP S5926099A JP 57135173 A JP57135173 A JP 57135173A JP 13517382 A JP13517382 A JP 13517382A JP S5926099 A JPS5926099 A JP S5926099A
Authority
JP
Japan
Prior art keywords
drying
heating
conduit
radioactive waste
valve
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
Application number
JP57135173A
Other languages
Japanese (ja)
Other versions
JPH0356438B2 (en
Inventor
高村 義之
福成寺 誠也
木下 高年
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP57135173A priority Critical patent/JPS5926099A/en
Publication of JPS5926099A publication Critical patent/JPS5926099A/en
Publication of JPH0356438B2 publication Critical patent/JPH0356438B2/ja
Granted legal-status Critical Current

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  • Processing Of Solid Wastes (AREA)
  • Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (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】 本発明は、放射性廃棄物処理装置の加温、乾燥方法に係
り、特に、原子力発電所等にて発生した放射性廃液又は
スラリを乾燥蒸発させ、それを固化処理する放射性廃棄
物処理装置の加温および洗浄後の乾燥に好適な放射性廃
棄物処理装置の加温。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a heating and drying method for a radioactive waste treatment device, and in particular, to a method for heating and drying a radioactive waste treatment device, and in particular, a method for drying and evaporating radioactive waste liquid or slurry generated at a nuclear power plant, etc., and solidifying it. Heating of radioactive waste processing equipment suitable for heating waste processing equipment and drying after cleaning.

乾燥方法に関するものである。This relates to a drying method.

従来の放射性廃棄物処理装置の加温、乾燥方法例を第1
図により説明する。
The first example of heating and drying methods for conventional radioactive waste processing equipment
This will be explained using figures.

第1図は、従来の放射性廃棄物処理装置の加温。Figure 1 shows the heating of a conventional radioactive waste treatment device.

乾燥方法を実施した放射性廃棄物処理装置の系統図で、
給液ポンプ10.給液弁30が設けられた導管50が連
結され、熱媒供給用、排出用の導管51.52が連結さ
れた加熱ジャケット11が包設されると共に、電動機等
の駆動装置12で駆動される回転翼13が回転可能に内
股された乾燥装置14には乾燥物出メ ロ管閏な介して、乾燥物ホッパ15と、乾燥物ホッパー
51こ乾燥物弁3工を介して一端が連結されると共に、
スクリュー駆動装置16で[動されるスクリュー17が
内股されたツイータ18と、フィーダ18の一端にドレ
ン弁32が設けられた導管54で連結されたドレンタン
ク19と、フィーダ18の他端にフィーダ出口弁33を
介して導管55で連結され、かつ、固化物仕切弁あが設
けられた導管間が連結された同化材混合製置加とで構成
された固化処理装置i!21が連結され、また、凝縮液
出口弁あが設けられた導管57および冷却水の供給用、
排出用の導管58.59がそれぞれ連結された復水器η
と、復水器nに連結された導管60のベント出口弁36
.37の間に設けられた吸引製置田とで構成された蒸発
処理装置路が導管61で連結されている。なお、同化材
混合製置加には、除湿装w125が弁間が設けられた導
管62で連結されている。
A system diagram of the radioactive waste processing equipment that implemented the drying method.
Liquid supply pump 10. A heating jacket 11 connected to a conduit 50 provided with a liquid supply valve 30 and connected to conduits 51 and 52 for heat medium supply and discharge is enclosed, and is driven by a drive device 12 such as an electric motor. A drying device 14, in which a rotary blade 13 is rotatably housed, is connected at one end to a drying material hopper 15 and a drying material hopper 51 through a drying material discharge pipe via a drying material valve. ,
A tweeter 18 with a screw 17 driven by the screw drive device 16, a drain tank 19 connected to one end of the feeder 18 by a conduit 54 provided with a drain valve 32, and a feeder outlet at the other end of the feeder 18. The solidification treatment device i! is connected by a conduit 55 via a valve 33, and is composed of an assimilation material mixing device and an assimilating material mixing device, which are connected to each other by a conduit 55 and a conduit provided with a solidified material gate valve. 21 is connected to the conduit 57, which is also provided with a condensate outlet valve, and a conduit 57 for supplying cooling water;
Condenser η to which discharge conduits 58 and 59 are respectively connected
and a vent outlet valve 36 of conduit 60 connected to condenser n.
.. A conduit 61 connects an evaporation treatment device path consisting of a suction tank and a suction tank provided between 37 and 37. Note that a dehumidifying device w125 is connected to the assimilating material mixing device through a conduit 62 provided with a valve gap.

原子力発電所等にて発生した放射性廃液又はスラリ等の
放射性廃棄物は給液ポンプ10より所定の供給容量で給
液弁3()を介し導′W50を経て乾燥装置14に供給
される。ここで放射性廃棄物は、駆wJ!装置12で駆
動され回転する回転翼13の遠心力作用により乾燥袋f
i14内壁面に薄膜状に押拡げられ、導gI51 、加
熱ジャケラ)H,2yf、管52を流通する熱媒の加熱
により蒸発乾燥する。蒸発物は導管6エを経て復水器2
2Iこ供給され、ここで導管間より供給され、また、導
管59より排出される冷却水で凝縮され、R剤液1ま1
17t、剤液出口弁35を介し導管57より他の水処理
装置(図示省略)に送給される。また、蒸発物中の非凝
縮性ガスは、ベント出口弁36を介し吸引装置nで吸引
され、ベント出口弁37を介し導管60より他のベント
処i装置(図示省略)に送給される。一方、乾燥物は乾
燥物出口管53を経て乾燥物弁31を介してフィーダー
8の一端に供給され、スクリュー駆動装置16で駆動さ
れるスクリュー17によりフィーダー8の他端に移送さ
れる。フィーダー8の他端に移送された乾燥物は、フィ
ーダ出口弁33を介し導管55を経て固化処理装置加に
供給され、ここでアスファルト又はプラスチック等の固
化層とともに混合された後に、固化物仕切弁あをメ 介し導管56を経て同化処理ドラム缶70に供給、充填
される。なお、フィーダー8の一端に溜ったドレンはド
レン弁32を介し導管シを経てドレンタンク19に抜出
され貯蔵される〇 これら一連の処理を円滑に行うためには、放射性廃棄物
処理装置を健全に保持しなければならない。つまり、放
射性廃棄物は蒸発により通常、残留含水率が数重量%以
下まで乾燥されるため、乾燥装置14から固化処理装置
21に至る乾燥物の流通経路(以下、乾燥物の流通経路
と略)は、運転前には完全に乾燥した状態になっていな
ければ、水分が残存する部分において乾燥物が付着し、
固形分の成長をまねいて円滑な運転を阻害する。また、
乾燥物の流通経路が乾燥物の温度よりも低い状態、すな
わち、常温に近い状態であると、乾燥物中の僅かな残留
水分あるいは乾燥物とともに排出される蒸発物が、乾燥
物の流通経路に凝縮、付着し、それにより固形分の付着
、成長を招いて円滑な運転を阻害する。そこで、これら
問題を解決し、放射性廃棄物処理装置を円滑に運転する
ため、放射性廃棄物処理装置は、従来、次の方法により
加温。
Radioactive waste such as radioactive liquid waste or slurry generated at a nuclear power plant or the like is supplied at a predetermined supply capacity from a liquid supply pump 10 to a drying device 14 via a liquid supply valve 3 () and a conduit W50. Here, radioactive waste is a waste! The drying bag f is formed by the centrifugal force of the rotary blade 13 driven and rotated by the device 12.
It is spread into a thin film on the inner wall surface of i14, and is evaporated and dried by the heating of the heating medium flowing through the pipe 52. Evaporated matter passes through conduit 6e to condenser 2
2I is supplied here, is supplied from between the conduits, and is condensed with the cooling water discharged from the conduit 59, and the R agent liquid 1 or 1 is
17t, and is sent to another water treatment device (not shown) through a conduit 57 via a chemical solution outlet valve 35. Further, the non-condensable gas in the evaporated matter is sucked by the suction device n via the vent outlet valve 36, and is sent to another vent treatment device i (not shown) via the vent outlet valve 37 through the conduit 60. On the other hand, the dried material is supplied to one end of the feeder 8 via the dried material outlet pipe 53 and the dried material valve 31, and is transferred to the other end of the feeder 8 by the screw 17 driven by the screw drive device 16. The dried material transferred to the other end of the feeder 8 is fed through the feeder outlet valve 33 and the conduit 55 to the solidification treatment equipment, where it is mixed with a solidified layer of asphalt or plastic, etc., and then passed through the solidified material gate valve. It is supplied and filled into an assimilation drum 70 through a conduit 56 through an aperture. In addition, the drain accumulated at one end of the feeder 8 is extracted and stored in the drain tank 19 via the drain valve 32 and the conduit. In order to perform this series of processing smoothly, it is necessary to keep the radioactive waste processing equipment in good health. must be maintained. In other words, since radioactive waste is usually dried by evaporation to a residual moisture content of several percent by weight or less, the distribution path of the dried material from the drying device 14 to the solidification processing device 21 (hereinafter abbreviated as the distribution path of the dried material) If the machine is not completely dry before operation, dry matter will adhere to areas where moisture remains, and
This leads to the growth of solids and impedes smooth operation. Also,
If the distribution path of the dried material is lower than the temperature of the dried material, that is, close to room temperature, a small amount of residual moisture in the dried material or evaporated matter discharged together with the dried material may enter the distribution path of the dried material. It condenses and adheres, which leads to the adhesion and growth of solids and impedes smooth operation. Therefore, in order to solve these problems and operate the radioactive waste processing equipment smoothly, the radioactive waste processing equipment has conventionally been heated using the following method.

乾燥されている。It has been dried.

まず、放射性廃棄物の処理前の放射性廃棄物処理装置の
加温は、乾燥物の通過経路におのおの電気ヒータあるい
は加熱ジャケットを設け、電気ヒータあるいは加熱ジャ
ケットにより乾燥物の通過経路を乾燥物の温度よりも高
い温度に加温することでなされ、また、例えば、洗浄後
の放射性廃棄物処理装置の乾燥は、除湿装ry12!5
で除湿された乾燥空気を弁間な介し導管62を経て固化
処理装置21に供給し、乾燥物の流通経路を逆方向に流
通させることでなされている。
First, to heat the radioactive waste processing equipment before processing radioactive waste, an electric heater or heating jacket is installed in each passage of the dried material, and the electric heater or heating jacket is used to adjust the passage of the dried material to the temperature of the dried material. For example, drying of the radioactive waste treatment equipment after cleaning is done by heating it to a higher temperature than the dehumidifier RY12!5.
The dehumidified dry air is supplied to the solidification processing device 21 through the conduit 62 between the valves, and the dried material is circulated in the opposite direction through the distribution path.

このような放射性廃棄物処理装置の加温、乾燥方法では
、次のような欠点があった。
This heating and drying method for radioactive waste processing equipment has the following drawbacks.

(1)駆動機構等局部的に加温が充分でない部分が生じ
、したがって、加温に長時間を要するか、あるいは、ど
うしても加温が不充分になりがちである。
(1) Some parts, such as the drive mechanism, are not sufficiently heated locally, and therefore, it takes a long time to warm up, or heating tends to be insufficient.

(2)洗浄後、滞溜部のドレンな完全に乾燥空気で乾燥
させるのが困難であり、したがって、完全に乾燥させる
には長時間を要する。
(2) After cleaning, it is difficult to completely dry the stagnation part with dry air, and therefore it takes a long time to completely dry it.

そこで、本発明者らは、上記欠点の解消を目的として特
願昭57−022739号記載の放射性廃棄物処理装置
の加温、乾燥方法を提案した。
Therefore, the present inventors proposed a heating and drying method for a radioactive waste processing apparatus described in Japanese Patent Application No. 57-022739 with the aim of eliminating the above-mentioned drawbacks.

第2図は、上記提案した方法の一実施例を説明するもの
で、なお、第2図で、第1図と同一装置。
FIG. 2 illustrates an embodiment of the method proposed above, and FIG. 2 shows the same apparatus as FIG. 1.

部品は同一符号で示し説明を省略する。Parts are designated by the same reference numerals and their explanations are omitted.

′!52図で、弁39が設けられ一端が大気開放された
導管63が、ベント山口弁36と吸引装[Z3との間の
導管60に連結され、吸引装置1i23とベント山口弁
37との間で導管60より分岐し弁40が設けられた導
管θが導管61に連結されている。また、同化処理装[
21の同化処理装置加には、弁41.42が設けられ、
一端が大気開放された導管65が連結され、弁41.4
2間で導管65より分岐し弁43が設けられた導管66
が吸引装置nの前流側で導管60に連結されている。こ
のような放射性廃棄物処理装置の加温。
′! In FIG. 52, a conduit 63 provided with a valve 39 and open to the atmosphere at one end is connected to a conduit 60 between the vent Yamaguchi valve 36 and the suction device [Z3, and is connected between the suction device 1i23 and the vent Yamaguchi valve 37. A conduit θ branched from the conduit 60 and provided with a valve 40 is connected to the conduit 61. In addition, assimilation processing equipment [
The assimilation treatment device 21 is provided with valves 41 and 42,
A conduit 65 with one end open to the atmosphere is connected to the valve 41.4.
A conduit 66 branched from the conduit 65 between the two and provided with a valve 43
is connected to the conduit 60 on the upstream side of the suction device n. Heating of such radioactive waste processing equipment.

乾燥は、次のように行われる。Drying is performed as follows.

給液弁間、ドレン弁32.固化物仕切弁あ、凝縮液山口
弁部、ベント出口弁36737.弁42を閉弁し、乾燥
物弁31. フィーダ出口弁33.弁39〜41.43
を開弁じた後に、吸引装置1123を駆動させる。これ
により気体、例えば、空気は弁39を介し導管63.6
0を経て吸引装置t23に吸引された後に、導管60を
経て弁40を介し導管d、61を経て乾燥装置14に供
給される。乾燥装置14に供給された空気は、導管51
゜加熱ジャケット11.導管52を流通する熱媒1こよ
り加温された後に、この加温された空気は乾燥装置14
から乾燥物出口管53を介して、同化処理装置21の乾
燥物ホッパ巧に供給され、同化処理装置21を乾燥物ホ
ッパ15.乾燥物弁31.  フィーダ18.ンイーダ
出ロ弁33.導管55.固化羽混合装置(イ)と順次流
通し、弁41を介し導管65より排出される。この間、
加温された空気により、乾燥物の流通経路は十分に加温
、乾燥される。なお、固化処理装置21から排出された
空気は、弁43を介し導管6を経て吸引装置部の前流側
に戻し、吸引装置おにより乾燥袋[+¥ 14に再供給
しても良く、また、弁42を開弁じ、弁43を閉弁して
弁42を介し導管65を経て大気放出してもよい。
Between the liquid supply valve and the drain valve 32. Solidified product gate valve A, condensate Yamaguchi valve, vent outlet valve 36737. Close valve 42 and close dry product valve 31. Feeder outlet valve 33. Valve 39-41.43
After opening the valve, the suction device 1123 is driven. Gas, for example air, is thereby passed through valve 39 to conduit 63.6.
After being sucked into the suction device t23 via a conduit 60, the liquid is supplied to the drying device 14 via a valve 40 and conduits d and 61. The air supplied to the drying device 14 is passed through the conduit 51
゜Heating jacket 11. After being heated by the heat medium flowing through the conduit 52, this heated air is passed through the drying device 14.
from the dry matter outlet pipe 53 to the dry matter hopper of the assimilation treatment device 21, and the dry matter hopper 15. Dry product valve 31. Feeder 18. Nida outlet valve 33. Conduit 55. It sequentially flows through the solidification feather mixer (a) and is discharged from the conduit 65 via the valve 41. During this time,
The distribution path of the dried material is sufficiently heated and dried by the heated air. Note that the air discharged from the solidification processing device 21 may be returned to the upstream side of the suction device section via the valve 43 and the conduit 6, and re-supplied to the drying bag [+\14] by the suction device. , the valve 42 may be opened, the valve 43 may be closed, and the gas may be discharged to the atmosphere via the valve 42 and the conduit 65.

このような方法では、乾燥物の流通経路を十分に、かつ
、短時間で加温、乾燥できる効果があるが、その後、更
に詳細に検討したところ、未だ次のような欠点があるこ
とが解った。
Although this method has the effect of sufficiently heating and drying the distribution route of dried products in a short period of time, a more detailed study revealed that it still has the following drawbacks. Ta.

l)乾燥物の流通経路を加温、乾燥した気体には、放射
性粒子が同伴し、そのまま系外へ排出されるため、作業
環境並びに作業者の保全を計る上で障害となる。
l) The gas that heats and dries the distribution route of the dried material is accompanied by radioactive particles and is discharged from the system as it is, which poses an obstacle to the protection of the working environment and workers.

本発明の目的は、上記した欠点を解消することで、〈乾
燥物の流通経路を十分に、かつ、短時間で加温、乾燥で
きると共に、作業環境並びに作業者の保全を計る上での
障害をなくすことができる放射性廃棄物処理装置の加温
、乾燥方法を提供することにある。
The purpose of the present invention is to solve the above-mentioned drawbacks, such as ``allowing the distribution route of dried materials to be sufficiently heated and dried in a short period of time, and preventing obstacles in protecting the working environment and workers.'' An object of the present invention is to provide a heating and drying method for a radioactive waste processing equipment that can eliminate the

本発明の特徴は、乾燥装置に気体を供給し、該気体を乾
燥装置に包設した加熱ジャケットを流通する熱媒により
加温して乾燥装置から乾燥物出口管を介して同化処理装
置に供給し流通させ、同伴した放射性粒子な放射性粒子
除去手段で除去した後に系外へ排出することで、乾燥物
の流通経路を加温、乾燥した気体を、放射性粒子を同伴
することなしに系外へ排出することにある。
The present invention is characterized by supplying gas to the drying device, heating the gas by a heating medium flowing through a heating jacket enclosed in the drying device, and supplying the gas from the drying device to the assimilation treatment device via the dried material outlet pipe. By distributing the radioactive particles, removing the entrained radioactive particles with a radioactive particle removal means, and then discharging them out of the system, the distribution path of the dried material is heated, and the dried gas is sent out of the system without accompanying radioactive particles. It consists in expelling.

本発明の一実施例を第3図により説明する。なお、第3
図で、茅1図および第2図と同一装置。
An embodiment of the present invention will be described with reference to FIG. In addition, the third
This figure shows the same equipment as Kaya Figures 1 and 2.

部品等は同一符号で示し説明を省略する。Parts, etc. are indicated by the same reference numerals and explanations are omitted.

第3図で、放射性粒子除去手段、例えば、ミストセパレ
ータ80の下部には、導管66と、一端が導管61に連
結されたU字形シール管67が、上部Iこ1よ、導管5
7と、洗浄水供給用の弁44が設けられた導管側が、頂
部には、一端が復水器nに連結された導管69が、底部
には、導管70がそれぞれ連結さitている。
In FIG. 3, a conduit 66 and a U-shaped seal tube 67 connected to the conduit 61 at one end are arranged in the lower part of the radioactive particle removal means, for example, the mist separator 80, and in the upper part, the conduit 5 is connected to the conduit 61 at one end.
7 and a conduit side provided with a wash water supply valve 44, a conduit 69 whose one end is connected to a condenser n is connected to the top, and a conduit 70 is connected to the bottom.

放射性粒子を同伴した気体、例えば、空気は、弁41.
43を開弁、弁42を開弁することで導管65゜66を
経てミストセパレーク80の下部に供給され、ミストセ
パレータ80内を上昇する。一方、弁aを開弁すること
で洗浄水が導管部な経てミストセパレーク80の上部に
供給され、ミストセパレーク80内を流下する。この間
に上列する空気と流下する洗浄水とは気液接触し、これ
により、空気:こ同伴した放射性粒子は、空気から除去
されん。その後、放射性粒子を含んだ洗浄水は、ミスト
セ/ slル−ク80の底部から導管70を経て系外へ
抜出され処理される。一方、放射性粒子を除去され清浄
となった空気は、ミストセパレータ800頂部カ)も導
管69な経て復水器nに供給され、ここで、湿分が除去
される。その後、この空気は、吸引製置羽により吸引さ
れ導管60を経て系外へ排出される。また、この他にこ
の空気を、弁39を開弁する二とで導管63を経て導管
60に外部より吸引される空気と混合して弁40を介し
導管B、61を経て乾燥装置14に再び供給するように
しても良い。
A gas, for example air, entrained with radioactive particles is passed through valve 41.
By opening the valve 43 and the valve 42, the water is supplied to the lower part of the mist separator 80 through the conduits 65 and 66, and rises inside the mist separator 80. On the other hand, by opening the valve a, the cleaning water is supplied to the upper part of the mist separator lake 80 through the conduit section, and flows down inside the mist separator lake 80. During this time, the air in the upper row and the washing water flowing down come into gas-liquid contact, and as a result, the radioactive particles entrained in the air are not removed from the air. Thereafter, the wash water containing the radioactive particles is extracted from the bottom of the mist cell/sl leak 80 through the conduit 70 to the outside of the system and treated. On the other hand, the clean air from which radioactive particles have been removed is supplied to the condenser n via the top of the mist separator 800 and the conduit 69, where moisture is removed. Thereafter, this air is sucked by the suction blade and discharged out of the system through the conduit 60. In addition, when the valve 39 is opened, this air is mixed with air sucked from the outside into the conduit 60 through the conduit 63, and is returned to the drying device 14 via the valve 40 and conduits B and 61. It may also be supplied.

なお、乾燥物の流通経路の加温、乾燥操作は、第2図で
説明した操作と同様であり、したがって、説明は省略す
る。
Incidentally, the heating and drying operations of the distribution path of the dried material are the same as those explained in FIG. 2, and therefore, the explanation will be omitted.

本実施例のような方法では、乾燥物の流通経路を乾燥装
置で加温した空気を流通させて加温、乾燥すると共に、
同伴した放射性粒子をミストセパレークで除去した後に
空気を系外へ排出するので、次のような効果が得られる
In the method of this embodiment, air heated by a drying device is passed through the distribution path of the dried material to heat and dry the material, and
After the accompanying radioactive particles are removed by the mist separator, the air is discharged to the outside of the system, resulting in the following effects.

(1)  乾燥物の流通経路を十分に、かつ、短時間で
加温、乾燥できる。
(1) The distribution route for dried products can be sufficiently heated and dried in a short time.

(2)作業環境並び冬二作業者の保全を計る上での障害
をなくすことができる。
(2) Obstacles in maintaining the working environment and winter workers can be eliminated.

本発明は、以上説明したように、乾燥装置に気体を供給
し、該気体を乾燥装置ζに包設した加熱ジャケットを流
通する熱媒により加温して乾燥装置から乾燥物出口管を
介して固化処理装置に供給し流通させ、同伴した放射性
粒子を放射性粒子除去手段で除去した後に系外へ排出す
ることで、乾燥物の流通経路を十分に、かつ、短時間で
加温、乾燥できると共に、作業環境並びに作業者の保全
を計る上での障害をなくすことができるといった効果が
ある。
As explained above, the present invention supplies gas to a drying device, heats the gas by a circulating heating medium through a heating jacket enclosed in the drying device ζ, and supplies the gas from the drying device via a dried material outlet pipe. By supplying the dried material to the solidification processing equipment and distributing it, removing the entrained radioactive particles with the radioactive particle removal means and then discharging it outside the system, the distribution route of the dried material can be sufficiently heated and dried in a short time. This has the effect of eliminating obstacles to protecting the work environment and workers.

【図面の簡単な説明】[Brief explanation of the drawing]

多S1図は、従来の放射性廃棄物処理装置の系統図、第
2図は、木発明者らが先に提案した放射性廃棄物処理装
置の加温、乾燥方法を実施した放射性廃棄物処理装置の
一例を示す系統図、第3図は、本発明を実施した放射性
廃棄物処理装置の一例を示す系統図である。
Fig. S1 is a system diagram of a conventional radioactive waste processing equipment, and Fig. 2 is a diagram of a radioactive waste processing equipment that implements the heating and drying method for radioactive waste processing equipment proposed earlier by the inventors. FIG. 3 is a system diagram showing an example of a radioactive waste processing apparatus in which the present invention is implemented.

Claims (1)

【特許請求の範囲】 1、回転翼が回転可能に内股され、かつ、熱媒が流通す
る加熱ジャケットが包設された放射性廃棄物を乾燥する
乾燥装置と、該乾燥’J’mIから排出された蒸発物を
凝縮する蒸発物処理装置と、前記乾燥装置と乾燥物出口
管で連結され、該出口管を経て前記乾燥装置から排出さ
れた乾燥物を固化処理する固化処理装置とで構成された
放射性廃棄物処理装置の加温、乾燥方法において、前記
乾燥装置に気体を供給し、該気体を前記加熱ジャケット
を流通する熱媒により加温して乾処 検装置から前記乾燥物出口管を介して前記固化処理装置
に供給し流通させ、同伴した放射性粒子を放射性粒子除
去手段で除去した後に系外へ排出することを特徴とする
放射性廃棄物処理装置の加温、乾燥方法。 2、 前記気体に同伴した放射性粒子をミヌトセバレー
クで除去する特許請求の範¥5第1項記載の放射性廃棄
物処理装置の加温、乾燥方法。
[Claims] 1. A drying device for drying radioactive waste in which rotary blades are rotatably arranged inside and a heating jacket through which a heat medium flows is enclosed, and an evaporated matter processing device that condenses the evaporated matter; and a solidification processing device that is connected to the drying device through a dry matter outlet pipe and solidifies the dried matter discharged from the drying device through the outlet pipe. In a method for heating and drying a radioactive waste treatment device, gas is supplied to the drying device, the gas is heated by a heating medium flowing through the heating jacket, and the gas is passed from the dry treatment device through the dried material outlet pipe. A heating and drying method for a radioactive waste processing apparatus, characterized in that the radioactive waste is supplied to the solidification processing apparatus and distributed, and the entrained radioactive particles are removed by a radioactive particle removal means and then discharged to the outside of the system. 2. The heating and drying method for a radioactive waste processing apparatus according to claim 5, wherein radioactive particles entrained in the gas are removed by a minutosebare lake.
JP57135173A 1982-08-04 1982-08-04 Heating and drying for radioactive waste treating equipment Granted JPS5926099A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57135173A JPS5926099A (en) 1982-08-04 1982-08-04 Heating and drying for radioactive waste treating equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57135173A JPS5926099A (en) 1982-08-04 1982-08-04 Heating and drying for radioactive waste treating equipment

Publications (2)

Publication Number Publication Date
JPS5926099A true JPS5926099A (en) 1984-02-10
JPH0356438B2 JPH0356438B2 (en) 1991-08-28

Family

ID=15145536

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57135173A Granted JPS5926099A (en) 1982-08-04 1982-08-04 Heating and drying for radioactive waste treating equipment

Country Status (1)

Country Link
JP (1) JPS5926099A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS575478A (en) * 1980-06-13 1982-01-12 Sony Corp Ghost rejecting device
JPS5722739A (en) * 1980-07-17 1982-02-05 Terumo Corp Cycle measuring system

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS575478A (en) * 1980-06-13 1982-01-12 Sony Corp Ghost rejecting device
JPS5722739A (en) * 1980-07-17 1982-02-05 Terumo Corp Cycle measuring system

Also Published As

Publication number Publication date
JPH0356438B2 (en) 1991-08-28

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