JP2006064561A - Execution method of activated concrete cutting work - Google Patents

Execution method of activated concrete cutting work Download PDF

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JP2006064561A
JP2006064561A JP2004248146A JP2004248146A JP2006064561A JP 2006064561 A JP2006064561 A JP 2006064561A JP 2004248146 A JP2004248146 A JP 2004248146A JP 2004248146 A JP2004248146 A JP 2004248146A JP 2006064561 A JP2006064561 A JP 2006064561A
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cutting
filtrate
activated concrete
waste liquid
solid
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Yuichi Tsukahara
裕一 塚原
Morishige Watanabe
守成 渡辺
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Shimizu Construction Co Ltd
Shimizu Corp
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Shimizu Construction Co Ltd
Shimizu Corp
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Abstract

<P>PROBLEM TO BE SOLVED: To provide an execution method of an activated concrete cutting work capable of reducing the amount of a radiation discharged into the sea or the like as the whole work, and having less effect on the general public. <P>SOLUTION: This execution method of the activated concrete cutting work has a wet cutting process S1 for cutting the activated concrete, while injecting cooling water into a cutting part; a solid/liquid separation treatment process S2 for separating cutting waste liquid 1 including activated concrete sludge generated at the wet cutting process S1 time into a solid portion 3 including a radioactive material and a filtrate 2 wherein the radioactive material is dissolved; and a neutralization treatment process S3 for neutralizing the filtrate 2 into a neutralized filtrate 4. In the method, the filtrate 2 generated in the solid/liquid separation treatment process S2 is used as the cooling water at the wet cutting process S1 time. <P>COPYRIGHT: (C)2006,JPO&NCIPI

Description

本発明は、放射化されているコンクリートを切断するとともに、放射化されたコンクリートスラッジを含む切断廃液から放射性物質を除去する放射化コンクリート切断工事の施工方法に関する。   The present invention relates to a method for constructing activated concrete cutting work for cutting activated concrete and removing radioactive substances from a cutting waste liquid containing activated concrete sludge.

コンクリート構造物を解体する際、ワイヤーソー切断工法が用いられることが多い。ワイヤーソー切断工法を用いた解体作業では、切断中に冷却材として水を使用することから、コンクリートスラッジと水とが混ざり合ったスラリー状の切断廃液が発生する。一般のコンクリート構造物の解体作業においては、切断廃液は浮遊物質（ＳＳ）や水素イオン濃度（ｐＨ）等を一般環境放流基準に合致した性状に処理されてから河川や海洋に放流される。   When demolishing a concrete structure, a wire saw cutting method is often used. In the dismantling work using the wire saw cutting method, water is used as a coolant during cutting, so that a slurry-like cutting waste liquid in which concrete sludge and water are mixed is generated. In the dismantling work of a general concrete structure, the cutting waste liquid is discharged into rivers and oceans after processing suspended matter (SS), hydrogen ion concentration (pH) and the like in accordance with general environmental discharge standards.

原子力発電所などの放射性物質を扱う施設のコンクリート構造物を解体する場合、コンクリートは放射化されているため、切断作業で発生した切断廃液中には放射性物質が含有されている。切断廃液中の放射性物質には、多量に存在する粒子状の核種（粒子状核種）と、水に溶解している核種（溶解性核種）とがある。したがって、切断作業で発生した切断廃液は、放射性物質除去後に所定の処理をしてから放流しなければならない。   When dismantling a concrete structure of a facility that handles radioactive substances such as nuclear power plants, since the concrete has been activated, radioactive waste is contained in the cutting waste liquid generated in the cutting operation. The radioactive substances in the cutting waste liquid include particulate nuclides (particulate nuclides) present in large quantities and nuclides dissolved in water (soluble nuclides). Therefore, the cutting waste liquid generated in the cutting operation must be discharged after performing a predetermined treatment after removing the radioactive substance.

一方、通常、原子力施設には、放射性の廃液を処理する設備が設置されている（例えば、特許文献１参照。）。これによって、廃液中の放射性物質を除去することができるが、コンクリートの切断廃液は、施設運転中に発生する廃液と性状が大きく異なるとともに、施設運転中に発生する廃液に比べて大量に発生することから、前記設備では切断廃液を処理することが困難である。   On the other hand, facilities for treating radioactive liquid waste are usually installed in nuclear facilities (see, for example, Patent Document 1). This can remove radioactive substances in the waste liquid, but the waste liquid from cutting concrete is significantly different from the waste liquid generated during facility operation and is produced in a larger amount than the waste liquid generated during facility operation. Therefore, it is difficult to treat the cutting waste liquid with the above equipment.

従来、放射化コンクリートを切断した際に発生する切断廃液を処理する方法が提案されている。この方法は、まずフィルタープレスを用いて切断廃液の固形分を除去して濾液とする固液分離処理工程（脱水工程）を行い、その後に固液分離処理により固形分が除去された濾液を中和する中和処理工程を行う方法である（例えば、特許文献２参照。）。この方法によれば、廃液の固形分を除去して濾液とする固液分離処理後に、この濾液のｐＨを下げる中和処理を行うので、切断廃液中の溶解していない放射性物質（粒子状核種）を固形分として取り出すことができる。そして、放射性物質が十分に除去された濾液を中和処理することによって一般環境に悪影響を与えない性状にすることができる。
特開平９−２３００９５号公報 特開２００２−３３３４９６号公報 Conventionally, a method has been proposed for treating cutting waste liquid generated when activated concrete is cut. In this method, first, a solid-liquid separation process (dehydration process) is performed by removing the solid content of the cutting waste liquid using a filter press to obtain a filtrate, and then the filtrate from which the solid content has been removed by the solid-liquid separation process. This is a method of performing a neutralizing treatment step (for example, see Patent Document 2). According to this method, after the solid-liquid separation process to remove the solid content of the waste liquid to obtain a filtrate, the neutralization process for lowering the pH of the filtrate is performed, so that the radioactive substance (particulate nuclides) in the cutting waste liquid is not dissolved. ) As solids. And it can be made the property which does not have a bad influence on a general environment by neutralizing the filtrate from which the radioactive substance was fully removed.
Japanese Patent Laid-Open No. 9-230095 JP 2002-333696 A

しかしながら、上記した従来の処理方法で切断廃液を処理した場合、切断廃液中に多量に存在する粒子状核種については９９．９９％以上除去することができるものの、水に溶解した溶解性核種については１５％程度しか除去することができずに処理後の濾液中に残存する。従来の処理方法を備えた放射化コンクリート切断工事の施工方法では、海洋などに放流される濾液の放射能濃度は微少であっても、工事全体で切断廃液が多量に生じる場合、海洋などに放流される放射能の全体量は多くなるという問題が存在する。したがって、冷却水を多量に用いる大規模工事の場合には、海洋などに放流される放射能の全体量が多くなり、一般公衆に影響を及ぼす虞が生じる。   However, when the cutting waste liquid is processed by the above-described conventional processing method, particulate nuclides present in a large amount in the cutting waste liquid can be removed by 99.99% or more, but the soluble nuclides dissolved in water Only about 15% can be removed and it remains in the filtrate after the treatment. In the construction method of activated concrete cutting work with the conventional treatment method, even if the radioactive concentration of the filtrate discharged to the ocean etc. is very small, if a large amount of cutting waste liquid is generated throughout the construction, it will be released to the ocean etc. There is a problem that the total amount of radioactivity produced increases. Therefore, in the case of large-scale construction using a large amount of cooling water, the total amount of radioactivity released to the ocean or the like increases, which may affect the general public.

本発明は、上記した従来の問題が考慮されたものであり、海洋などに放流される放射能量を工事全体として低減し、一般公衆への影響を低減することができる放射化コンクリート切断工事の施工方法を提供することを目的としている。   The present invention takes the above-mentioned conventional problems into consideration, and reduces the amount of radioactivity released to the ocean as a whole construction, and the construction of activated concrete cutting work that can reduce the impact on the general public It aims to provide a method.

請求項１記載の発明は、切断部分に冷却水を注水しつつ放射化コンクリートを切断する湿式切断工程と、湿式切断工程時に生じる放射化コンクリートスラッジを含む切断廃液を、放射性物質を含有する固形分と放射性物質が溶解された濾液とに分離させる固液分離処理工程と、該濾液を中和して中和濾液にする中和処理工程とを備える放射化コンクリート切断工事の施工方法において、固液分離処理工程によって生じた前記濾液を、再び湿式切断工程時の冷却水として用いることを特徴としている。   The invention described in claim 1 includes a wet cutting step of cutting activated concrete while injecting cooling water into a cut portion, and a cutting waste liquid containing activated concrete sludge generated during the wet cutting step, and a solid content containing a radioactive substance. And a solid-liquid separation treatment step for separating the radioactive substance into a filtrate, and a neutralization treatment step for neutralizing the filtrate into a neutralized filtrate. The filtrate produced in the separation treatment step is used again as cooling water in the wet cutting step.

このような特徴により、濾液を冷却水として再利用することで、放射性物質が溶解された濾液は、一定量の放射性物質が溶解されて其れ以上溶解しなくなる状態（飽和状態）となり、飽和された濾液を冷却水として用いて湿式切断工程を行っても、濾液には放射性物質が溶解しなくなる。また、濾液を冷却水として再利用するため、中和されて最終的に放流されることになる中和濾液は、放射化コンクリート切断工事全体として少量となる。   Due to these characteristics, by reusing the filtrate as cooling water, the filtrate in which the radioactive substance is dissolved is in a state (saturated state) in which a certain amount of radioactive substance is dissolved and no longer dissolves (saturated state). Even if the wet cutting process is performed using the filtrate as cooling water, the radioactive substance is not dissolved in the filtrate. Further, since the filtrate is reused as cooling water, the neutralized filtrate that is neutralized and finally discharged becomes a small amount as a whole of the activated concrete cutting work.

本発明に係る放射化コンクリート切断工事の施工方法によれば、濾液を冷却水として再利用することで、放射性物質が溶解された濾液は、飽和状態となって湿式切断工程時に放射性物質が溶解しなくなるとともに、中和されて最終的には放流される中和濾液は、放射化コンクリート切断工事全体として少量となるため、濾液（中和濾液）の放射能濃度は増加するが、放流される放射能の全体量を減少させることができる。これによって、放射化コンクリート切断工事に伴う一般公衆への影響を低減することができる。   According to the method for cutting activated concrete according to the present invention, by reusing the filtrate as cooling water, the filtrate in which the radioactive material is dissolved becomes saturated and the radioactive material is dissolved in the wet cutting process. The neutralized filtrate that is neutralized and eventually discharged becomes a small amount of the activated concrete cutting work as a whole, so the radioactive concentration of the filtrate (neutralized filtrate) increases, but the discharged radiation The total amount of performance can be reduced. As a result, it is possible to reduce the influence on the general public due to the activation concrete cutting work.

以下、本発明に係る放射化コンクリート切断工事の施工方法の実施の形態について、図面に基いて説明する。図１は本発明の廃液処理方法の一実施形態を示すフローチャート図、図２は脱水処理で用いるフィルタープレス装置の概略図、図３は中和処理で用いる中和装置の構成図である。   Hereinafter, an embodiment of a construction method of activation concrete cutting work according to the present invention will be described with reference to the drawings. FIG. 1 is a flowchart showing an embodiment of the waste liquid treatment method of the present invention, FIG. 2 is a schematic view of a filter press apparatus used in dehydration treatment, and FIG. 3 is a block diagram of a neutralization apparatus used in neutralization treatment.

図１に示すように、放射化コンクリート切断工事の施工方法は、切断部分に冷却水を注水しつつ放射化コンクリートを切断する湿式切断工程Ｓ１と、湿式切断工程Ｓ１時に生じる放射化コンクリートスラッジを含む切断廃液１を、放射性物質を含有する固形分３と放射性物質が溶解された濾液２とに分離させる固液分離処理（脱水処理）工程Ｓ２と、濾液２を中和して中和濾液４にする中和処理工程Ｓ３とを有している。   As shown in FIG. 1, the activation concrete cutting construction method includes a wet cutting step S1 for cutting the activated concrete while injecting cooling water into the cut portion, and an activated concrete sludge generated during the wet cutting step S1. A solid-liquid separation process (dehydration process) step S2 for separating the cutting waste liquid 1 into a solid content 3 containing a radioactive substance and a filtrate 2 in which the radioactive substance is dissolved, and neutralizing the filtrate 2 into a neutralized filtrate 4 And neutralizing treatment step S3.

先ず始めに、湿式切断工程Ｓ１では、一般的に知られているワイヤーソー切断工法によって放射化コンクリートを切断する。切断部分に最初に注水される冷却水は清水５であり、この清水５と切断時に発生するコンクリートスラッジとが混合されてスラリー状の切断廃液１が生成される。切断時に発生するコンクリートスラッジには放射性物質が含まれており、このコンクリートスラッジを含む切断廃液１は、放射性物質が含まれているとともに、固形分濃度が高く、セメントに含まれる水酸化カルシウム溶解の影響から高ｐＨである。   First, in the wet cutting step S1, the activated concrete is cut by a generally known wire saw cutting method. The cooling water initially poured into the cut portion is fresh water 5, and the clean water 5 and concrete sludge generated during cutting are mixed to produce slurry-like cutting waste liquid 1. The concrete sludge generated at the time of cutting contains a radioactive substance. The cutting waste liquid 1 containing this concrete sludge contains a radioactive substance, has a high solid content, and dissolves calcium hydroxide contained in cement. High pH due to influence.

次いで、固液分離処理工程Ｓ２では、切断廃液１をフィルタープレス装置１０（図２参照）によって脱水処理し、固形分３と濾液２とに分離する。フィルタープレス装置１０は、図２に示すように、締込板１１と、締込板１１に対向する位置に設けられている受板１２と、締込板１１と受板１２との間に設けられた複数の濾過板１３とを有している。締込板１１は受板１２に対して進退可能に設けられている。濾過板１３どうしの間には濾室１４が形成されるとともに、濾過板１３のそれぞれの中央を貫通するように切断廃液１を通過させる流路１５が設けられている。また、濾過板１３どうしは連結部材１６によって連結されている。   Next, in the solid-liquid separation processing step S <b> 2, the cutting waste liquid 1 is dehydrated by the filter press device 10 (see FIG. 2) and separated into the solid content 3 and the filtrate 2. As shown in FIG. 2, the filter press device 10 is provided between the clamping plate 11, the receiving plate 12 provided at a position facing the clamping plate 11, and the clamping plate 11 and the receiving plate 12. A plurality of filter plates 13. The fastening plate 11 is provided so as to be able to advance and retreat with respect to the receiving plate 12. A filter chamber 14 is formed between the filter plates 13, and a flow path 15 through which the cutting waste liquid 1 passes is provided so as to pass through the respective centers of the filter plates 13. Further, the filter plates 13 are connected by a connecting member 16.

フィルタープレス装置１０を用いて切断廃液１を固形分３と水分２とに分離するには、図２（ａ）に示すように、締込板１１と受板１２とを接近させ、複数の濾過板１３どうしを締め込みつつ、流路１５を介して濾室１４に切断廃液１を圧送する。
すると、切断廃液１中に含まれているコンクリートスラッジは固形分３として濾布に捕集される。一方、切断廃液１の水分は、濾液２として濾室１４外に排出される。こうして、切断廃液１は固形分３と濾液２とに分離される。濾室１４内の固形分３は、図２（ｂ）に示すように、締込板１１と受板１２とを離間して濾室１４を開放することにより排出される。この際、固形分３は容易にハンドリング可能である。 In order to separate the cutting waste liquid 1 into the solid content 3 and the moisture 2 using the filter press device 10, as shown in FIG. 2 (a), the fastening plate 11 and the receiving plate 12 are brought close to each other, and a plurality of filtrations are performed. While tightening the plates 13, the cutting waste liquid 1 is pumped to the filter chamber 14 through the flow path 15.
Then, the concrete sludge contained in the cutting waste liquid 1 is collected on the filter cloth as the solid content 3. On the other hand, the moisture of the cutting waste liquid 1 is discharged out of the filter chamber 14 as the filtrate 2. Thus, the cutting waste liquid 1 is separated into the solid content 3 and the filtrate 2. As shown in FIG. 2B, the solid content 3 in the filter chamber 14 is discharged by separating the fastening plate 11 and the receiving plate 12 and opening the filter chamber 14. At this time, the solid content 3 can be easily handled.

切断廃液１中に含まれている放射性物質のうち粒子状核種は、フィルタープレス装置１０を用いて分離された固形分３に含まれているため、濾液２中には、水に溶解した放射性物質（溶解性核種）のみが残存する。   Among the radioactive substances contained in the cutting waste liquid 1, the particulate nuclides are contained in the solid content 3 separated using the filter press device 10, and therefore the radioactive substance dissolved in water is contained in the filtrate 2. Only (soluble nuclides) remain.

次いで、上記した固液分離処理工程Ｓ２によって生じた濾液２を冷却水として用いて、上述した湿式切断工程Ｓ１を行う。具体的には、濾室１４外に排出された濾液２を切断部分に導いて、切断部分に濾液２を注水しつつ引き続き放射化コンクリートを切断する。このとき、放射化コンクリートへの染込み等による喪失量を補充すべく、切断部分に注水する濾液２に少量の清水を追加する。無論、喪失量が微少な場合は清水を追加する必要はない。   Next, the above-described wet cutting step S1 is performed using the filtrate 2 generated in the above-described solid-liquid separation treatment step S2 as cooling water. Specifically, the filtrate 2 discharged to the outside of the filter chamber 14 is guided to the cut portion, and the activated concrete is continuously cut while pouring the filtrate 2 into the cut portion. At this time, a small amount of fresh water is added to the filtrate 2 poured into the cut portion in order to supplement the loss due to the soaking into the activated concrete. Of course, it is not necessary to add fresh water if the amount of loss is very small.

次いで、冷却水として濾液２を用いた湿式切断工程Ｓ１によって発生した切断廃液１をフィルタープレス装置１０によって固形分３と濾液２とに分離する固液分離処理工程Ｓ２を行う。
このように、上記した工程を繰り返し行い、濾液２を再利用して放射化コンクリートを切断する。このとき、濾液２の再利用を繰り返すことで、溶解性核種を含有する濾液２は飽和状態となる。 Next, a solid-liquid separation processing step S2 is performed in which the cutting waste liquid 1 generated in the wet cutting step S1 using the filtrate 2 as cooling water is separated into the solid content 3 and the filtrate 2 by the filter press device 10.
Thus, the above-described steps are repeated, and the activated concrete is cut by reusing the filtrate 2. At this time, by repeating the reuse of the filtrate 2, the filtrate 2 containing the soluble nuclide becomes saturated.

ここで、溶解性核種を含有する濾液２は飽和状態となることを確認することができる試験データについて説明する。図４は例えば溶解性核種Ｃ−１４（炭素１４）を含有する切断廃液及び濾液の固形分濃度と放射能濃度との関係の一例を表すグラフである。図４に示すように、固液分離処理（脱水処理）工程Ｓ２前の切断廃液は、固形分濃度が上昇することで放射能濃度も上昇するが、各固形分濃度の切断廃液について固液分離処理工程Ｓ２を行うと、分離された濾液の放射能濃度はほとんど変化していない。この試験データにより、一定量の放射性物質が溶解すると溶解性核種起因の物質（炭酸塩や炭酸ガス等）が水に溶解しきれなくなって飽和状態となり、溶解されない放射性物質は粒子状核種として固形分と一緒に取り除かれたと考察される。したがって、飽和状態の濾液２を冷却水として用いると、飽和状態の濾液２に放射性物質が溶解することはない。   Here, the test data which can confirm that the filtrate 2 containing a soluble nuclide will be in a saturated state will be described. FIG. 4 is a graph showing an example of the relationship between the solid content concentration and the radioactivity concentration of the cutting waste liquid containing the soluble nuclide C-14 (carbon 14) and the filtrate. As shown in FIG. 4, the cutting waste liquid before the solid-liquid separation (dehydration) step S2 increases the radioactivity concentration as the solid concentration increases, but the solid-liquid separation is performed on the cutting waste liquid of each solid concentration. When processing step S2 is performed, the radioactivity concentration of the separated filtrate is hardly changed. According to this test data, when a certain amount of radioactive material dissolves, the soluble nuclide-derived substances (carbonates, carbon dioxide, etc.) cannot be completely dissolved in water and become saturated. Considered to have been removed. Therefore, when the saturated filtrate 2 is used as cooling water, the radioactive substance is not dissolved in the saturated filtrate 2.

次いで、放射化コンクリートを切断し終えた後、中和処理工程Ｓ３を行う。中和処理工程Ｓ３では、フィルタープレス装置１０を用いた固液分離処理工程Ｓ２によって生成された濾液２を、図３に示すような中和装置２０によって中和処理する。具体的には、セメントに含まれる水酸化カルシウム溶出の影響から高ｐＨとなっている濾液２を炭酸ガスを用いて中和する。中和装置２０は、ラインミキサー２１と、ミキサー２１に濾液２を送るポンプ２２と、ミキサー２１に炭酸ガスを圧送する炭酸ガス供給装置２３とを備えている。本実施形態において、炭酸ガス供給装置２３は炭酸ガスボンベである。ミキサー２１では、濾液２と多量の炭酸ガスと混合することにより、濾液２を中和する。   Next, after the activated concrete has been cut, a neutralization treatment step S3 is performed. In the neutralization treatment step S3, the filtrate 2 produced by the solid-liquid separation treatment step S2 using the filter press device 10 is neutralized by a neutralization device 20 as shown in FIG. Specifically, the filtrate 2 having a high pH due to the influence of calcium hydroxide elution contained in the cement is neutralized using carbon dioxide gas. The neutralization device 20 includes a line mixer 21, a pump 22 that sends the filtrate 2 to the mixer 21, and a carbon dioxide supply device 23 that pumps carbon dioxide to the mixer 21. In the present embodiment, the carbon dioxide supply device 23 is a carbon dioxide cylinder. In the mixer 21, the filtrate 2 is neutralized by mixing the filtrate 2 and a large amount of carbon dioxide gas.

濾液２を炭酸ガスを用いて中和することにより、ｐＨが一般環境へ悪影響を及ぼさない程度（海洋放流基準値ｐＨ５．０〜９．０の範囲内）の中和濾液４となる。また、炭酸ガスを用いた通常の中和処理では、濾液２中の溶解カルシウムが炭酸ガスと反応して炭酸カルシウム沈殿を生成して浮遊物質を増加させるが、本実施形態のように、濾液２と多量（所定量以上）の炭酸ガスとをラインミキサー２１で強制混合して反応させることにより、炭酸カルシウムを重炭酸カルシウムとして再溶解させ、浮遊物質を１００ｍｇ／リットル程度まで低減することができ、一般環境へ放出する際の基準値２００ｍｇ／リットルを満足する。   By neutralizing the filtrate 2 using carbon dioxide gas, the neutralized filtrate 4 is obtained to such an extent that the pH does not adversely affect the general environment (in the range of the marine discharge reference value pH 5.0 to 9.0). Further, in the normal neutralization treatment using carbon dioxide gas, dissolved calcium in the filtrate 2 reacts with the carbon dioxide gas to generate calcium carbonate precipitates and increase floating substances. However, as in this embodiment, the filtrate 2 And a large amount (predetermined amount or more) of carbon dioxide gas is forcibly mixed and reacted with the line mixer 21 to re-dissolve calcium carbonate as calcium bicarbonate, and the suspended solids can be reduced to about 100 mg / liter, Satisfies the standard value of 200 mg / liter for release into the general environment.

このように、固液分離処理工程Ｓ２及び中和処理工程Ｓ３を経て処理された中和濾液４は、浮遊物質（ＳＳ）を基準値以下とし、水素イオン濃度（ｐＨ）を基準値以下とし、且つ放射能量を低減させてから、一般環境（海洋など）に放流される。   Thus, the neutralized filtrate 4 treated through the solid-liquid separation treatment step S2 and the neutralization treatment step S3 has the suspended matter (SS) below the reference value, the hydrogen ion concentration (pH) below the reference value, And after reducing the amount of radioactivity, it is discharged into the general environment (the ocean etc.).

ここで、従来の施工方法のように、最初から最後まで清水５を切断箇所に注水し続けて湿式切断工程Ｓ１を行う場合と、上記した発明に係る施工方法のように、最初は清水５を切断箇所に注水し、その後は濾液２を再利用して湿式切断工程Ｓ１を行う場合とを比較する。
図５は、放流される中和濾液４の放射能濃度，放流される中和濾液４の量，及び放流される放射能量について、従来の施工方法と本発明に係る施工方法とを比較した一例を示す表である。図５に示すように、本発明の施工方法は、最終的に放流される中和濾液４の放射能濃度が従来の施工方法と比べて４倍程度増加するが、放流される中和濾液４の量が従来の施工方法と比べて１０分の１程度になり、結果的に放流される放射能量は従来の方法と比べて２分の１程度になる。この結果により、本発明に係る施工方法では、従来の施工方法よりも多くの放射性物質が除去されたことが確認できる。 Here, as in the conventional construction method, the case where the wet cutting step S1 is performed by continuously pouring the fresh water 5 from the beginning to the end, and the fresh water 5 is initially used as in the construction method according to the above-described invention. The case where water is poured into the cutting portion and then the wet cutting step S1 is performed by reusing the filtrate 2 is compared.
FIG. 5 is an example in which the conventional construction method and the construction method according to the present invention are compared with respect to the radioactivity concentration of the neutralized filtrate 4 to be discharged, the amount of the neutralized filtrate 4 to be discharged, and the amount of radioactivity to be discharged. It is a table | surface which shows. As shown in FIG. 5, in the construction method of the present invention, the radioactive concentration of the neutralized filtrate 4 finally discharged is increased by about 4 times compared to the conventional construction method, but the neutralized filtrate 4 discharged is discharged. As a result, the amount of radioactivity released is about one-half that of the conventional method. From this result, it can be confirmed that in the construction method according to the present invention, more radioactive substances were removed than in the conventional construction method.

上記した構成からなる放射化コンクリート切断工事の施工方法によれば、濾液２を冷却水として再利用することで、図４に示すように、放射性物質が溶解された濾液２は、飽和状態となって湿式切断工程時に放射性物質が溶解しなくなるとともに、中和されて最終的には放流される中和濾液４は、放射化コンクリート切断工事全体として少量となる。このため、図５に示すように、濾液２（中和濾液４）の放射能濃度は増加するが、放流される放射能の全体量を減少させることができる。これによって、放射化コンクリート切断工事に伴う一般公衆への影響を低減することができる。   According to the construction method of the activated concrete cutting construction having the above-described configuration, the filtrate 2 in which the radioactive substance is dissolved becomes saturated as shown in FIG. 4 by reusing the filtrate 2 as cooling water. As a result, the radioactive material does not dissolve during the wet cutting process, and the neutralized filtrate 4 that is neutralized and finally discharged becomes a small amount as a whole of the activated concrete cutting work. For this reason, as shown in FIG. 5, although the radioactive concentration of the filtrate 2 (neutralized filtrate 4) increases, the whole quantity of the released radioactivity can be decreased. As a result, it is possible to reduce the influence on the general public due to the activation concrete cutting work.

以上、本発明に係る放射化コンクリート切断工事の施工方法の実施の形態について説明したが、本発明は上記した実施の形態に限定されるものではなく、その趣旨を逸脱しない範囲で適宜変更可能である。例えば、上記した実施の形態では、切断廃液１を濾液２と固形分３とを分離する際にフィルタープレス装置１０が用いられているが、スラッジを含む廃液の水分と固形分とを十分に分離可能な装置であればなんでもよい。一方、フィルタープレス装置１０を用いることにより、高い固液分離性能を得ることができるとともに、脱水処理後の固形分のハンドリングを容易にすることができる。   As mentioned above, although embodiment of the construction method of the activation concrete cutting construction concerning this invention was described, this invention is not limited to above-described embodiment, In the range which does not deviate from the meaning, it can change suitably. is there. For example, in the above-described embodiment, the filter press apparatus 10 is used when the cutting waste liquid 1 is separated from the filtrate 2 and the solid content 3, but the water and solid content of the waste liquid containing sludge are sufficiently separated. Any device is possible. On the other hand, by using the filter press device 10, high solid-liquid separation performance can be obtained, and handling of the solid content after the dehydration treatment can be facilitated.

また、上記した実施の形態では、中和処理工程Ｓ３に炭酸ガスを用いるが、本発明は、塩酸や硫酸等の他の酸を用いてもよい。ただし、炭酸ガスは、塩酸・硫酸を用いる場合に比べて安全であり、更に、中和処理に塩酸を用いた場合には腐食性ガスが生成され、硫酸を用いた場合には溶解しない沈殿物が生成されて浮遊物質の量が上昇する恐れがあるため添加量を管理しなければならないが、炭酸ガスでは所定量（溶解カルシウムを重炭酸カルシウムにするのに必要な量）以上を添加すればよく添加量管理が非常に容易なので、作業効率を向上することができる。   In the embodiment described above, carbon dioxide gas is used in the neutralization step S3. However, other acids such as hydrochloric acid and sulfuric acid may be used in the present invention. However, carbon dioxide gas is safer than when hydrochloric acid / sulfuric acid is used, and moreover, corrosive gas is produced when hydrochloric acid is used for neutralization, and precipitates that do not dissolve when sulfuric acid is used. Since the amount of suspended solids may increase due to the generation of carbon dioxide, the amount added must be controlled. However, with carbon dioxide, if you add more than the prescribed amount (the amount necessary to convert dissolved calcium to calcium bicarbonate) Since the addition amount management is often very easy, work efficiency can be improved.

本発明に係る放射化コンクリート切断工事の施工方法の実施の形態を説明するためのフローチャート図である。It is a flowchart figure for demonstrating embodiment of the construction method of the activated concrete cutting construction which concerns on this invention. 本発明に係る放射化コンクリート切断工事の施工方法の実施の形態を説明するための固液分離処理工程を行う装置を示す図である。It is a figure which shows the apparatus which performs the solid-liquid separation process for demonstrating embodiment of the construction method of the activation concrete cutting construction which concerns on this invention. 本発明に係る放射化コンクリート切断工事の施工方法の実施の形態を説明するための中和処理工程を行う装置を示す構成図である。It is a block diagram which shows the apparatus which performs the neutralization process process for describing embodiment of the construction method of the activation concrete cutting construction which concerns on this invention. 本発明に係る放射化コンクリート切断工事の施工方法の実施の形態を説明するための固形分濃度と放射能濃度との関係を表すグラフである。It is a graph showing the relationship between solid content concentration and radioactivity concentration for demonstrating embodiment of the construction method of the activation concrete cutting construction which concerns on this invention. 本発明に係る放射化コンクリート切断工事の施工方法の実施の形態を説明するための本発明に係る施工方法と従来の施工方法とを比較した表である。It is the table | surface which compared the construction method which concerns on embodiment of the construction method of the activation concrete cutting construction which concerns on this invention, and the conventional construction method.

符号の説明Explanation of symbols

１ 切断廃液
２ 濾液
３ 固形分
４ 中和濾液
Ｓ１ 湿式切断工程
Ｓ２ 固液分離処理工程
Ｓ３ 中和処理工程

1 Cutting waste liquid 2 Filtrate 3 Solid content 4 Neutralized filtrate S1 Wet cutting process S2 Solid-liquid separation process S3 Neutralization process

Claims (1)

切断部分に冷却水を注水しつつ放射化コンクリートを切断する湿式切断工程と、
湿式切断工程時に生じる放射化コンクリートスラッジを含む切断廃液を、放射性物質を含有する固形分と放射性物質が溶解された濾液とに分離させる固液分離処理工程と、
該濾液を中和して中和濾液にする中和処理工程とを備える放射化コンクリート切断工事の施工方法において、
固液分離処理工程によって生じた前記濾液を、湿式切断工程時の冷却水として用いることを特徴とする放射化コンクリート切断工事の施工方法。

A wet cutting step of cutting the activated concrete while injecting cooling water into the cutting part;
A solid-liquid separation treatment step for separating cutting waste liquid containing activated concrete sludge generated during the wet cutting step into a solid content containing a radioactive substance and a filtrate in which the radioactive substance is dissolved;
In the construction method of the activated concrete cutting work comprising a neutralization treatment step to neutralize the filtrate to neutralize the filtrate,
An activation method for activated concrete cutting work, wherein the filtrate produced by the solid-liquid separation process is used as cooling water in a wet cutting process.

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JP2011209053A (en) * 2010-03-29 2011-10-20 Shimizu Corp Demolition method for concrete structure
JP2015025774A (en) * 2013-07-29 2015-02-05 株式会社キクテック Method of removing inorganic fine particles from contaminants containing inorganic fine particles
JP2016515918A (en) * 2013-03-08 2016-06-02 ペリ−バット Apparatus and method for decontaminating surfaces having one or more toxic products

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JP2016515918A (en) * 2013-03-08 2016-06-02 ペリ−バット Apparatus and method for decontaminating surfaces having one or more toxic products
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