JPH0664187B2 - Treatment method of radioactive waste liquid - Google Patents

Treatment method of radioactive waste liquid

Info

Publication number
JPH0664187B2
JPH0664187B2 JP61197939A JP19793986A JPH0664187B2 JP H0664187 B2 JPH0664187 B2 JP H0664187B2 JP 61197939 A JP61197939 A JP 61197939A JP 19793986 A JP19793986 A JP 19793986A JP H0664187 B2 JPH0664187 B2 JP H0664187B2
Authority
JP
Japan
Prior art keywords
liquid
treatment
recovery rate
property
flow rate
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
JP61197939A
Other languages
Japanese (ja)
Other versions
JPS6353499A (en
Inventor
大介 種田
和則 鈴木
敬 加藤
総一 松永
Original Assignee
科学技術庁原子力局長
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 科学技術庁原子力局長 filed Critical 科学技術庁原子力局長
Priority to JP61197939A priority Critical patent/JPH0664187B2/en
Publication of JPS6353499A publication Critical patent/JPS6353499A/en
Publication of JPH0664187B2 publication Critical patent/JPH0664187B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Landscapes

  • Separation Using Semi-Permeable Membranes (AREA)

Description

【発明の詳細な説明】Detailed Description of the Invention

発明の目的 Purpose of the invention

【産業上の利用分野】[Industrial applications]

本発明は、逆浸透法を用いた放射性廃液の処理方法の改
良に関する。
The present invention relates to improvement of a method for treating radioactive waste liquid using a reverse osmosis method.

【従来の技術】[Prior art]

原子力発電所や核燃料再生処理工場から発生する中低レ
ベルの放射性廃液の処理手段のひとつとして、廃液を逆
浸透膜装置に供給し、供給液を処理液と濃縮液とに分離
し、処理液を放出または再利用し、濃縮液は回収して固
化処理等に送る技術がある。 これを実施する従来の逆浸透膜装置では、処理液ライン
に設けた流量計の測定値を流量調節計へ入力し、その測
定値が一定になるように濃縮液の流量を制御する方法
か、または操作圧力を測定し、その圧力を制御する方法
がとられている。 処理液を河川や海洋に放出するには、処理液の性状が法
令で規制された条件を満たすようにしなければならない
ことはもちろんである。従来の処理方法では、供給液の
性状が変化すると処理液の性状も変化してしまう。従っ
て、常に規制に合致できるようにするためには、運転条
件を予め大きく安全サイドにとらなければならない。す
なわち、供給液の濃度が最も高い場合でも処理液の性状
が所定のレベルを超えないように配慮して、運転する必
要がある。当然に逆浸透装置は大容量のものが要求さ
れ、建設費、運転費のどちらも嵩み、経済的には不利と
なる。
As one of the means for treating medium to low level radioactive waste liquid generated from a nuclear power plant or a nuclear fuel regeneration treatment plant, the waste liquid is supplied to a reverse osmosis membrane device, the supply liquid is separated into a processing liquid and a concentrated liquid, and the processing liquid is separated. There is a technology of releasing or reusing, collecting the concentrated liquid, and sending it to a solidification treatment or the like. In the conventional reverse osmosis membrane device for carrying out this, a method of inputting the measured value of the flow meter provided in the treatment liquid line to the flow rate controller and controlling the flow rate of the concentrated solution so that the measured value becomes constant, Alternatively, a method of measuring the operating pressure and controlling the pressure is adopted. Of course, in order to release the treatment liquid to the river or the ocean, the properties of the treatment liquid must satisfy the conditions regulated by law. In the conventional processing method, when the property of the supply liquid changes, the property of the processing liquid also changes. Therefore, in order to be able to always comply with the regulations, it is necessary to set the driving conditions on the large safety side in advance. That is, it is necessary to operate so that the property of the treatment liquid does not exceed a predetermined level even when the concentration of the supply liquid is the highest. Naturally, a reverse osmosis device is required to have a large capacity, which increases both construction cost and operating cost, which is economically disadvantageous.

【発明が解決しようとする問題点】[Problems to be Solved by the Invention]

本発明の目的は、上記した問題を解消し、放射性廃液の
処理を過度に安全側に片寄らせず、しかし安全上必要な
限界を超えないことは確保しつつ、廃液の性状の変化に
追従して経済的に有利に実施できる、逆浸透法を利用し
た処理方法を提供することにある。 発明の構成
The object of the present invention is to solve the above-mentioned problems and to follow the change in the properties of the waste liquid while ensuring that the processing of the radioactive waste liquid is not excessively biased to the safe side, but does not exceed the limit necessary for safety. Another object of the present invention is to provide a treatment method using the reverse osmosis method, which can be economically carried out advantageously. Structure of the invention

【問題点を解決するための手段】[Means for solving problems]

図面を参照して説明すれば、本発明の放射性廃液の処理
方法は、第1図に示すように、放射性廃液を高圧ポンプ
Pにより逆浸透膜装置R/Oに供給して、供給液Fを処
理液Pおよび濃縮液Bに分離し、処理液Pを放出または
再利用し、濃縮液Bを回収して固化処理等する処理方法
において、供給液ラインおよび処理液のラインに溶液の
性状を測定する手段を設けるとともに、処理液および濃
縮液のラインに流量を測定する手段を設け、供給液性
状、処理液性状、処理液流量および濃縮液流量の信号を
回収率調節計に入力して 回収率=(処理液流量/供給液流量) を適切に定め回収率調節計からの出力信号により濃縮液
ラインの圧力調節弁の開度を調節して回収率を制御し、
供給液の性状が悪くなったときは回収率を低くし、良く
なったときは高めることにより、供給液の性状が変化し
ても処理液の性状が所定の範囲内にあるようにしたこと
を特徴とする。 溶液の性状を測定する手段としては、放射性廃液の処理
という観点から適当な因子、たとえば放射能濃度、電導
度などを選択し、これを正確に測定できるセンサーを使
用すればよい。その測定結果により逆浸透膜装置R/O
の回収率を制御する。制御方法としては、供給液の性状
を測定して回収率を制御するフィードフォワード制御、
および処理液の性状を測定して回収率を制御するフィー
ドバック制御のいずれでもよく、もちろんこれらを組合
せた制御によってもよい。 逆浸透膜装置R/Oは、圧力調節弁Vの操作によりその
運転を制御する。圧力調節弁を閉じるほど処理液流量が
増大して濃縮液流量が減少し、回収率が高くなる。 高い回収率で運転を行なうと、処理液流量は多くなる
が、その液性状が悪くなる。すなわち、CF(供給液流量
/濃縮液流量)は大きくなるが、DF(供給液濃度/処理
液濃度)は小さくなる。逆に、回収率を低くして運転す
ると、CFは小さくなるが、DFは大きくなる。このよう
に、処理液の性状はその回収率により変化する。
Referring to the drawings, the method for treating a radioactive liquid waste of the present invention, as shown in FIG. 1, supplies a radioactive liquid waste to a reverse osmosis membrane device R / O by a high-pressure pump P to supply a liquid feed F. In the treatment method of separating the treatment liquid P and the concentrated liquid B, releasing or reusing the treatment liquid P, recovering the concentrated liquid B and solidifying, etc., measure the properties of the solution in the supply liquid line and the treatment liquid line. In addition to providing a means for measuring the flow rate on the lines of the processing liquid and the concentrated liquid, the signals of the supply liquid property, the processing liquid property, the processing liquid flow rate and the concentrated liquid flow rate are input to the recovery rate controller to recover the recovery rate. = (Processing liquid flow rate / Supplying liquid flow rate) is appropriately determined, and the recovery rate is controlled by adjusting the opening degree of the pressure control valve of the concentrate line by the output signal from the recovery rate controller.
When the properties of the feed liquid deteriorate, the recovery rate is lowered, and when it improves, the recovery ratio is increased so that the properties of the treatment liquid remain within the specified range even if the properties of the feed liquid change. Characterize. As a means for measuring the properties of the solution, a sensor which can select an appropriate factor from the viewpoint of treating the radioactive liquid waste, for example, the radioactivity concentration, the electric conductivity, etc., and accurately measure it can be used. Reverse osmosis device R / O
Control the recovery rate of. As a control method, feedforward control for controlling the recovery rate by measuring the properties of the supply liquid,
Also, any of feedback control for controlling the recovery rate by measuring the properties of the treatment liquid may be used, and of course, control combining these may be used. The reverse osmosis membrane device R / O controls its operation by operating the pressure control valve V. As the pressure control valve is closed, the processing liquid flow rate increases, the concentrate flow rate decreases, and the recovery rate increases. When the operation is performed at a high recovery rate, the processing liquid flow rate increases, but the liquid properties deteriorate. That is, CF (supply liquid flow rate / concentration liquid flow rate) increases, but DF (supply liquid concentration / treatment liquid concentration) decreases. On the contrary, when the recovery rate is low, the CF decreases but the DF increases. As described above, the properties of the treatment liquid change depending on the recovery rate.

【作用】[Action]

本発明の方法によれば、供給液または処理液の性状を測
定し、性状がそれまでより悪くなった場合、たとえば放
射能濃度が所定値を超えたときは、回収率を低くして運
転し、装置のDFを大きくすることにより、処理液の性状
を常に一定に保つことができる。 一方、供給液または処理液の性状がよくなった場合に
は、回収率を高くする。装置のDFは小さくなるが、CFを
大きくすることで、処理液性状を一定にして効率の高い
運転をすることができる。 このように、本発明の方法によれば、供給される放射性
廃液の性状が標準の値より悪い場合でも、設定値を満足
する処理液が得られ、また標準の値よりも良い場合には
設定値を満足しつつ処理能力を向上させることができ、
放射性廃液の処理を経済的に行なうことができる。 このような効果は、逆浸透膜装置R/Oを、第2図Aお
よびBに示すように、2段、3段と多段に接続して構成
した場合にいっそう大きくなり、回収率の変化に対する
DFおよびCFの変化の幅を大きくすることができる。
According to the method of the present invention, the properties of the supply liquid or the treatment liquid are measured, and when the properties are worse than before, for example, when the radioactivity concentration exceeds a predetermined value, the recovery rate is lowered and the operation is performed. By increasing the DF of the device, the properties of the processing liquid can be kept constant at all times. On the other hand, when the properties of the supply liquid or the processing liquid are improved, the recovery rate is increased. Although the DF of the equipment becomes smaller, increasing the CF makes it possible to operate with high efficiency while keeping the property of the treatment liquid constant. Thus, according to the method of the present invention, even when the property of the supplied radioactive waste liquid is worse than the standard value, a treatment liquid satisfying the set value can be obtained, and when it is better than the standard value, the set value is set. It is possible to improve the processing capacity while satisfying the value,
The radioactive waste liquid can be treated economically. Such an effect becomes even greater when the reverse osmosis device R / O is configured by connecting two stages, three stages and multiple stages as shown in FIGS.
The width of change in DF and CF can be increased.

【実施例1】 第2図Bに示す構成の3段モジュール式の逆浸透膜装置
を使用して、ヨウ化ナトリウムの溶液を下記の操作条件
で処理した。 第一段逆浸透膜装置回収率 85% 第二段逆浸透膜装置回収率 35〜85% 第三段逆浸透膜装置回収率 60% 供給液I濃度 37ppm すなわち、第一段および第三段の逆浸透膜装置の回収率
を一定とし、第二段での回収率を変化させ、そのときの
NaIのDFおよびCFを求めた。結果は、第3図に示すとお
りである。 第3図から明らかなように、第二段逆浸透膜装置で回収
率を変化させることにより、装置のDFおよびCFが大きく
変化することがわかる。従って、供給液の性状に応じて
回収率を変え、処理液を所望の設定値に規制することが
できる。
Example 1 Using a three-stage modular reverse osmosis membrane device configured as shown in FIG. 2B, a solution of sodium iodide was treated under the following operating conditions. 1st stage reverse osmosis membrane device recovery rate 85% 2nd stage reverse osmosis membrane device recovery rate 35-85% 3rd stage reverse osmosis membrane device recovery rate 60% Feed liquid I - concentration 37ppm That is, 1st stage and 3rd stage The recovery rate of the reverse osmosis membrane device is fixed and the recovery rate in the second stage is changed.
DF and CF of NaI were calculated. The results are as shown in FIG. As is clear from FIG. 3, it is understood that the DF and CF of the device greatly change by changing the recovery rate in the second-stage reverse osmosis device. Therefore, the recovery rate can be changed according to the properties of the supply liquid to regulate the processing liquid to a desired set value.

【実施例2】 上記と同様の3段式の逆浸透膜装置において、運転途中
で供給液のNaNO濃度(電導度により測定)を増加さ
せ、これに対応して第二段逆浸透膜装置での回収率を減
少させる制御方法を実施した。処理液濃度(電導度)の
経時変化を、供給液のそれとともに第4図に示した。 その結果、供給液濃度が変化した場合でも、回収率を制
御することにより、短時間で処理液の濃度が一定の値に
戻ることがわかる。破線は、本発明によらなかった場合
の処理液の濃度変化である。 発明の効果 本発明の逆浸透法による放射性廃液の処理方法は、供給
液の性状が変化してもそれに追従して回収率を制御する
ことにより、常に一定範囲内の濃度の処理液を得ること
ができる。従って安全を確保しつつ経済的に有利な処理
を実施することができる。
Example 2 In the same three-stage type reverse osmosis membrane device as described above, the NaNO 3 concentration of the feed liquid (measured by conductivity) was increased during operation, and the second stage reverse osmosis membrane device was correspondingly increased. A control method was implemented to reduce the recovery rate at. The change with time of the concentration (conductivity) of the treatment liquid is shown in FIG. 4 together with that of the supply liquid. As a result, it can be seen that even if the supply liquid concentration changes, the concentration of the treatment liquid returns to a constant value in a short time by controlling the recovery rate. The broken line shows the change in the concentration of the treatment liquid when it is not according to the present invention. Effect of the Invention The method for treating radioactive waste liquid by the reverse osmosis method of the present invention always obtains a treatment liquid having a concentration within a certain range by controlling the recovery rate even if the property of the supply liquid changes. You can Therefore, it is possible to carry out economically advantageous processing while ensuring safety.

【図面の簡単な説明】 第1図は、本発明の処理方法を実施するための逆浸透装
置の基本的な構成の例を示すフローチャートである。 第2図AおよびBは、それぞれ2段式および3段式の逆
浸透装置の例を示す部分的なフローチャートである。 第3図は、本発明の方法の一実施例における廃液処理の
結果を示すグラフである。 第4図は、本発明の方法の他の実施例における効果を示
すグラフである。 P……高圧ポンプ R/O……逆浸透膜装置 CT,CT,CT……溶液センサー FT,FT……流量計 RC……回収率調節計 V……圧力調節弁
BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a flow chart showing an example of the basic configuration of a reverse osmosis device for carrying out the treatment method of the present invention. 2A and 2B are partial flow charts showing examples of two-stage and three-stage reverse osmosis devices, respectively. FIG. 3 is a graph showing the results of waste liquid treatment in one example of the method of the present invention. FIG. 4 is a graph showing the effect of another embodiment of the method of the present invention. P ... High-pressure pump R / O ... Reverse osmosis device CT f , CT p , CT b ... Solution sensor FT p , FT b ... Flow meter RC ... Recovery rate controller V ... Pressure control valve

───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭55−84586(JP,A) ─────────────────────────────────────────────────── --- Continuation of front page (56) References JP-A-55-84586 (JP, A)

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】放射性廃液を逆浸透膜装置に供給して供給
液を処理液および濃縮液に分離する処理方法において、
供給液のラインおよび処理液のラインに溶液の性状を測
定する手段を設けるとともに、処理液および濃縮液のラ
インに流量を測定する手段を設け、供給液性状、処理液
性状、処理液流量および濃縮液流量の信号を回収率調節
計に入力して 回収率=(処理液流量/供給液流量) を適切に定め回収率調節計からの出力信号により濃縮液
のラインの圧力調節弁の開度を調節して回収率を制御
し、供給液の性状が悪くなったときは回収率を低くし、
良くなったときは高めることにより、供給液の性状が変
化しても処理液の性状が所定の範囲内にあるようにした
ことを特徴とする逆浸透法を用いた放射性廃液の処理方
法。
1. A processing method for supplying a radioactive waste liquid to a reverse osmosis membrane device to separate the supplied liquid into a processing liquid and a concentrated liquid,
A means for measuring the properties of the solution is provided in the feed liquid line and the treatment liquid line, and a means for measuring the flow rate is provided in the treatment liquid and concentrate lines, and the feed liquid property, the treatment liquid property, the treatment liquid flow rate and the concentration By inputting the liquid flow rate signal to the recovery rate controller, the recovery rate = (process liquid flow rate / supply solution flow rate) is set appropriately and the output signal from the recovery rate controller determines the opening of the pressure control valve in the concentrate line. Adjust the recovery rate by adjusting, and if the quality of the supply liquid becomes poor, lower the recovery rate,
A method for treating radioactive waste liquid using the reverse osmosis method, which is characterized in that the property of the treatment liquid is within a predetermined range even if the property of the supply liquid is changed by raising it when it is improved.
【請求項2】溶液の性状として放射能濃度を測定して実
施する特許請求の範囲第1項の処理方法。
2. The treatment method according to claim 1, which is carried out by measuring a radioactivity concentration as a property of the solution.
【請求項3】溶液の性状として電導度を測定して実施す
る特許請求の範囲第1項の処理方法。
3. The treatment method according to claim 1, which is carried out by measuring electric conductivity as a property of the solution.
【請求項4】逆浸透膜装置を二段以上の多段に使用して
実施する特許請求の範囲第1項の処理方法。
4. The treatment method according to claim 1, wherein the reverse osmosis membrane device is used in multiple stages of two or more stages.
JP61197939A 1986-08-22 1986-08-22 Treatment method of radioactive waste liquid Expired - Lifetime JPH0664187B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61197939A JPH0664187B2 (en) 1986-08-22 1986-08-22 Treatment method of radioactive waste liquid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61197939A JPH0664187B2 (en) 1986-08-22 1986-08-22 Treatment method of radioactive waste liquid

Publications (2)

Publication Number Publication Date
JPS6353499A JPS6353499A (en) 1988-03-07
JPH0664187B2 true JPH0664187B2 (en) 1994-08-22

Family

ID=16382807

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61197939A Expired - Lifetime JPH0664187B2 (en) 1986-08-22 1986-08-22 Treatment method of radioactive waste liquid

Country Status (1)

Country Link
JP (1) JPH0664187B2 (en)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH01310703A (en) * 1988-06-09 1989-12-14 Japan Organo Co Ltd Method for controlling concentration in membrane separator
JPH0368426A (en) * 1989-08-08 1991-03-25 Kubota Corp Controlling method for concentrator
JPH0588693U (en) * 1992-05-19 1993-12-03 三菱重工業株式会社 Waste liquid boric acid processor
JP2005147788A (en) * 2003-11-13 2005-06-09 Inst Nuclear Energy Research Rocaec Boric acid purification and reutilization system, and method, using reverse osmosis separation method
CN102745775A (en) * 2007-10-29 2012-10-24 株式会社神钢环境舒立净 Water treatment method, water treatment apparatus, method for recovering purified water, and purified water recovering apparatus
JP5222526B2 (en) * 2007-10-29 2013-06-26 株式会社神鋼環境ソリューション Water treatment method and water treatment apparatus
JP5075597B2 (en) * 2007-11-30 2012-11-21 株式会社神鋼環境ソリューション Purified water recovery device and purified water recovery method
JP2009154070A (en) * 2007-12-26 2009-07-16 Kobelco Eco-Solutions Co Ltd Purified water recovering apparatus and method for recovering purified water
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
CN106448787B (en) * 2014-01-09 2018-10-02 清华大学 A kind of method and apparatus of Spent Radioactive water process

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5925633B2 (en) * 1978-09-20 1984-06-19 三菱重工業株式会社 How to treat wastewater

Also Published As

Publication number Publication date
JPS6353499A (en) 1988-03-07

Similar Documents

Publication Publication Date Title
JPH0664187B2 (en) Treatment method of radioactive waste liquid
CN103745759A (en) Method and device for processing radioactive wastewater
DE68908316T2 (en) Power inverter device with DC component suppression.
CA1300287C (en) Apparatus and process for feeding hypochlorite solution
ES8502882A1 (en) Separation system including a floatation tank having level control means
CN103936104A (en) Water purification system
CN105540894A (en) Reverse osmosis water purification machine system and control method thereof
CN203922809U (en) Water cleaning systems
DE3338728A1 (en) METHOD AND DEVICE FOR REGULATING A FLUID BEARING
DE1671884C3 (en) Method and device for regulating the electrolyte throughput through a seawater battery
JPH06277455A (en) Operation of ultrafiltration membrane module
KR20120049870A (en) Closed circuit desalination retrofit for improved performance of common reverse osmosis systems
DE202013100870U1 (en) Hydropower plant for generating electrical energy
JP2010099594A (en) Method for operating electric desalination apparatus
CH653822A5 (en) COOLING ARRANGEMENT AND METHOD FOR OPERATING THE ARRANGEMENT.
DE102019129348A1 (en) System for the treatment of water and procedures for it
DE2245501B2 (en) Process for regulating the water pressure in a working area open to the face in a shield tunneling construction process
JP3307140B2 (en) Reprocessing of spent nuclear fuel
JP2019217435A (en) Membrane separation unit
JPS61220788A (en) Method for controlling extremely pure water generator
CN211620198U (en) External sewage treatment system
JP4137231B2 (en) Method for controlling the operating pressure of a membrane separation process
CN211209617U (en) Frequency conversion control system
JPS62237988A (en) Method for treating waste water
CN208500614U (en) Reverse osmosis concentrated recovery processing system

Legal Events

Date Code Title Description
EXPY Cancellation because of completion of term