JPH11109092A - Processing method for radioactive material-containing waste liquid using reverse osmosis membrane - Google Patents

Processing method for radioactive material-containing waste liquid using reverse osmosis membrane

Info

Publication number
JPH11109092A
JPH11109092A JP26877997A JP26877997A JPH11109092A JP H11109092 A JPH11109092 A JP H11109092A JP 26877997 A JP26877997 A JP 26877997A JP 26877997 A JP26877997 A JP 26877997A JP H11109092 A JPH11109092 A JP H11109092A
Authority
JP
Japan
Prior art keywords
membrane
waste liquid
measured
radioactive material
concentration
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.)
Withdrawn
Application number
JP26877997A
Other languages
Japanese (ja)
Inventor
Kuniharu Wakuta
邦晴 涌田
Hiroshi Sagawa
佐川  寛
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP26877997A priority Critical patent/JPH11109092A/en
Publication of JPH11109092A publication Critical patent/JPH11109092A/en
Withdrawn legal-status Critical Current

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  • Separation Using Semi-Permeable Membranes (AREA)

Abstract

PROBLEM TO BE SOLVED: To facilitate the control of processing equipment by measuring the concentration of Na in waste liquid before and after passing a reverse osmosis membrane (RO membrane), and evaluating the degradation status of the RO membrane from the permeability of Na calculated from the measured value. SOLUTION: Raw water containing radioactive material is once received in a washing drain tank 1, and supplied to an RO membrane 3 by a high pressure pump 2 for waste liquid transport. Electric conductivity and Na concentration of the raw water is measured at a measurement position 7 upstream of the RO membrane 3, and electric conductivity and Na concentration of the processed water is measured at a downstream measurement position 8 and radioactivity is measured with a radiation monitor 6. Although in this example, the electric conductivity of the permeated water at the time of integral processing amount of 600 m<3> is below the discharge standard, radioactive material is detected in the radioactivity measurement, and Na permeability is 60% at this moment, and it is lower than initial performance. By this constitution, the degradation of processing performance of radioactive material in the RO membrane which can not be grasped in the conventional electric conductivity measurement can be easily detected, and the control of the processing equipment can be easily and smoothly performed.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は原子力施設における
洗浄排水などの放射性物質含有廃液を逆浸透膜を用いて
処理する方法に関し、さらに詳しくは使用中の逆浸透膜
の劣化状況の評価方法が改良された放射性物質含有廃液
の処理方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a waste liquid containing radioactive substances such as washing wastewater in a nuclear facility by using a reverse osmosis membrane, and more particularly, to an improved method for evaluating the state of degradation of a reverse osmosis membrane in use. The present invention relates to a method for treating a radioactive substance-containing waste liquid.

【0002】[0002]

【従来の技術】原子力施設(原子力発電プラント)にお
ける洗浄排水など放射性物質を含有する廃液の処理方法
の一つとして逆浸透膜( Reverse Osmosis:以下、RO
膜と略称する)を用いた処理が行われている。これらの
処理系統においては、運転中(使用期間中)の当該膜の
健全性(劣化状況)の評価は透過水(処理水)の電導度
により行われていた。すなわち、透過水の電導度を測定
し、その値がある基準値を上回った場合には膜損傷、経
年劣化等により原液がリークしているものと判断し、膜
交換を行っていた。
2. Description of the Related Art Reverse osmosis (hereinafter referred to as RO) is one of the methods for treating wastewater containing radioactive substances such as washing wastewater in nuclear facilities (nuclear power plants).
(Abbreviated as a film). In these treatment systems, the soundness (deterioration state) of the membrane during operation (during use) was evaluated based on the conductivity of permeated water (treated water). That is, the conductivity of the permeated water was measured, and when the value exceeded a certain reference value, it was determined that the stock solution was leaking due to membrane damage, aging, etc., and the membrane was replaced.

【0003】[0003]

【発明が解決しようとする課題】原子力発電プラントで
使用されているRO膜を用いた放射性物質含有廃液処理
設備の概略系統図の1例を図2に示す。図2の設備にお
いて、放射性物質を含有している廃液(洗浄排水)は洗
浄排水タンク1にいったん受け入れられ、廃液移送用高
圧ポンプ2によりRO膜3へ供給される。RO膜3を透
過した処理水は電導度計4にて連続自動測定され、電導
度が基準値以下であれば透過水タンク5へ排出される。
さらに、透過水タンク5へ排出された処理水は放射線モ
ニタ6にて放射能のチェックを受け、放出基準値以下で
あれば最終的に放流される。ここで放流可否を測定判断
するのは上述のとおり最終的には放射線モニタ6にて放
射能が基準値以上検出されるか否かであり、仮に電導度
計4にて基準値を下回った場合であっても放流できな
い、つまり放射能が検出される場合もあり得る。すなわ
ち、電導度管理によりRO膜が健全(使用継続可能)で
あると判断しても実際には電導度に対する寄与があまり
ない程度の放射性物質が透過し、最終的に放射線モニタ
6にて検出され放流不可となる場合がある。この場合、
当該RO膜の継続使用はできず、新膜への取り替えを行
う必要が生じる。
FIG. 2 shows an example of a schematic system diagram of a radioactive substance-containing waste liquid treatment facility using an RO membrane used in a nuclear power plant. In the equipment shown in FIG. 2, a waste liquid (washing wastewater) containing a radioactive substance is once received in a washing wastewater tank 1 and supplied to the RO membrane 3 by a wastewater transfer high-pressure pump 2. The treated water that has passed through the RO membrane 3 is continuously and automatically measured by a conductivity meter 4, and is discharged to a permeated water tank 5 when the conductivity is equal to or less than a reference value.
Further, the treated water discharged to the permeated water tank 5 is checked for radioactivity by the radiation monitor 6, and is finally discharged if it is below the release reference value. Here, the determination of whether or not discharge is possible is based on whether or not the radioactivity is finally detected by the radiation monitor 6 at or above the reference value, as described above. However, there is a possibility that the radioactivity cannot be released, that is, radioactivity is detected. That is, even if the RO film is determined to be healthy (continuous use) by the conductivity management, a radioactive substance that does not contribute much to the conductivity actually penetrates, and is finally detected by the radiation monitor 6. Release may not be possible. in this case,
The RO film cannot be used continuously, and it is necessary to replace it with a new film.

【0004】このように、放射性廃液を取り扱う処理系
統においてRO膜を使用する場合、一般産業界等にて用
いられている電導度による膜健全性確認方法では実際の
膜状態(劣化、損傷等)を正確に把握できない場合があ
る。本発明はこのような従来技術の実状に鑑み、放射性
物質含有廃液の処理設備におけるRO膜の性能劣化状態
を正確に評価することができ、前記処理設備の管理が容
易な、放射性物質含有廃液の処理方法を提供することを
目的とする。
As described above, when an RO membrane is used in a treatment system for handling radioactive waste liquid, the actual state of the membrane (deterioration, damage, etc.) is determined by the method of confirming the integrity of the membrane based on electrical conductivity used in the general industry. May not be accurately understood. The present invention, in view of the state of the prior art, can accurately evaluate the performance deterioration state of an RO membrane in a treatment facility for radioactive substance-containing waste liquid, and can easily manage the treatment facility. It is an object to provide a processing method.

【0005】[0005]

【課題を解決するための手段】本発明者らは前記課題を
解決するため、放射性物質を含有する廃液のRO膜によ
る処理プロセスについて種々検討の結果、廃液中に含ま
れるNaの透過率を測定することにより膜劣化状態(経
時変化)を正確に把握できることを見出した。すなわ
ち、本発明は逆浸透膜を用いて放射性物質含有廃液を処
理する方法において、逆浸透膜を通過する前後の廃液中
のNa濃度を測定し、その測定値から算出されるNa透
過率により逆浸透膜の劣化状況を評価することを特徴と
する放射性物質含有廃液の処理方法である。
Means for Solving the Problems In order to solve the above-mentioned problems, the present inventors have conducted various studies on a process for treating a waste liquid containing a radioactive substance by an RO membrane, and measured the transmittance of Na contained in the waste liquid. By doing so, it was found that the film deterioration state (change with time) can be accurately grasped. That is, the present invention relates to a method for treating a radioactive substance-containing waste liquid using a reverse osmosis membrane, wherein the Na concentration in the waste liquid before and after passing through the reverse osmosis membrane is measured, and the Na concentration is calculated based on the Na transmittance calculated from the measured value. This is a method for treating a radioactive substance-containing waste liquid, wherein the state of deterioration of the permeable membrane is evaluated.

【0006】本発明の方法においては、放射性物質含有
廃液中に含まれる放射性元素である 60Co、 137Cs等
の金属イオンはNaイオンと類似した膜透過性を示すこ
とに着目し、放射性物質含有廃液中に共存するNaの透
過率を測定することによって逆浸透膜の劣化状況を評価
するようにしている。具体的にはRO膜の前後におい
て、液中のNa濃度を測定し、Naの透過率を算出す
る。この透過率の変化の状況からRO膜の損傷又は劣化
の状況を評価することができる。
[0006] In the method of the present invention, the radioactive material containing
It is a radioactive element contained in waste liquid 60Co,137Cs, etc.
Metal ions show similar membrane permeability to Na ions.
And the permeability of Na coexisting in the waste liquid containing radioactive substances.
Evaluate reverse osmosis membrane degradation by measuring excess rate
I am trying to do it. Specifically, before and after the RO film
To measure the Na concentration in the solution and calculate the Na transmittance.
You. From the situation of this change in transmittance, the RO film is damaged or deteriorated.
Can be evaluated.

【0007】通常、原子力発電プラントにおいてRO膜
で処理される被処理液は洗浄排水(洗濯排水)が主体で
あり、人の汗成分であるNaClが含まれているので、
このNa濃度を測定すればよい。なお、被処理液中にN
aが含まれていない場合には適宜NaCl等を添加し、
原水中と処理水中のNa濃度を測定し、対比すればよ
い。
Usually, the liquid to be treated by the RO membrane in a nuclear power plant mainly consists of washing wastewater (washing wastewater) and contains NaCl which is a human sweat component.
What is necessary is just to measure this Na concentration. It should be noted that N
When a is not contained, NaCl or the like is appropriately added,
The concentrations of Na in the raw water and the treated water may be measured and compared.

【0008】RO膜の性能は一般的に脱塩率(原水中の
塩濃度に対する透過水中塩濃度の割合)として表され、
膜製作後の初期性能の確認(検査)についても塩(=N
aCl)の透過率を測定することによって行われてい
る。したがって、実際に使用中のRO膜の性能評価もN
aの透過率を測定して行うことにより、膜製作時点〜膜
使用期間中の劣化状況を、同一手段により一貫して管
理、把握することが可能となる。また、単なる電導度管
理では検知できない膜劣化を確認することができる。
The performance of an RO membrane is generally expressed as a desalination rate (a ratio of a salt concentration in a permeated water to a salt concentration in a raw water).
Confirmation (inspection) of the initial performance after film production is also made with salt (= N
aCl) is measured. Therefore, the performance evaluation of the RO film actually used is also N
By measuring and performing the transmittance of “a”, it is possible to consistently manage and grasp the state of deterioration from the time of film production to the time of use of the film by the same means. In addition, it is possible to confirm film deterioration that cannot be detected by simple conductivity management.

【0009】なお、本発明の方法の実施に際しては、図
2に示す従来設備構成品のうち電導度計4の代わりにN
a計を設置するだけで、従来設備からの改造範囲を最小
限にして、RO膜の劣化状況を経時的に確認することが
できる。
In carrying out the method of the present invention, the electric conductivity meter 4 is replaced with N in the conventional equipment shown in FIG.
Only by installing the a meter, it is possible to check the deterioration state of the RO film over time while minimizing the remodeling range from the conventional equipment.

【0010】[0010]

【実施例】以下実施例により本発明の方法をさらに具体
的に説明する。 (実施例1)国内の原子力発電プラントの一つで洗浄排
水処理系に使用されているRO膜設備により廃液処理試
験を行った。その概略系統図を図1に示す。試験操作
は、放射性物質を含む原水をいったん洗浄排水タンク1
に受け入れ、廃液移送用高圧ポンプ2にてRO膜3へ供
給した。RO膜3の前流側の測定位置7で原水(被処理
液)の電導度及びNa濃度を測定し、RO膜3の後流側
の測定位置8で処理水の電導度及びNa濃度を測定する
とともに、放射線モニタ7にて放射能の測定を行い、被
処理液の積算処理量と電導度、Na透過率及び放射能の
関係を確認した。結果を表1に示す。
EXAMPLES The method of the present invention will be described more specifically with reference to the following examples. (Example 1) A waste liquid treatment test was performed using an RO membrane facility used in a washing and drainage treatment system at one of domestic nuclear power plants. The schematic system diagram is shown in FIG. The test operation involves cleaning the wastewater once containing radioactive
And supplied to the RO membrane 3 by the high-pressure pump 2 for transferring waste liquid. The conductivity and Na concentration of the raw water (liquid to be treated) are measured at the measurement position 7 on the upstream side of the RO film 3, and the conductivity and Na concentration of the treated water are measured at the measurement position 8 on the downstream side of the RO film 3. At the same time, the radioactivity was measured by the radiation monitor 7, and the relationship among the integrated processing amount of the liquid to be processed and the conductivity, Na transmittance, and radioactivity was confirmed. Table 1 shows the results.

【0011】[0011]

【表1】 [Table 1]

【0012】表1の結果からわかるとおり、原水の積算
処理量が600m3 の時点において透過水の電導度は4
6.3μS/cmであり、下流の透過水タンク5への放
出基準である450μS/cmを下回っているため、処
理自体は継続して行われることとなるが、最終的な放流
前の放射能チェックでは放射性物質が検出されて放流不
可となっている。一方、このときのNa透過率は60%
であり、明らかに初期性能(1%)に比べ低下してい
る。以上より、従来の電導度管理のみでは確認できない
ような膜劣化をNaの測定により可能となることが分か
る。
As can be seen from the results in Table 1, the conductivity of the permeated water is 4 at the time when the integrated treatment amount of the raw water is 600 m 3.
6.3 μS / cm, which is less than 450 μS / cm, which is the standard for release to the permeated water tank 5 downstream, so that the processing itself is continuously performed. In the check, radioactive substances were detected and release was impossible. On the other hand, the Na transmittance at this time is 60%.
Which is clearly lower than the initial performance (1%). From the above, it can be seen that film deterioration that cannot be confirmed only by the conventional conductivity management can be performed by measuring Na.

【0013】[0013]

【発明の効果】本発明の方法によれば、従来の電導度測
定による管理では把握できなかった、RO膜の放射性物
質の処理性能の劣化を容易に検出することができ、放射
性物質含有廃液の処理設備の管理を容易かつ円滑に行う
ことができる。本発明の方法は特に原子力発電プラント
における洗浄排水の処理に好適である。
According to the method of the present invention, it is possible to easily detect the deterioration of the processing performance of radioactive substances of the RO film, which could not be grasped by the conventional management by conductivity measurement, and to easily detect the radioactive substance-containing waste liquid. Management of processing equipment can be performed easily and smoothly. The method of the present invention is particularly suitable for treating cleaning wastewater in a nuclear power plant.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明の実施例に係る放射性物質含有廃液の処
理設備の概略系統図
FIG. 1 is a schematic system diagram of a facility for treating radioactive substance-containing waste liquid according to an embodiment of the present invention.

【図2】従来の放射性物質含有廃液処理設備の概略系統
FIG. 2 is a schematic system diagram of a conventional radioactive substance-containing waste liquid treatment facility.

───────────────────────────────────────────────────── フロントページの続き (51)Int.Cl.6 識別記号 FI C02F 1/44 ZAB C02F 1/44 ZABK ──────────────────────────────────────────────────の Continued on the front page (51) Int.Cl. 6 Identification code FI C02F 1/44 ZAB C02F 1/44 ZABK

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 逆浸透膜を用いて放射性物質含有廃液を
処理する方法において、逆浸透膜を通過する前後の廃液
中のNa濃度を測定し、その測定値から算出されるNa
透過率により逆浸透膜の劣化状況を評価することを特徴
とする放射性物質含有廃液の処理方法。
In a method of treating a radioactive substance-containing waste liquid using a reverse osmosis membrane, the Na concentration in the waste liquid before and after passing through the reverse osmosis membrane is measured, and the Na concentration calculated from the measured value is measured.
A method for treating a radioactive substance-containing waste liquid, wherein the degradation state of the reverse osmosis membrane is evaluated based on transmittance.
JP26877997A 1997-10-01 1997-10-01 Processing method for radioactive material-containing waste liquid using reverse osmosis membrane Withdrawn JPH11109092A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP26877997A JPH11109092A (en) 1997-10-01 1997-10-01 Processing method for radioactive material-containing waste liquid using reverse osmosis membrane

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP26877997A JPH11109092A (en) 1997-10-01 1997-10-01 Processing method for radioactive material-containing waste liquid using reverse osmosis membrane

Publications (1)

Publication Number Publication Date
JPH11109092A true JPH11109092A (en) 1999-04-23

Family

ID=17463179

Family Applications (1)

Application Number Title Priority Date Filing Date
JP26877997A Withdrawn JPH11109092A (en) 1997-10-01 1997-10-01 Processing method for radioactive material-containing waste liquid using reverse osmosis membrane

Country Status (1)

Country Link
JP (1) JPH11109092A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2004507340A (en) * 2000-06-02 2004-03-11 ビバンデイ・ユニベルサル Nanofiltration module or reverse osmosis module, or method of checking the system integrity of such a module
JP2006231289A (en) * 2005-02-28 2006-09-07 Toyobo Co Ltd Method for detecting leak in hollow fiber membrane module and leak detection apparatus
JP2010194541A (en) * 2010-05-14 2010-09-09 Chubu Electric Power Co Inc Waste water treatment system
CN105738189A (en) * 2016-04-01 2016-07-06 北京辰安科技股份有限公司 Concentration treatment device and method for radioactivity analysis and detection

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2004507340A (en) * 2000-06-02 2004-03-11 ビバンデイ・ユニベルサル Nanofiltration module or reverse osmosis module, or method of checking the system integrity of such a module
JP2006231289A (en) * 2005-02-28 2006-09-07 Toyobo Co Ltd Method for detecting leak in hollow fiber membrane module and leak detection apparatus
JP4538732B2 (en) * 2005-02-28 2010-09-08 東洋紡績株式会社 Hollow fiber membrane module leak detection method and leak detection device
JP2010194541A (en) * 2010-05-14 2010-09-09 Chubu Electric Power Co Inc Waste water treatment system
CN105738189A (en) * 2016-04-01 2016-07-06 北京辰安科技股份有限公司 Concentration treatment device and method for radioactivity analysis and detection

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