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JPH0477279B2 - - Google Patents
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JPH0477279B2 - - Google Patents

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Publication number
JPH0477279B2
JPH0477279B2 JP57188647A JP18864782A JPH0477279B2 JP H0477279 B2 JPH0477279 B2 JP H0477279B2 JP 57188647 A JP57188647 A JP 57188647A JP 18864782 A JP18864782 A JP 18864782A JP H0477279 B2 JPH0477279 B2 JP H0477279B2
Authority
JP
Japan
Prior art keywords
waste liquid
amount
deviation
signal
diluted
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 - Lifetime
Application number
JP57188647A
Other languages
Japanese (ja)
Other versions
JPS5979198A (en
Inventor
Katsuo Niizawa
Akira Saku
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.)
Toshiba Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
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 Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP18864782A priority Critical patent/JPS5979198A/en
Publication of JPS5979198A publication Critical patent/JPS5979198A/en
Publication of JPH0477279B2 publication Critical patent/JPH0477279B2/ja
Granted legal-status Critical Current

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  • Measurement Of Radiation (AREA)
  • Electrical Discharge Machining, Electrochemical Machining, And Combined Machining (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は原子力発電設備等から排出される放射
性廃液を処理する設備に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to equipment for treating radioactive waste liquid discharged from nuclear power generation equipment and the like.

〔発明の技術的背景〕[Technical background of the invention]

一般に原子力発電設備等から排出された放射性
廃液は廃液濃縮設備によつて濃縮されて減容され
たのちドラム缶等の貯蔵容器内に詰められ、セメ
ント等で固化されて貯蔵される。そして、従来こ
の濃縮された放射性廃液を貯蔵容器内に積めるに
はまず廃液計量タンク内に一定量の放射性廃液を
溜め、この一定量の放射性廃液をドラム缶内に移
送するとともにこのドラム缶内にセメント等を供
給して放射性廃液と混合して固化させていた。
In general, radioactive waste liquid discharged from nuclear power generation facilities and the like is concentrated and reduced in volume by waste liquid concentration equipment, and then packed into storage containers such as drums, solidified with cement, etc., and stored. Conventionally, in order to store this concentrated radioactive waste liquid in a storage container, a certain amount of radioactive waste liquid is first stored in a waste liquid measuring tank, and this certain amount of radioactive waste liquid is transferred into a drum, and cement etc. was supplied and mixed with radioactive waste liquid to solidify it.

〔背景技術の問題点〕[Problems with background technology]

放射性廃液の放射能濃度は一定とは限らない。
このため、放射性廃液の放射能濃度が高い場合に
はこの放射性廃液が詰められたドラム缶の放射能
レベルが規定値より高くなつてしまうことがあ
る。そして、このような場合にはこのドラム缶を
高放射性廃棄物として長期間貯蔵し、放射能の減
衰を図らねばならない等その取扱がきわめて面倒
となる不具合があつた。
The radioactivity concentration of radioactive waste liquid is not necessarily constant.
Therefore, when the radioactive concentration of the radioactive waste liquid is high, the radioactivity level of the drum can filled with the radioactive waste liquid may become higher than the specified value. In such cases, the drums must be stored for a long period of time as highly radioactive waste, and the handling of the drums becomes extremely troublesome, as the radioactivity must be attenuated.

〔発明の目的〕[Purpose of the invention]

本発明は以上の事情にもとづいてなされたもの
で、その目的とするところは放射能濃度に対応し
てドラム缶等の貯蔵容器に詰める放射性廃液の量
を自動的に制御し、放射性廃液の放射能濃度が高
い場合であつてもこの放射性廃液が詰められた貯
蔵容器の放射能レベルを所定の値以下とすること
ができる放射性廃液処理設備を提供することにあ
る。
The present invention has been made based on the above circumstances, and its purpose is to automatically control the amount of radioactive waste liquid packed into storage containers such as drums according to the radioactivity concentration, and to reduce the radioactivity of the radioactive waste liquid. An object of the present invention is to provide a radioactive waste liquid treatment facility that can reduce the radioactivity level of a storage container filled with radioactive waste liquid to a predetermined value or less even when the concentration is high.

〔発明の概要〕[Summary of the invention]

本発明は、放射性廃液を計量するための廃液計
量タンクと、この廃液計量タンクに放射性廃液を
導入する廃液供給手段と、この廃液供給手段から
前記廃液計量タンクに導入された放射性廃液量を
検出する廃液量検出手段と、前記廃液計量タンク
に導入された放射性廃液の放射線量を検出する放
射線検出手段と、前記廃液計量タンクに導入され
た放射性廃液を固化貯蔵用の貯蔵容器に移送する
廃液移送手段と、前記貯蔵容器に希釈液を注入す
る希釈液供給手段と、前記廃液計量タンクに導入
される放射性廃液量および前記貯蔵容器に注入さ
れる希釈液量を制御する制御手段とを具備し、前
記制御手段は、前記貯蔵容器に貯蔵される放射性
廃液の最大詰め量を設定する詰め量設定器と、前
記廃液量検出手段から出力された廃液量検出信号
と前記詰め量設定器から出力された詰め量設定信
号との偏差を求める偏差演算手段と、前記廃液量
検出手段で検出された廃液量が前記詰め量設定器
で設定された詰め量よりも小さい場合に廃液供給
許可信号を出力する第1の偏差判断器と、前記廃
液量検出手段、放射線検出手段、詰め量設定器お
よび偏差演算手段からの出力信号を受け前記偏差
演算手段で算出された偏差値に対応した量の希釈
液を廃液計量タンクに加えた場合の放射性廃液の
単位体積当りの希釈放射能濃度を算出する希釈放
射能濃度算出手段と、前記貯蔵容器に貯蔵される
放射性廃液の単位体積当りの許容放射能濃度を設
定する放射能濃度設定器と、前記希釈放射能濃度
算出手段で算出された希釈放射能濃度が前記放射
能濃度設定器で設定された許容放射能濃度よりも
小さい場合に廃液供給許可信号を出力する第2の
偏差判断器と、この第2の偏差判断器または前記
第1の偏差判断器のいずれか一方が廃液供給許可
信号を出力しなくなつたときに前記廃液供給手段
に廃液供給停止信号を送出する廃液供給停止信号
送出手段と、前記希釈液供給手段から前記貯蔵容
器に注入された希釈液量を検出する希釈液量検出
手段と、前記第1の偏差演算手段から出力された
偏差信号の最小値を記憶する記憶手段と、前記希
釈液量検出手段で検出された希釈液量が前記記憶
手段に記憶された値に達したとき前記希釈液供給
手段に希釈液供給停止信号を送出する第3の偏差
判断器とを有するものである。したがつて、放射
性廃液の放射能濃度が高い場合には計量タンク内
に供給される放射性廃液の量が自動的に減少し、
貯蔵容器に詰められる放射性廃液の量が少なくな
るので、この放射性廃液が詰められた貯蔵容器の
放射能レベルを規定の値以下とすることができる
ものである。
The present invention includes a waste liquid measuring tank for measuring radioactive waste liquid, a waste liquid supply means for introducing the radioactive waste liquid into the waste liquid measuring tank, and a method for detecting the amount of radioactive waste liquid introduced from the waste liquid supply means into the waste liquid measuring tank. A waste liquid amount detection means, a radiation detection means for detecting the radiation dose of the radioactive waste liquid introduced into the waste liquid measuring tank, and a waste liquid transfer means for transferring the radioactive waste liquid introduced into the waste liquid measuring tank to a storage container for solidification storage. and a diluent supply means for injecting a diluent into the storage container, and a control means for controlling the amount of radioactive waste liquid introduced into the waste liquid measuring tank and the amount of diluent injected into the storage container, The control means includes a filling amount setting device that sets a maximum filling amount of radioactive waste liquid stored in the storage container, and a waste liquid amount detection signal output from the waste liquid amount detection means and a filling amount setting device that sets the maximum filling amount of radioactive waste liquid stored in the storage container. a deviation calculation means for calculating a deviation from the amount setting signal; and a first device for outputting a waste liquid supply permission signal when the amount of waste liquid detected by the waste liquid amount detection means is smaller than the filling amount set by the filling amount setting device. Measures the amount of diluted liquid corresponding to the deviation value calculated by the deviation calculation means in response to the output signals from the deviation judgment device, the waste liquid amount detection means, the radiation detection means, the fill amount setting device, and the deviation calculation means. a diluted radioactivity concentration calculation means for calculating the diluted radioactivity concentration per unit volume of radioactive waste liquid when added to the tank; and a radioactivity concentration calculation means for calculating the permissible radioactivity concentration per unit volume of the radioactive waste liquid stored in the storage container. an activity concentration setting device; and a second device that outputs a waste liquid supply permission signal when the diluted radioactivity concentration calculated by the diluted radioactivity concentration calculation means is smaller than the allowable radioactivity concentration set by the radioactivity concentration setting device. a deviation judge, and when either the second deviation judge or the first deviation judge ceases to output a waste liquid supply permission signal, sends a waste liquid supply stop signal to the waste liquid supply means. waste liquid supply stop signal sending means, dilution liquid amount detection means for detecting the amount of dilution liquid injected into the storage container from the dilution liquid supply means, and the minimum value of the deviation signal output from the first deviation calculation means. a third storage means for storing a diluent supply stop signal to the diluent supply means when the diluent volume detected by the diluent volume detection means reaches the value stored in the storage means; and a deviation judger. Therefore, when the radioactive concentration of radioactive waste liquid is high, the amount of radioactive waste liquid supplied to the measuring tank is automatically reduced.
Since the amount of radioactive waste liquid packed into the storage container is reduced, the radioactivity level of the storage container filled with this radioactive waste liquid can be kept below a specified value.

〔発明の実施例〕[Embodiments of the invention]

以下図を参照して本発明の一実施例を説明す
る。図中1は放射性廃液を計量するための廃液計
量タンクである。そして、この廃液計量タンク1
内には廃液供給機構2から放射性廃液が供給され
るように構成されている。この廃液供給機構2は
ポンプ3およびタンク入口弁4から構成されてお
り、廃液濃縮装置(図示せず)等によつて濃縮さ
れた放射性廃液はこのポンプ3によつてタンク入
口弁4を介して廃液計量タンク1内に供給され
る。また、この廃液計量タンク1内に溜つた放射
性廃液は廃液移送機構5によつて貯蔵容器たとえ
ばドラム缶6内に送られるように構成されてい
る。この廃液移送機構5は上記廃液計量タンク1
の底部に連通した移送管7と、この移送管7の途
中に設けられたタンク出口弁8とから構成されて
おり、このタンク出口弁8を開弁することにより
上記廃液計量タンク1内の放射性廃液は重力によ
つて移送管7を通してドラム管6内に充填される
ように構成されている。また、上記廃液計量タン
ク1内にはこの廃液計量タンク1内の放射性廃液
の液位を検出しこの廃液計量タンク1内に貯溜さ
れた放射性廃液の量を検出する廃液量検出器9が
設けられている。また、この廃液計量タンク1内
には放射性廃液の放射線量を検出する放射線検出
器10が設けられている。また、11は希釈液供
給機構である。この希釈液供給機構11は水等の
希釈液を供給する希釈液供給源12と、この希釈
液供給源12からドラム缶6内に希釈液を供給す
る希釈液供給管13と、この希釈液供給管13の
途中に設けられた希釈液止弁14および希釈液流
量検出器15とから構成されている。そして、上
記希釈液止弁14が開弁されることにより希釈液
供給源12から希釈液供給管13を介してドラム
缶6内に希釈液が供給され、またこの供給される
希釈液の流量は希釈液流量検出器15で検出され
るように構成されている。
An embodiment of the present invention will be described below with reference to the drawings. In the figure, 1 is a waste liquid measuring tank for measuring radioactive waste liquid. And this waste liquid measuring tank 1
A radioactive waste liquid is supplied therein from a waste liquid supply mechanism 2. This waste liquid supply mechanism 2 is composed of a pump 3 and a tank inlet valve 4, and the radioactive waste liquid concentrated by a waste liquid concentrator (not shown) is transferred by this pump 3 to the tank inlet valve 4. The waste liquid is supplied into the waste liquid measuring tank 1. Further, the radioactive waste liquid accumulated in the waste liquid measuring tank 1 is configured to be sent into a storage container such as a drum can 6 by a waste liquid transfer mechanism 5. This waste liquid transfer mechanism 5 is connected to the waste liquid measuring tank 1.
It consists of a transfer pipe 7 communicating with the bottom of the waste liquid measuring tank 1, and a tank outlet valve 8 provided in the middle of the transfer pipe 7.By opening the tank outlet valve 8, the radioactivity in the waste liquid measuring tank 1 is removed. The waste liquid is configured to be filled into the drum pipe 6 through the transfer pipe 7 by gravity. Further, a waste liquid amount detector 9 is provided in the waste liquid measuring tank 1 to detect the liquid level of the radioactive waste liquid in the waste liquid measuring tank 1 and to detect the amount of radioactive waste liquid stored in the waste liquid measuring tank 1. ing. Furthermore, a radiation detector 10 is provided in the waste liquid measuring tank 1 to detect the radiation dose of the radioactive waste liquid. Further, 11 is a diluent supply mechanism. This diluent supply mechanism 11 includes a diluent supply source 12 that supplies a diluent such as water, a diluent supply pipe 13 that supplies the diluent from this diluent supply source 12 into the drum can 6, and this diluent supply pipe. The diluent stop valve 14 and the diluent flow rate detector 15 are provided in the middle of the diluent 13. When the diluent stop valve 14 is opened, the diluent is supplied from the diluent supply source 12 into the drum can 6 via the diluent supply pipe 13, and the flow rate of the supplied diluent is It is configured to be detected by a liquid flow rate detector 15.

そして、上記の廃液量検出器9、放射線検出器
10および希釈液流量検出器15からの信号は廃
液計量制御装置16に送られ、この廃液計量制御
装置16によつて前記ポンプ3、タンク入口弁
4、タンク出口弁8および希釈液止弁14が制御
されるように構成されている。
Signals from the waste liquid amount detector 9, radiation detector 10, and diluted liquid flow rate detector 15 are sent to a waste liquid metering control device 16, which controls the pump 3, tank inlet valve, etc. 4. The tank outlet valve 8 and diluent stop valve 14 are configured to be controlled.

以下この廃液計量制御装置16の構成を第2図
を参照して説明する。図中17は廃液供給機構運
転操作器であつて、この廃液供給機構運転操作器
17を操作することによつて廃液供給機構運転指
令信号S1がアンド回路18に送られるように構成
される。また、前記廃液量検出器9から廃液量信
号S2は加減演算器19に送られるように構成され
ている。また、20はドラム缶6に充填される放
射性廃液の充填量を設定する充填量設定器(以
下、詰め量設定器と称す)であつて、この詰め量
設定器20からは詰め量設定信号S3が上記加減演
算器19に送られる。そして、この加減演算器1
9では上記廃液量信号S2と詰め量設定信号S3との
偏差を求め、廃液量偏差信号S4を出力するように
構成されている。そして、この廃液量偏差信号S4
は偏差判断器21に送られ、この廃液量偏差信号
S4が正すなわち廃液計量タンク1内の放射性廃液
の量が詰め量設定値より小さい場合に廃液供給許
可信号S5を上記のアンド回路18に送るように構
成されている。また、22は関数発生器であつ
て、この関数発生器22には上記廃液量検出器9
から廃液量信号S2、加減演算器19からの廃液量
偏差信号S4および前記放射線検出器10からの出
力信号S6が入力されるように構成されている。そ
して、この関数発生器22はこれらの信号にもと
づいて、現在廃液計量タンク1内に貯溜されてい
る放射性廃液に廃液量偏差値に対応した量だけ希
釈液を混合して希釈した場合の放射能濃度を算出
し、これに対応した希釈放射能濃度信号S7を加減
演算器23に送るように構成されている。また、
24は放射能濃度設定器であつて、ドラム缶6に
詰められる放射性廃液の許容放射能濃度に対応し
た放射能濃度設定信号S8を上記の加減演算器23
に送るように構成されている。そして、この加減
演算器23では上記の希釈放射能濃度信号S7と放
射能濃度設定信号S8との偏差値を求め、これに対
応した放射能濃度偏差信号S9を偏差判断器24に
送るように構成されている。この偏差判断器24
は加減演算器23から送られる放射能濃度信号S9
が正の場合すなわち関数発生器22で演算された
希釈放射能濃度が放射能濃度設定器24で設定さ
れた放射能濃度設定値より小さな場合に廃液供給
許可信号S10を前記のアンド回路18に送るよう
に構成されている。そしてこのアンド回路18は
前記の廃液供給機構運転指令信号S1、廃液供給許
可信号S5,S10が入力された場合に廃液供給機構
2のポンプ3およびタンク入口弁4に廃液供給信
号S11を送り、このポンプ3を運転するとともに
タンク入口弁4を開弁し、廃液計量タンク1内に
放射性廃液を供給するように構成されている。
The configuration of this waste liquid metering control device 16 will be explained below with reference to FIG. In the figure, reference numeral 17 denotes a waste liquid supply mechanism operating device, and the waste liquid supply mechanism operation command signal S 1 is sent to the AND circuit 18 by operating this waste liquid supply mechanism operating device 17 . Further, the waste liquid amount signal S 2 is sent from the waste liquid amount detector 9 to an addition/subtraction calculator 19 . Further, 20 is a filling amount setting device (hereinafter referred to as a filling amount setting device) for setting the filling amount of radioactive waste liquid to be filled into the drum 6, and this filling amount setting device 20 outputs a filling amount setting signal S3. is sent to the addition/subtraction calculator 19. And this addition/subtraction calculator 1
At 9, the deviation between the waste liquid amount signal S 2 and the filling amount setting signal S 3 is determined, and a waste liquid amount deviation signal S 4 is output. Then, this waste liquid amount deviation signal S 4
is sent to the deviation judge 21, and this waste liquid amount deviation signal
It is configured to send a waste liquid supply permission signal S 5 to the above-mentioned AND circuit 18 when S 4 is positive, that is, when the amount of radioactive waste liquid in the waste liquid measuring tank 1 is smaller than the filling amount setting value. Further, 22 is a function generator, and this function generator 22 has the above-mentioned waste liquid amount detector 9.
, a waste liquid amount signal S 2 from the addition/subtraction calculator 19, and an output signal S 6 from the radiation detector 10 are input. Based on these signals, the function generator 22 calculates the radioactivity when the radioactive waste liquid currently stored in the waste liquid measuring tank 1 is diluted by mixing diluting liquid in an amount corresponding to the waste liquid amount deviation value. It is configured to calculate the concentration and send a corresponding diluted radioactivity concentration signal S7 to the addition/subtraction calculator 23. Also,
Reference numeral 24 is a radioactivity concentration setting device, which outputs a radioactivity concentration setting signal S8 corresponding to the allowable radioactivity concentration of the radioactive waste liquid packed into the drum 6 to the above-mentioned addition/subtraction calculator 23.
It is configured to send to. Then, the addition/subtraction calculator 23 calculates the deviation value between the diluted radioactivity concentration signal S 7 and the radioactivity concentration setting signal S 8 and sends the corresponding radioactivity concentration deviation signal S 9 to the deviation judgment unit 24. It is configured as follows. This deviation judge 24
is the radioactivity concentration signal S 9 sent from the addition/subtraction calculator 23
is positive, that is, when the diluted radioactivity concentration calculated by the function generator 22 is smaller than the radioactivity concentration setting value set by the radioactivity concentration setting device 24, the waste liquid supply permission signal S10 is sent to the AND circuit 18. configured to send. This AND circuit 18 sends a waste liquid supply signal S 11 to the pump 3 and tank inlet valve 4 of the waste liquid supply mechanism 2 when the waste liquid supply mechanism operation command signal S 1 and waste liquid supply permission signals S 5 and S 10 are input. The pump 3 is operated, the tank inlet valve 4 is opened, and the radioactive waste liquid is supplied into the waste liquid measuring tank 1.

また、前記加減演算器19から出力された廃液
量偏差信号S4はメモリ回路25に送られ、このメ
モリ回路25はこの廃液量偏差信号Sの最小値を
記憶し、この廃液量偏差最小値信号S12を加減演
算器26に送るように構成されている。また、2
7は希釈液積分器であつて、前記希釈液流量検出
器14からの希釈液流量信号S12が入力されるよ
うに構成されている。そして、この希釈液積分器
27は希釈液流量信号S13を積分し、供給された
希釈液の量を求め、この希釈液供給量信号S14
上記の加減演算器26に送るように構成されてい
る。そして、この加減演算器26では上記廃液偏
差最小値信号S12と希釈液供給量信号S14との偏差
を求め、この希釈液偏差信号S15を偏差判断器2
7に送るように構成されている。そしてこの偏差
判断器27は希釈液偏差信号S15が正の場合すな
わち希釈液の供給量が廃液計量タンク1内の放射
性廃液と詰め量設定値との差より小さい場合に希
釈許可信号S16をアンド回路28に送るように構
成されている。また、29は希釈操作器であつ
て、この希釈操作器29を操作することにより上
記アンド回路28に希釈指令信号S17が送られる
ように構成されている。そして、このアンド回路
28は上記の希釈許可信号S16および希釈指令信
号S17が入力した場合に希釈液止弁14に開弁信
号S18を送り、この希釈液止弁14を開弁してド
ラム缶6内に希釈液を供給するように構成されて
いる。なお、前記メモリ回路25および希釈液積
分器27は計量完了操作器29から出力される計
量完了信号S19によつてリセツトされるように構
成されている。
Further, the waste liquid amount deviation signal S 4 outputted from the addition/subtraction calculator 19 is sent to the memory circuit 25, and this memory circuit 25 stores the minimum value of this waste liquid amount deviation signal S. S 12 is configured to be sent to the addition/subtraction calculator 26 . Also, 2
Reference numeral 7 denotes a diluent integrator, which is configured to receive the diluent flow rate signal S12 from the diluent flow rate detector 14. The diluent integrator 27 is configured to integrate the diluent flow rate signal S 13 to determine the amount of supplied diluent, and send this diluent supply amount signal S 14 to the addition/subtraction calculator 26. ing. Then, the addition/subtraction calculator 26 calculates the deviation between the waste liquid deviation minimum value signal S 12 and the diluted liquid supply amount signal S 14 , and sends this diluted liquid deviation signal S 15 to the deviation judgment unit 2.
7. The deviation judge 27 outputs a dilution permission signal S 16 when the dilution liquid deviation signal S 15 is positive, that is, when the supply amount of the dilution liquid is smaller than the difference between the radioactive waste liquid in the waste liquid measuring tank 1 and the filling amount setting value. The signal is configured to be sent to the AND circuit 28. Further, reference numeral 29 is a dilution operating device, and is configured such that a dilution command signal S 17 is sent to the AND circuit 28 by operating this dilution operating device 29. Then, this AND circuit 28 sends a valve opening signal S 18 to the dilution liquid stop valve 14 when the above-mentioned dilution permission signal S 16 and dilution command signal S 17 are input, and opens this dilution liquid stop valve 14. It is configured to supply diluent into the drum 6. The memory circuit 25 and diluent integrator 27 are configured to be reset by a metering completion signal S19 outputted from a metering completion operator 29.

また、30は廃液移送操作器であつて、この廃
液移送操作器30を操作することによつて廃液移
送機構5のタンク出口弁8に開弁信号S20が送ら
れ、このタンク出口弁8が開弁して廃液計量タン
ク1内の放射性廃液がドラム缶6内に充填される
ように構成されている。
Further, 30 is a waste liquid transfer operation device, and by operating this waste liquid transfer operation device 30, a valve opening signal S20 is sent to the tank outlet valve 8 of the waste liquid transfer mechanism 5, and this tank outlet valve 8 is The valve is opened so that the radioactive waste liquid in the waste liquid measuring tank 1 is filled into the drum can 6.

次にこの一実施例の作用を説明する。まず、廃
液供給機構運転操作器17を操作してアンド回路
18に廃液供給機構運転指令信号S1を送る。そし
てこの場合、廃液計量タンク1内が空であれば廃
液量検出器9から送られる廃液量信号S2および放
射線検出器10の出力信号S6のレベルは低いた
め、加減演算器19からの廃液量偏差信号S4は正
であり、よつて偏差判断器21からアンド回路1
8に廃液供給許可信号S5が送られる。また関数発
生器22から出力される希釈放射能濃度信号S7
レベルも低いので加減演算器23から出力される
放射能濃度偏差信号S9は正であり、よつて偏差演
算器24からアンド回路18に廃液供給許可信号
S10が送られる。よつてこのアンド回路18から
廃液供給信号S11が出力し、廃液供給機構2のポ
ンプ3が運転されるとともにタンク入口弁4が開
弁し、この廃液計量タンク1内に放射性廃液が供
給される。そしてこの廃液計量タンク1内の放射
性廃液の液位が上昇してゆくと廃液量信号S2およ
び放射能濃度信号S6のレベルが上昇する。そし
て、放射性廃液の放射能濃度が高い場合にはこの
廃液計量タンク1内の放射性廃液の液位が詰め量
設定値に達する前に関数発生器22から出力され
る希釈放射能濃度信号S7が放射能濃度設定器24
から出力される放射能濃度信号S8と等しくなり、
加減演算器23から出力される放射能濃度偏差信
号S9が零となり、偏差判断器24からの廃液供給
許可信号S10が断たれる。よつてアンド回路18
からの廃液供給信号S11が断たれ、廃液供給機構
2のポンプ3が停止するとともにタンク入口弁4
が閉弁し、放射性廃液の供給が停止される。そし
て、この場合に廃液計量タンク1内に溜つた放射
性廃液の量はこれを希釈液で希釈して全体の量を
ドラム缶6への詰め量の設定値と等しくした場合
にその放射能濃度が放射能濃度設定値と等しくな
る量である。また、この場合に加減演算器19か
ら出力された廃液量偏差信号S4の最小値はメモリ
回路25に記憶される。
Next, the operation of this embodiment will be explained. First, the waste liquid supply mechanism operation control device 17 is operated to send the waste liquid supply mechanism operation command signal S 1 to the AND circuit 18 . In this case, if the inside of the waste liquid measuring tank 1 is empty, the level of the waste liquid amount signal S 2 sent from the waste liquid amount detector 9 and the output signal S 6 of the radiation detector 10 is low, so that the waste liquid from the addition/subtraction calculator 19 is The quantity deviation signal S4 is positive, and therefore the deviation judgment device 21 outputs the AND circuit 1.
A waste liquid supply permission signal S5 is sent to 8. Furthermore, since the level of the diluted radioactivity concentration signal S 7 outputted from the function generator 22 is also low, the radioactivity concentration deviation signal S 9 outputted from the addition/subtraction calculator 23 is positive, and therefore the deviation calculation unit 24 outputs the signal from the AND circuit. Waste liquid supply permission signal to 18
S10 sent. Therefore, the waste liquid supply signal S 11 is output from this AND circuit 18, the pump 3 of the waste liquid supply mechanism 2 is operated, and the tank inlet valve 4 is opened, and radioactive waste liquid is supplied into the waste liquid measuring tank 1. . As the level of the radioactive waste liquid in the waste liquid measuring tank 1 rises, the levels of the waste liquid amount signal S2 and the radioactivity concentration signal S6 rise. When the radioactivity concentration of the radioactive waste liquid is high, the diluted radioactivity concentration signal S 7 output from the function generator 22 before the liquid level of the radioactive waste liquid in the waste liquid measuring tank 1 reaches the filling amount set value Radioactivity concentration setting device 24
It is equal to the radioactivity concentration signal S8 output from
The radioactivity concentration deviation signal S 9 output from the addition/subtraction calculator 23 becomes zero, and the waste liquid supply permission signal S 10 from the deviation judge 24 is cut off. Yotsute AND circuit 18
The waste liquid supply signal S11 from the tank is cut off, the pump 3 of the waste liquid supply mechanism 2 is stopped, and the tank inlet valve 4 is stopped.
The valve is closed and the supply of radioactive waste liquid is stopped. In this case, when the amount of radioactive waste liquid accumulated in the waste liquid measuring tank 1 is diluted with a diluent and the total amount is made equal to the set value of the amount to be filled into the drum can 6, its radioactive concentration becomes radioactive. This is the amount that is equal to the set value of the functional concentration. Further, in this case, the minimum value of the waste liquid amount deviation signal S 4 output from the addition/subtraction calculator 19 is stored in the memory circuit 25 .

次に廃液移送操作器30を操作し、タンク出口
弁8を開弁し、廃液計量タンク1内の放射性廃液
をドラム缶6内に移送する。
Next, the waste liquid transfer operation device 30 is operated, the tank outlet valve 8 is opened, and the radioactive waste liquid in the waste liquid measuring tank 1 is transferred into the drum can 6.

次に希釈操作器29を操作し、アンド回路28
に希釈指令信号S17を送る。そして、この場合、
前記メモリ回路25には廃液量偏差信号S4の最小
値が記憶されており、このメモリ回路25からは
廃液量偏差最小値信号S12が加減演算器26に送
られる。また、この加減演算器26には希釈液積
分器27から希釈液供給量信号S14が送られるが、
ドラム缶1内に希釈液が送られていない場合には
この希釈液供給量信号S14は零である。よつてこ
の加減演算器26から出力される希釈液偏差信号
S15は正であり、偏差判断器27からアンド回路
28に希釈許可信号S16が送られる。したがつて
このアンド回路28から希釈液止弁14に開弁信
号S18が送られ、この希釈液止弁14が開弁し、
ドラム缶6内に希釈液が供給される。そして、こ
のドラム缶6内に供給される希釈液の流量は希釈
液流量検出器14で検出され、希釈液流量信号
S13が希釈液積分器27に送られ、積分される。
そして、この希釈液積分器27からは希釈液供給
信号S14が加減演算器26に送られる。そして、
この希釈液供給量信号S14がメモリ回路25から
出力される廃液量偏差最小値信号S12と等しくな
ると加減演算器26からの希釈液偏差信号S15
零となり、よつて偏差判断器27からアンド回路
28に送られている希釈許可信号S16が断たれ、
希釈液止弁14が開弁されてドラム缶6への希釈
液の供給が停止する。したがつて、このドラム缶
6には廃液量偏差最小値すなわち詰め量設定器2
0で設定されている詰め量設定値とドラム缶6内
に充填された放射性廃液の量との差に対応した量
の希釈液が供給される。したがつて、ドラム缶6
内の放射性廃液はこの希釈液で希釈され、その放
射能濃度は放射能濃度設定器24で設定されてい
る所定の放射能濃度となり、またドラム缶6内に
詰められた放射性廃液と希釈液の総量は詰め量設
定器20で設定された所定の詰め量となる。
Next, operate the dilution operator 29, and the AND circuit 28
Send dilution command signal S17 to. And in this case,
The minimum value of the waste liquid amount deviation signal S 4 is stored in the memory circuit 25 , and the waste liquid amount deviation minimum value signal S 12 is sent from this memory circuit 25 to the addition/subtraction calculator 26 . Further, a diluent supply amount signal S 14 is sent to this addition/subtraction calculator 26 from a diluent integrator 27.
When no diluent is being sent into the drum 1, this diluent supply amount signal S14 is zero. Therefore, the diluent deviation signal output from the addition/subtraction calculator 26
S 15 is positive, and a dilution permission signal S 16 is sent from the deviation judge 27 to the AND circuit 28 . Therefore, a valve opening signal S18 is sent from this AND circuit 28 to the dilution liquid stop valve 14, and this dilution liquid stop valve 14 is opened.
A diluent is supplied into the drum 6. The flow rate of the diluent supplied into the drum can 6 is detected by a diluent flow rate detector 14, and a diluent flow rate signal is detected.
S13 is sent to diluent integrator 27 and integrated.
The diluent integrator 27 sends the diluent supply signal S 14 to the addition/subtraction calculator 26 . and,
When this diluted liquid supply amount signal S 14 becomes equal to the waste liquid amount deviation minimum value signal S 12 outputted from the memory circuit 25, the diluted liquid deviation signal S 15 from the addition/subtraction calculator 26 becomes zero, and therefore the deviation judgment unit 27 The dilution permission signal S16 sent to the AND circuit 28 is cut off,
The diluent stop valve 14 is opened and the supply of diluent to the drum 6 is stopped. Therefore, this drum 6 has a minimum waste liquid amount deviation value, that is, a filling amount setting device 2.
The diluent is supplied in an amount corresponding to the difference between the filling amount setting value set at 0 and the amount of radioactive waste liquid filled in the drum 6. Therefore, drum 6
The radioactive waste liquid in the drum 6 is diluted with this diluent, and its radioactivity concentration becomes the predetermined radioactivity concentration set by the radioactivity concentration setting device 24, and the total amount of the radioactive waste liquid and diluted liquid packed in the drum can 6. is the predetermined filling amount set by the filling amount setting device 20.

そして、このようにして放射性廃液の計量と希
釈が終了したらこのドラム缶6内に所定量のセメ
ントを流し込み、放射性廃液と混合して固化し、
貯蔵処理される。
After measuring and diluting the radioactive waste liquid in this way, a predetermined amount of cement is poured into the drum 6, mixed with the radioactive waste liquid, and solidified.
Stored and processed.

なお、放射性廃液の放射能濃度が放射能濃度設
定器24で設定されている所定の放射能濃度より
低い場合には関数発生器22から出力される希釈
放射能濃度信号S7が放射能濃度設定器24で設定
されている所定の放射能濃度以上となることはな
い。そして、この場合には廃液計量タンク1内に
詰め量設定器20で設定されている所定の詰め量
まで放射性廃液が溜ると加減演算器19から出力
される廃液量偏差信号S4が零となり、偏差判断器
21からアンド回路18に送られている廃液供給
許可信号S5が断たれるので廃液の供給が停止す
る。また、この場合にもメモリ回路25に記憶さ
れる廃液量偏差最小信号S12は零となるので、希
釈操作器29を操作してもドラム缶6内に希釈液
は供給されない。したがつて、この場合にはドラ
ム缶6内に放射性廃液が希釈されずに詰め量設定
器20で設定された所定の詰め量だけ送られる。
Note that if the radioactivity concentration of the radioactive waste liquid is lower than the predetermined radioactivity concentration set by the radioactivity concentration setting device 24, the diluted radioactivity concentration signal S7 output from the function generator 22 is used as the radioactivity concentration setting. The radioactivity concentration will never exceed a predetermined radioactivity concentration set in the device 24. In this case, when the radioactive waste liquid accumulates in the waste liquid measuring tank 1 to a predetermined filling amount set by the filling amount setting device 20, the waste liquid amount deviation signal S 4 output from the adjustment calculator 19 becomes zero. Since the waste liquid supply permission signal S5 sent from the deviation judger 21 to the AND circuit 18 is cut off, the supply of waste liquid is stopped. Also in this case, the waste liquid amount deviation minimum signal S12 stored in the memory circuit 25 is zero, so no diluent is supplied into the drum 6 even if the dilution operator 29 is operated. Therefore, in this case, the radioactive waste liquid is sent into the drum 6 in a predetermined filling amount set by the filling amount setting device 20 without being diluted.

以上の如くこの一実施例は放射性廃液の放射能
濃度が高い場合には詰め量が少なくなるので、こ
の放射性廃液を詰めたドラム缶が規定以上の放射
能レベルとなることはなく、その取扱がきわめて
容易となる。また、この一実施例では放射性廃液
の放射能濃度が高い場合には希釈液で希釈してそ
の放射能濃度を所定の値以下とするのでセメント
充填等の際の取扱が容易となり、また放射性廃液
の量が常に一定であるのでセメントとの混合比が
一定となり、作業が容易となる。
As described above, in this embodiment, if the radioactivity concentration of the radioactive waste liquid is high, the amount of filling will be small, so the drum can filled with this radioactive waste liquid will not have a radioactivity level higher than the specified level, and its handling will be extremely difficult. It becomes easier. In addition, in this embodiment, when the radioactive concentration of the radioactive waste liquid is high, it is diluted with a diluent to bring the radioactive concentration below a predetermined value, making it easier to handle when filling cement, etc. Since the amount of cement is always constant, the mixing ratio with cement is constant, making the work easier.

なお、本発明は上記の一実施例には限定されな
い。
Note that the present invention is not limited to the above embodiment.

たとえば放射能濃度が高い場合に希釈液で希釈
するように構成する必要は必らずしもなく、放射
性廃液の量の少ない分だけセメント等を余分に充
填するようにしてもよい。
For example, when the radioactivity concentration is high, it is not necessarily necessary to dilute the radioactive waste with a diluent, and an extra amount of cement or the like may be filled to compensate for the small amount of radioactive waste.

また、本発明はセメントで固化するものに限ら
ずその他アスフアルト、合成樹脂等で固化する場
合にも適用できるものである。
Furthermore, the present invention is applicable not only to those that are solidified with cement, but also to those that are solidified with asphalt, synthetic resins, and the like.

また、廃液計量制御装置の構成は必らずしも前
記第1実施例のものには限定されない。
Further, the configuration of the waste liquid metering control device is not necessarily limited to that of the first embodiment.

〔発明の効果〕〔Effect of the invention〕

上述の如く本発明は、放射性廃液を計量するた
めの廃液計量タンクと、この廃液計量タンクに放
射性廃液を導入する廃液供給手段と、この廃液供
給手段から前記廃液計量タンクに導入された放射
性廃液量を検出する廃液量検出手段と、前記廃液
計量タンクに導入された放射性廃液の放射線量を
検出する放射線検出手段と、前記廃液計量タンク
に導入された放射性廃液を固化貯蔵用の貯蔵容器
に移送する廃液移送手段と、前記貯蔵容器に希釈
液を注入する希釈液供給手段と、前記廃液計量タ
ンクに導入される放射性廃液量および前記貯蔵容
器に注入される希釈液量を制御する制御手段とを
具備し、前記制御手段は、前記貯蔵容器に貯蔵さ
れる放射性廃液の最大詰め量を設定する詰め量設
定器と、前記廃液量検出手段から出力された廃液
量検出信号と前記詰め量設定器から出力された詰
め量設定信号との偏差を求める偏差演算手段と、
前記廃液量検出手段で検出された廃液量が前記詰
め量設定器で設定された放射性廃液の最大詰め量
よりも小さい場合に廃液供給許可信号を出力する
第1の偏差判断器と、前記廃液量検出手段、放射
線検出手段、詰め量設定器および偏差演算手段か
らの出力信号を受け前記偏差演算手段で算出され
た偏差値に対応した量の希釈液を廃液計量タンク
に加えた場合の放射性廃液の単位体積当りの希釈
放射能濃度を算出する希釈放射能濃度算出手段
と、前記貯蔵容器に貯蔵される放射性廃液の単位
体積当りの許容放射能濃度を設定する放射能濃度
設定器と、前記希釈放射能濃度算出手段で算出さ
れた希釈放射能濃度が前記放射能濃度設定器で設
定された許容放射能濃度よりも小さい場合に廃液
供給許可信号を出力する第2の偏差判断器と、こ
の第2の偏差判断器または前記第1の偏差判断器
のいずれか一方が廃液供給許可信号を出力しなく
なつたときに前記廃液供給手段に廃液供給停止信
号を送出する廃液供給停止信号送出手段と、前記
希釈液供給手段から前記貯蔵容器に注入された希
釈液量を検出する希釈液量検出手段と、前記第1
の偏差演算手段から出力された偏差信号の最小値
を記憶する記憶手段と、前記希釈液量検出手段で
検出された希釈液量が前記記憶手段に記憶された
値に達したとき前記希釈液供給手段に希釈液供給
停止信号を送出する第3の偏差判断器とを有する
ものである。
As described above, the present invention provides a waste liquid measuring tank for measuring radioactive waste liquid, a waste liquid supply means for introducing the radioactive waste liquid into the waste liquid measuring tank, and an amount of radioactive waste liquid introduced from the waste liquid supply means into the waste liquid measuring tank. a waste liquid amount detection means for detecting the radiation amount of the radioactive waste liquid introduced into the waste liquid measuring tank; a radiation detecting means for detecting the radiation amount of the radioactive waste liquid introduced into the waste liquid measuring tank; and a radiation detecting means for detecting the radiation amount of the radioactive waste liquid introduced into the waste liquid measuring tank; A waste liquid transfer means, a diluent supply means for injecting a diluent into the storage container, and a control means for controlling the amount of radioactive waste introduced into the waste liquid measuring tank and the amount of diluted liquid injected into the storage container. The control means includes a filling amount setting device for setting a maximum filling amount of radioactive waste liquid stored in the storage container, a waste liquid amount detection signal output from the waste liquid amount detection means, and an output from the filling amount setting device. deviation calculating means for calculating the deviation from the filling amount setting signal that has been set;
a first deviation determination device that outputs a waste liquid supply permission signal when the amount of waste liquid detected by the waste liquid amount detection means is smaller than the maximum filling amount of radioactive waste liquid set by the filling amount setting device; Radioactive waste liquid when an amount of diluent corresponding to the deviation value calculated by the deviation calculation means in response to the output signals from the detection means, radiation detection means, fill amount setting device, and deviation calculation means is added to the waste liquid measuring tank. a diluted radioactivity concentration calculation means for calculating a diluted radioactivity concentration per unit volume; a radioactivity concentration setting device for setting an allowable radioactivity concentration per unit volume of the radioactive waste liquid stored in the storage container; a second deviation determination device that outputs a waste liquid supply permission signal when the diluted radioactivity concentration calculated by the radioactivity concentration calculation means is smaller than the allowable radioactivity concentration set by the radioactivity concentration setting device; a waste liquid supply stop signal sending means for sending a waste liquid supply stop signal to the waste liquid supply means when either the deviation judger or the first deviation judge no longer outputs the waste liquid supply permission signal; diluent amount detection means for detecting the amount of diluent injected into the storage container from the diluent supply means;
storage means for storing the minimum value of the deviation signal outputted from the deviation calculation means; and a storage means for storing the minimum value of the deviation signal outputted from the deviation calculation means; and a third deviation judger for sending a diluent supply stop signal to the means.

したがつて、本発明は、廃液供給手段から廃液
計量タンクに導入された放射性廃液の廃液量また
は放射能レベルのいずれか一方があらかじめ設定
された値になると、廃液供給手段からの廃液供給
が停止し、廃液計量タンクに導入された放射性廃
液が廃液移送手段により固化貯蔵用の貯蔵容器に
移送されるので、所定レベル以下の放射性廃液を
貯蔵容器に貯蔵することができる。また、貯蔵容
器に貯蔵される放射性廃液があらかじめ設定され
た詰め量よりも少ない場合には、詰め量と廃液量
との差に対応した量の希釈液が貯蔵容器に注入さ
れるので、貯蔵容器に貯蔵される高放射能レベル
の放射性廃液を希釈液で希釈して規定レベル以下
にすることができるとともに、放射性廃液と共に
貯蔵容器に充填される固定化剤の充填量を一定に
することができる。
Therefore, in the present invention, when either the waste amount or the radioactivity level of the radioactive waste introduced from the waste liquid supply means into the waste liquid measuring tank reaches a preset value, the waste liquid supply from the waste liquid supply means is stopped. However, since the radioactive waste liquid introduced into the waste liquid measuring tank is transferred to the storage container for solidification storage by the waste liquid transfer means, it is possible to store the radioactive waste liquid below a predetermined level in the storage container. In addition, if the amount of radioactive waste liquid stored in the storage container is less than the preset filling amount, an amount of diluted liquid corresponding to the difference between the amount of filling and the amount of waste liquid is injected into the storage container. It is possible to dilute the radioactive waste liquid with a high radioactivity level stored in the storage container with a diluent to bring it below the specified level, and it is also possible to keep the amount of fixing agent filled into the storage container together with the radioactive waste liquid constant. .

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

図は本発明の一実施例を示し、第1図は概略構
成図、第2図は廃液計量制御装置の概略構成図で
ある。 1……廃液計量タンク、2……廃液供給機構、
5……廃液移送機構、6……ドラム缶(貯蔵容
器)、9……廃液量検出器、10……放射線検出
器、11……希釈液供給機構、16……廃液計量
制御装置。
The drawings show an embodiment of the present invention, with FIG. 1 being a schematic configuration diagram and FIG. 2 being a schematic configuration diagram of a waste liquid metering control device. 1... Waste liquid measuring tank, 2... Waste liquid supply mechanism,
5... Waste liquid transfer mechanism, 6... Drum can (storage container), 9... Waste liquid amount detector, 10... Radiation detector, 11... Diluted liquid supply mechanism, 16... Waste liquid metering control device.

Claims (1)

【特許請求の範囲】[Claims] 1 放射性廃液を計量するための廃液計量タンク
1と、この廃液計量タンクに放射性廃液を導入す
る廃液供給手段2と、この廃液供給手段から前記
廃液計量タンクに導入された放射性廃液量を検出
する廃液量検出手段9と、前記廃液計量タンクに
導入された放射性廃液の放射線量を検出する放射
線検出手段10と、前記廃液計量タンクに導入さ
れた放射性廃液を固化貯蔵用の貯蔵容器に移送す
る廃液移送手段5と、前記貯蔵容器に希釈液を注
入する希釈液供給手段11と、前記廃液計量タン
クに導入される放射性廃液量および前記貯蔵容器
に注入される希釈液量を制御する制御手段16と
を具備し、前記制御手段は、前記貯蔵容器に貯蔵
される放射性廃液の最大詰め量を設定する詰め量
設定器20と、前記廃液量検出手段から出力され
た廃液量検出信号と前記詰め量設定器から出力さ
れた詰め量設定信号との偏差を求める偏差演算手
段19と、前記廃液量検出手段で検出された廃液
量が前記詰め量設定器で設定された放射性廃液の
詰め量よりも小さい場合に廃液供給許可信号を出
力する第1の偏差判断器21と、前記廃液量検出
手段、放射線検出手段、詰め量設定器および偏差
演算手段からの出力信号を受け前記偏差演算手段
で算出された偏差値に対応した量の希釈液を廃液
計量タンクに加えた場合の放射性廃液の単位体積
当りの希釈放射能濃度を算出する希釈放射能濃度
算出手段22と、前記貯蔵容器に貯蔵される放射
性廃液の単位体積当りの許容放射能濃度を設定す
る放射能濃度設定器24と、前記希釈放射能濃度
算出手段で算出された希釈放射能濃度が前記放射
能濃度設定器で設定された許容放射能濃度よりも
小さい場合に廃液供給許可信号を出力する第2の
偏差判断器24と、この第2の偏差判断器または
前記第1の偏差判断器のいずれか一方が廃液供給
許可信号を出力しなくなつたときに前記廃液供給
手段に廃液供給停止信号を送出する廃液供給停止
信号送出手段18と、前記希釈液供給手段から前
記貯蔵容器に注入された希釈液量を検出する希釈
液量検出手段27と、前記第1の偏差演算手段か
ら出力された偏差信号の最小値を記憶する記憶手
段25と、前記希釈液量検出手段で検出された希
釈液量が前記記憶手段に記憶された値に達したと
き前記希釈液供給手段に希釈液供給停止信号を送
出する第3の偏差判断器27とを有することを特
徴とする放射性廃液処理設備。
1 A waste liquid measuring tank 1 for measuring radioactive waste liquid, a waste liquid supply means 2 for introducing radioactive waste liquid into this waste liquid measuring tank, and a waste liquid for detecting the amount of radioactive waste liquid introduced from this waste liquid supply means into the waste liquid measuring tank. a radiation detection means 10 for detecting the radiation dose of the radioactive waste liquid introduced into the waste liquid measuring tank; and a waste liquid transfer unit for transferring the radioactive waste liquid introduced into the waste liquid measuring tank to a storage container for solidification storage. means 5, diluent supply means 11 for injecting diluent into the storage container, and control means 16 for controlling the amount of radioactive waste introduced into the waste liquid measuring tank and the amount of diluent injected into the storage container. The control means includes a filling amount setting device 20 that sets the maximum filling amount of radioactive waste liquid stored in the storage container, and a waste liquid amount detection signal output from the waste liquid amount detection means and the filling amount setting device. a deviation calculation means 19 for calculating a deviation from a filling amount setting signal outputted from the filling amount setting signal; A first deviation determination device 21 that outputs a waste liquid supply permission signal, and a deviation value calculated by the deviation calculation means in response to output signals from the waste liquid amount detection means, the radiation detection means, the filling amount setting device, and the deviation calculation means. diluted radioactivity concentration calculation means 22 for calculating the diluted radioactivity concentration per unit volume of the radioactive waste liquid when an amount of diluted liquid corresponding to the amount of diluted liquid is added to the waste liquid measuring tank; and a unit of radioactive waste liquid stored in the storage container. A radioactivity concentration setter 24 that sets an allowable radioactivity concentration per volume, and a diluted radioactivity concentration calculated by the diluted radioactivity concentration calculation means are higher than the allowable radioactivity concentration set by the radioactivity concentration setter. When the second deviation judge 24 outputs a waste liquid supply permission signal when the difference is small, and either the second deviation judge or the first deviation judge ceases to output a waste liquid supply permission signal. a waste liquid supply stop signal sending means 18 for sending a waste liquid supply stop signal to the waste liquid supply means; a diluted liquid amount detection means 27 for detecting the amount of diluted liquid injected into the storage container from the diluted liquid supply means; A storage means 25 for storing the minimum value of the deviation signal outputted from the first deviation calculation means; A radioactive waste liquid processing equipment characterized by having a third deviation determination device 27 that sends a diluent supply stop signal to the diluent supply means.
JP18864782A 1982-10-27 1982-10-27 Radioactive liquid waste processing facility Granted JPS5979198A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP18864782A JPS5979198A (en) 1982-10-27 1982-10-27 Radioactive liquid waste processing facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP18864782A JPS5979198A (en) 1982-10-27 1982-10-27 Radioactive liquid waste processing facility

Publications (2)

Publication Number Publication Date
JPS5979198A JPS5979198A (en) 1984-05-08
JPH0477279B2 true JPH0477279B2 (en) 1992-12-07

Family

ID=16227375

Family Applications (1)

Application Number Title Priority Date Filing Date
JP18864782A Granted JPS5979198A (en) 1982-10-27 1982-10-27 Radioactive liquid waste processing facility

Country Status (1)

Country Link
JP (1) JPS5979198A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2799074B2 (en) * 1990-11-30 1998-09-17 株式会社東芝 Radioactive waste solidification method
JP5914017B2 (en) * 2012-02-02 2016-05-11 鹿島建設株式会社 Treatment system and treatment method for radioactive substance-containing water or radioactive substance-containing slurry

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5210200B2 (en) * 1971-10-18 1977-03-22
JPS4882300A (en) * 1972-02-05 1973-11-02
JPS51111600A (en) * 1975-03-28 1976-10-01 Hitachi Ltd Hardening process of radioactive waste substance

Also Published As

Publication number Publication date
JPS5979198A (en) 1984-05-08

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