JP2008232773A - Treater for water containing radioactive material in nuclear power plant - Google Patents

Treater for water containing radioactive material in nuclear power plant Download PDF

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JP2008232773A
JP2008232773A JP2007071787A JP2007071787A JP2008232773A JP 2008232773 A JP2008232773 A JP 2008232773A JP 2007071787 A JP2007071787 A JP 2007071787A JP 2007071787 A JP2007071787 A JP 2007071787A JP 2008232773 A JP2008232773 A JP 2008232773A
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activated carbon
nuclear power
power plant
filter
radioactive
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Shinichi Ohashi
伸一 大橋
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Organo Corp
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Japan Organo Co Ltd
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<P>PROBLEM TO BE SOLVED: To provide a device which can reduce the concentration of radioactive materials in the water containing them in a nuclear power plant without any extensive renovations of existing installations or increasing the amount of radioactive waste. <P>SOLUTION: In a purification system for the water containing radioactive materials which is equipped with a desalting tower 10 in a nuclear power plant, an active carbon treatment component 22 which brings the water containing radioactive materials into contact with active carbons is provided on the upstream side or the downstream side of an ion exchange resin layer 18 in the desalting tower 10. Alternatively, in a purification system for the water containing radioactive materials which is equipped with a filter 12 in the nuclear power plant, an active carbon treatment component which brings the water containing radioactive materials into contact with active carbons is provided in the filter. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

本発明は、ＰＷＲ型（加圧水型）、ＢＷＲ型（沸騰水型）等の原子力発電所における放射性物質含有水の処理装置に関し、さらに詳述すると、上記放射性物質含有水から放射性物質を除去する装置に関する。   The present invention relates to a treatment apparatus for radioactive substance-containing water in nuclear power plants such as PWR type (pressurized water type) and BWR type (boiling water type), and more specifically, an apparatus for removing radioactive substances from the radioactive substance-containing water. About.

ＰＷＲ型原子力発電所の１次系水には、コバルト６０をはじめとする放射性核種が含まれており、これらの放射性核種は鉄などの金属酸化物中に取り込まれた不溶解性物質またはイオンとして存在している。上記不溶解性放射性物質やイオン状放射性物質は、プラント定期検査時に作業員の放射線被曝の原因となるため、１次系水中の放射性物質の濃度低減や、放射性物質の配管表面への付着防止などのさまざまな対策が検討および実行されている。例えば、前者の対策としてはコバルト選択性樹脂を用いた放射性物質の濃度低減の提案があり、後者の対策としては配管表面への放射性物質の付着を防止する亜鉛注入の実施がある。   The primary water of the PWR nuclear power plant contains radioactive nuclides such as cobalt 60, and these radioactive nuclides are insoluble substances or ions incorporated into metal oxides such as iron. Existing. Since the above insoluble radioactive substances and ionic radioactive substances cause radiation exposure of workers during periodic plant inspections, reducing the concentration of radioactive substances in the primary water and preventing the radioactive substances from adhering to the piping surface, etc. Various measures are being considered and implemented. For example, as the former measure, there is a proposal of reducing the concentration of the radioactive substance using a cobalt selective resin, and as the latter countermeasure, there is an implementation of zinc injection for preventing the radioactive substance from adhering to the pipe surface.

また、ＰＷＲ型原子力発電所における１次系水の浄化系である化学体積制御系、ホウ酸回収系、燃料プール浄化系などには、それぞれの水質および目的に応じた浄化設備が設けられており、１次系水に含まれる放射性物質はこれらの浄化設備で除去されている。   In addition, the chemical volume control system, boric acid recovery system, fuel pool purification system, etc., which are primary water purification systems in PWR nuclear power plants, are equipped with purification facilities according to their water quality and purpose. Radioactive substances contained in the primary water are removed by these purification facilities.

通常は、イオン状放射性物質はカチオン交換樹脂およびアニオン交換樹脂を用いた混床、単床あるいは複床による脱塩塔にて除去され、不溶解性放射性物質は高分子製不織布などを用いたプリーツ状カートリッジフィルタにより除去されている。例えば、図６に示すように、１次系水の化学体積制御系にカチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔１０およびプリーツ状カートリッジフィルタ１２をこの順に設置し、原子炉格納容器からの１次系水１４を上記脱塩塔１０およびフィルタ１２に順次通水した後、体積制御タンク１６に送ることが行われている（例えば、非特許文献１参照）。なお、図中１８は脱塩塔１０内のイオン交換樹脂層、２０はフィルタ１２内のプリーツ状フィルタメディアを示す。   Usually, ionic radioactive materials are removed in a mixed bed using cation exchange resin and anion exchange resin, single bed or multiple bed desalting tower, and insoluble radioactive materials are pleated using polymer nonwoven fabric. It is removed by the cartridge filter. For example, as shown in FIG. 6, a mixed bed desalting tower 10 and a pleated cartridge filter 12 using a cation exchange resin and an anion exchange resin in a chemical volume control system for primary water are installed in this order, The primary water 14 from the containment vessel is sequentially passed through the desalting tower 10 and the filter 12 and then sent to the volume control tank 16 (see, for example, Non-Patent Document 1). In the figure, 18 indicates an ion exchange resin layer in the desalting tower 10, and 20 indicates a pleated filter medium in the filter 12.

「原子炉水化学ハンドブック」（日本原子力学会編、コロナ社発行）の１１５〜１１６頁および１２２〜１２３頁"Reactor Water Chemistry Handbook" (edited by the Atomic Energy Society of Japan, published by Corona), pages 115-116 and 122-123

本発明者の知見によれば、現在、ＰＷＲ型原子力発電所における１次系水の化学体積制御系や放射性廃液処理系において、前述した脱塩塔やフィルタで除去されにくい形態の放射性物質が存在することが確認されている。この形態の放射性物質は、脱塩塔に充填されたイオン交換樹脂でも除去されにくいことから、完全なイオン状ではないと考えられ、微細なコロイド状物質として存在するものと推察される。また、放射性廃液処理系における本発明者の知見では、上記形態の放射性物質は限外ろ過膜でも除去されにくいことが確認されている。   According to the knowledge of the present inventor, there is currently a radioactive material in a form that is difficult to be removed by the above-described desalting tower and filter in the chemical volume control system and the radioactive liquid waste treatment system of the primary water in the PWR nuclear power plant. It has been confirmed that Since this form of radioactive material is difficult to remove even with an ion exchange resin packed in a desalting tower, it is considered that the radioactive material is not completely ionic, and is presumed to exist as a fine colloidal material. In addition, according to the knowledge of the present inventors in the radioactive liquid waste treatment system, it has been confirmed that the radioactive substance of the above form is difficult to be removed even by an ultrafiltration membrane.

上述した脱塩塔やフィルタで除去されにくい形態の放射性物質を除去するためには、より目開きの細かいナノ濾過膜（ＮＦ膜）あるいは逆浸透膜（ＲＯ膜）を用いた濾過処理や、１次系水に金属塩等を加えて放射性物質を沈殿させる共沈法などの凝集処理を行うことが考えられる。しかし、前者の手段は、フィルタの透過抵抗が増大するため、既設設備の大規模改造が必要となり、適用が難しい。また、後者の手段は、放射性廃棄物量の増大につながるため好ましくない。そのため、ＰＷＲ型原子力発電所の１次系水中の放射性物質濃度を現状よりも低減することは、事実上困難となっていた。   In order to remove radioactive substances in a form that is difficult to remove with the above-described desalting tower or filter, filtration using a nanofiltration membrane (NF membrane) or reverse osmosis membrane (RO membrane) with finer openings, It is conceivable to perform a coagulation treatment such as a coprecipitation method in which a radioactive salt is precipitated by adding a metal salt or the like to secondary water. However, the former means increases the transmission resistance of the filter, necessitating a large-scale modification of existing facilities, and is difficult to apply. The latter means is not preferable because it leads to an increase in the amount of radioactive waste. Therefore, it has been practically difficult to reduce the concentration of radioactive material in the primary water of the PWR nuclear power plant from the current level.

本発明は、前述した事情に鑑みてなされたもので、既設設備の大規模改造を行うことなく、また放射性廃棄物量を増大させることなく、原子力発電所の放射性物質含有水中の放射性物質濃度を低減することができる装置を提供することを目的とする。   The present invention has been made in view of the above-described circumstances, and reduces the concentration of radioactive material in the radioactive material-containing water of a nuclear power plant without making a large-scale modification of existing facilities and without increasing the amount of radioactive waste. It is an object of the present invention to provide an apparatus that can do this.

本発明者は、前記目的を達成するために種々検討を行った結果、原子力発電所の放射性物質含有水中に含まれる脱塩塔やフィルタで除去されにくい形態の放射性物質は、上記放射性物質含有水を活性炭に接触させることにより除去できることを見出した。   As a result of various studies to achieve the above object, the present inventor has found that the radioactive material in a form that is difficult to be removed by a desalting tower or a filter contained in the radioactive material-containing water of a nuclear power plant is the above-mentioned radioactive material-containing water. Was found to be removed by contacting the activated carbon with activated carbon.

本発明は、上記知見に基づいてなされたもので、下記（１）および（２）の発明を提供する。
（１）原子力発電所における脱塩塔を備えた放射性物質含有水の浄化系において、前記脱塩塔内のイオン交換樹脂層の上流側または下流側に前記放射性物質含有水を活性炭に接触させる活性炭処理部を設けたことを特徴とする原子力発電所における放射性物質含有水の処理装置。
（２）原子力発電所におけるフィルタを備えた放射性物質含有水の浄化系において、前記フィルタ内に前記放射性物質含有水を活性炭に接触させる活性炭処理部を設けたことを特徴とする原子力発電所における放射性物質含有水の処理装置。 The present invention has been made based on the above findings, and provides the following inventions (1) and (2).
(1) In the purification system of radioactive substance-containing water provided with a desalting tower in a nuclear power plant, activated carbon that makes the radioactive substance-containing water contact activated carbon upstream or downstream of the ion exchange resin layer in the desalting tower An apparatus for treating radioactive material-containing water in a nuclear power plant, characterized in that a treatment unit is provided.
(2) In the purification system for radioactive substance-containing water provided with a filter in a nuclear power plant, an activated carbon treatment section for bringing the radioactive substance-containing water into contact with the activated carbon is provided in the filter. Substance-containing water treatment equipment.

本発明において、原子力発電所における放射性物質含有水の浄化系とは、ＰＷＲ型原子力発電所の１次系における化学体積制御系、ホウ酸回収系、燃料プール浄化系および放射性廃液処理系、ＢＷＲ型原子力発電所における原子炉冷却材浄化系、燃料プール冷却浄化系および放射性廃液処理系等が挙げられるが、これらに限定されるものではない。   In the present invention, the radioactive material-containing water purification system in a nuclear power plant is a chemical volume control system, boric acid recovery system, fuel pool purification system and radioactive waste liquid treatment system, BWR type in a primary system of a PWR nuclear power plant. Examples include, but are not limited to, a nuclear reactor coolant purification system, a fuel pool cooling and purification system, and a radioactive liquid waste treatment system.

（１）の発明における脱塩塔としては、例えば、カチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔、カチオン交換樹脂およびアニオン交換樹脂を用いた複床式脱塩塔、カチオン交換樹脂を用いた単床式脱塩塔とアニオン交換樹脂を用いた単床式脱塩塔とからなる脱塩塔等を挙げることができる。   Examples of the desalting tower in the invention of (1) include a mixed bed desalting tower using a cation exchange resin and an anion exchange resin, a multi-bed desalting tower using a cation exchange resin and an anion exchange resin, and a cation exchange. Examples thereof include a desalting tower composed of a single bed type desalting tower using a resin and a single bed type desalting tower using an anion exchange resin.

（２）の発明におけるフィルタとしては、例えば、プリーツ状カートリッジフィルタ、デプスフィルタ、糸巻きフィルタ等を挙げることができる。   Examples of the filter in the invention of (2) include a pleated cartridge filter, a depth filter, and a bobbin filter.

本発明では、活性炭として、活性炭の充填量をＶｍ３、処理流量をＱｍ３／ｈとしたときに、上記活性炭からの不純物溶出量が、Ｃｌ（ｇ／ｍ３／ｈ）≦０．０５Ｑ／Ｖ、Ｆ（ｇ／ｍ３／ｈ）≦０．１５Ｑ／Ｖ、Ｎａ（ｇ／ｍ３／ｈ）≦０．０３Ｑ／Ｖであるものを用いることが好ましく、これによりＰＷＲ発電所の１次冷却材の水質維持基準値を満足することできる。さらに、望ましくは、処理水質が適用プラント毎に定められている推奨値を満足するレベルまで洗浄された活性炭（高純度活性炭）を用いることが好ましい。これにより、適用プラントの水質を維持したまま本技術を適用することができ、水質管理業務に影響を及ぼすことなく放射性物質低減効果を得ることができる。 In the present invention, the activated carbon filling amount is Vm 3 , and the treatment flow rate is Qm 3 / h. The impurity elution amount from the activated carbon is Cl (g / m 3 /h)≦0.05 Q / V, it is preferable to use a material which is F (g / m 3 /h)≦0.15Q/V,Na(g/m 3 /h)≦0.03Q/V, thereby primary PWR power plants The water quality maintenance standard value of the coolant can be satisfied. Furthermore, it is desirable to use activated carbon (high-purity activated carbon) that has been cleaned to a level that satisfies the recommended value determined for each application plant. Thereby, this technique can be applied, maintaining the water quality of an applied plant, and the radioactive substance reduction effect can be acquired, without affecting water quality management work.

上述した浄化系で処理した処理水は、冷却水として再利用してもよく、系外に排出してもよい。   The treated water treated in the purification system described above may be reused as cooling water or discharged outside the system.

本発明によれば、既設設備の大規模改造を行うことなく、また放射性廃棄物量を増大させることなく、原子力発電所の放射性物質含有水中に含まれる脱塩塔やフィルタで除去されにくい形態の放射性物質を除去して、上記放射性物質含有水中の放射性物質濃度を低減することができる。   According to the present invention, radioactive materials in a form that is difficult to be removed by a desalting tower or a filter contained in radioactive material-containing water of a nuclear power plant without performing large-scale remodeling of existing facilities and without increasing the amount of radioactive waste. The substance can be removed to reduce the radioactive substance concentration in the radioactive substance-containing water.

以下、本発明の実施の形態を図面を参照して説明するが、本発明は下記例に限定されるものではない。   Hereinafter, embodiments of the present invention will be described with reference to the drawings. However, the present invention is not limited to the following examples.

（第１実施形態）
図１は本発明に係る原子力発電所における放射性物質含有水の処理装置の第１実施形態を示すフロー図である。本実施形態は、ＰＷＲ型原子力発電所の１次系水処理装置として構成されており、１次系水の化学体積制御系にカチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔１０およびプリーツ状カートリッジフィルタ１２をこの順に設置し、原子炉格納容器からの１次系水１４を上記脱塩塔１０およびフィルタ１２に順次通水した後、体積制御タンク１６に送る図６に示した装置において、脱塩塔１０内のイオン交換樹脂層１８の下方（下流側）に、濾過層を形成するように活性炭層（活性炭処理部）２２を配置したものである。 (First embodiment)
FIG. 1 is a flowchart showing a first embodiment of a radioactive substance-containing water treatment apparatus in a nuclear power plant according to the present invention. The present embodiment is configured as a primary water treatment apparatus for a PWR nuclear power plant, and a mixed bed desalting tower 10 using a cation exchange resin and an anion exchange resin for the chemical volume control system of the primary water. The pleated cartridge filter 12 is installed in this order, and the primary water 14 from the reactor containment vessel is sequentially passed through the desalting tower 10 and the filter 12 and then sent to the volume control tank 16 as shown in FIG. In the apparatus, an activated carbon layer (activated carbon treatment unit) 22 is disposed below the ion exchange resin layer 18 in the desalting tower 10 (downstream side) so as to form a filtration layer.

一般に、活性炭はイオン交換樹脂よりも比重が大きく流動しにくい特性がある。そのため、脱塩塔の下部に予め活性炭層を形成し、その上方にイオン交換樹脂層を形成することにより、比較的容易にイオン交換樹脂と活性炭との複床層を得ることができる。また、この際に特開２００４−０８１９２７、特開２００４−２５５２９２に示されている方法を用いることにより、容易に上記複床層を得ることができる。本実施形態によれば、既設の設備をそのまま利用して本発明を容易に実施することができる。   In general, activated carbon has a specific gravity greater than that of an ion exchange resin and is less likely to flow. Therefore, by forming an activated carbon layer in the lower part of the desalting tower in advance and forming an ion exchange resin layer thereabove, a double bed layer of ion exchange resin and activated carbon can be obtained relatively easily. Further, at this time, by using the methods disclosed in Japanese Patent Application Laid-Open Nos. 2004-081927 and 2004-255292, the multi-bed layer can be easily obtained. According to this embodiment, the present invention can be easily implemented using existing facilities as they are.

（第２実施形態）
図２は本発明に係る原子力発電所における放射性物質含有水の処理装置の第２実施形態を示すフロー図である。本実施形態は、ＰＷＲ型原子力発電所の１次系水処理装置として構成されており、１次系水の化学体積制御系にカチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔１０およびプリーツ状カートリッジフィルタ１２をこの順に設置し、原子炉格納容器からの１次系水１４を上記脱塩塔１０およびフィルタ１２に順次通水した後、体積制御タンク１６に送る図６に示した装置において、フィルタ１２内のプリーツ状フィルタメディア２０の内方（上流側）に、濾過層を形成するように活性炭層（活性炭処理部）２２を配置したものである。 (Second Embodiment)
FIG. 2 is a flowchart showing a second embodiment of the apparatus for treating radioactive material-containing water in a nuclear power plant according to the present invention. The present embodiment is configured as a primary water treatment apparatus for a PWR nuclear power plant, and a mixed bed desalting tower 10 using a cation exchange resin and an anion exchange resin for the chemical volume control system of the primary water. The pleated cartridge filter 12 is installed in this order, and the primary water 14 from the reactor containment vessel is sequentially passed through the desalting tower 10 and the filter 12 and then sent to the volume control tank 16 as shown in FIG. In the apparatus, an activated carbon layer (activated carbon treatment unit) 22 is disposed on the inner side (upstream side) of the pleated filter medium 20 in the filter 12 so as to form a filtration layer.

本例の活性炭層を有するフィルタは、図３に示すように、内筒および外筒としてのステンレス鋼製またはプラスチック製のサポートネット２６、２６の間に粒状活性炭を充填して活性炭層２２を形成することにより円筒形の活性炭カートリッジ２８を作製し、この活性炭カートリッジ２８を既設の円筒形のカートリッジフィルタ１２の内側に配置するとともに、Ｏ−リング３２、３４により活性炭カートリッジ２８とカートリッジフィルタ１２との間およびカートリッジフィルタ１２とアウターケージ３６との間をそれぞれシールすることにより作製することができる。図３に示したカートリッジフィルタ１２と活性炭カートリッジ２８との一体型フィルタ３０では、原水３８はフィルタ３０の内側から外側に向けて通水され、処理水４０はカートリッジフィルタ１２から流出する。なお、活性炭としては粒状活性炭のほか、繊維状活性炭を筒状に成形した活性炭フィルタなども使用可能であり、この場合はサポートネットを不要とすることができる。本実施形態によれば、既設の設備をそのまま利用して本発明を容易に実施することができる。   As shown in FIG. 3, the filter having the activated carbon layer of this example is filled with granular activated carbon between stainless steel or plastic support nets 26, 26 as an inner cylinder and an outer cylinder to form an activated carbon layer 22. As a result, a cylindrical activated carbon cartridge 28 is produced, and this activated carbon cartridge 28 is disposed inside the existing cylindrical cartridge filter 12, and between the activated carbon cartridge 28 and the cartridge filter 12 by O-rings 32 and 34. Further, it can be manufactured by sealing between the cartridge filter 12 and the outer cage 36. In the integrated filter 30 of the cartridge filter 12 and the activated carbon cartridge 28 shown in FIG. 3, the raw water 38 is passed from the inside to the outside of the filter 30, and the treated water 40 flows out from the cartridge filter 12. As the activated carbon, in addition to granular activated carbon, an activated carbon filter in which a fibrous activated carbon is formed into a cylindrical shape can be used. In this case, a support net can be omitted. According to this embodiment, the present invention can be easily implemented using existing facilities as they are.

（第３実施形態）
図４は本発明に係る原子力発電所における放射性物質含有水の処理装置の第３実施形態を示すフロー図である。本実施形態は、ＰＷＲ型原子力発電所の１次系水処理装置として構成されており、１次系水の化学体積制御系にプリーツ状カートリッジフィルタ１２およびカチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔１０をこの順に設置し、原子炉格納容器からの１次系水１４を上記フィルタ１２および脱塩塔１０に順次通水した後、体積制御タンク１６に送る装置において、脱塩塔１０内のイオン交換樹脂層１８の上方（上流側）に、濾過層を形成するように活性炭層（活性炭処理部）２２を設けたものである。 (Third embodiment)
FIG. 4 is a flowchart showing a third embodiment of the radioactive substance-containing water treatment apparatus in the nuclear power plant according to the present invention. The present embodiment is configured as a primary water treatment apparatus for a PWR nuclear power plant, and a pleated cartridge filter 12, a cation exchange resin, and an anion exchange resin are used as a chemical volume control system for primary water. In the apparatus in which the floor-type desalting tower 10 is installed in this order and the primary water 14 from the reactor containment vessel is sequentially passed through the filter 12 and the desalting tower 10 and then sent to the volume control tank 16, An activated carbon layer (activated carbon treatment part) 22 is provided above the ion exchange resin layer 18 in the tower 10 (upstream side) so as to form a filtration layer.

活性炭はイオン交換樹脂よりも比重が大きく、粒径が同じであれば沈降速度が速くなる。沈降速度が速い粒子を上層に充填すると、樹脂流入時に生じる流動で活性炭層が樹脂層内に入り込み、均一に充填されない可能性がある。これを防ぐには、前述の特開２００４−０８１９２７、特開２００４−２５５２９２に示されている方法を用いるか、あるいは活性炭の粒径を小さくし、沈降速度を遅くする手法が有効である。後者の方法を用いた場合には、１次系水が不溶解性物質を多く含む水質であると、小粒径の活性炭を用いた活性炭層に不溶解性物質が堆積して差圧が急激に上昇する可能性があるが、本実施形態では、活性炭層の上流側にフィルタを設置しているので、１次系水が不溶解性物質を多く含む水質であっても、上記のように活性炭層の差圧が急激に上昇することを防止することができるともに、イオン交換樹脂層の目詰まりを防ぐことができる。   Activated carbon has a specific gravity greater than that of the ion exchange resin, and if the particle size is the same, the sedimentation rate is increased. If the upper layer is filled with particles having a high sedimentation speed, the activated carbon layer may enter the resin layer due to the flow generated when the resin flows in, and may not be uniformly filled. In order to prevent this, it is effective to use the method disclosed in the aforementioned JP-A-2004-081927 and JP-A-2004-255292, or reduce the particle size of the activated carbon and slow down the sedimentation rate. When the latter method is used, if the primary water has a water quality that contains a large amount of insoluble substances, the insoluble substances are deposited on the activated carbon layer using activated carbon having a small particle size, and the differential pressure increases rapidly. In this embodiment, since a filter is installed on the upstream side of the activated carbon layer, even if the primary water has a high quality of insoluble substances, as described above. While being able to prevent the differential pressure of the activated carbon layer from rising rapidly, clogging of the ion exchange resin layer can be prevented.

また、ＰＷＲ型原子力発電所の１次系水にはイオン交換樹脂の酸化劣化の要因となる過酸化水素が含まれているが、活性炭は過酸化水素を分解する触媒として機能するため、本実施形態では、イオン交換樹脂の上流側で１次系水を活性炭と接触させることにより、１次系水中の過酸化水素を除去してイオン交換樹脂の酸化劣化を防止することができる。   In addition, the primary water of the PWR nuclear power plant contains hydrogen peroxide, which causes oxidative degradation of the ion exchange resin, but the activated carbon functions as a catalyst for decomposing hydrogen peroxide. In the embodiment, by bringing the primary water into contact with the activated carbon on the upstream side of the ion exchange resin, hydrogen peroxide in the primary water can be removed to prevent oxidative deterioration of the ion exchange resin.

（第４実施形態）
図５は本発明に係る原子力発電所における放射性物質含有水の処理装置の第４実施形態を示すフロー図である。本実施形態は、ＰＷＲ型原子力発電所の１次系水処理装置として構成されており、１次系水の化学体積制御系にプリーツ状カートリッジフィルタ１２およびカチオン交換樹脂およびアニオン交換樹脂を用いた混床式脱塩塔１０をこの順に設置し、原子炉格納容器からの１次系水１４を上記フィルタ１２および脱塩塔１０に順次通水した後、体積制御タンク１６に送る装置において、フィルタ１２内のプリーツ状フィルタメディア２０の内方（上流側）に、濾過層を形成するように活性炭層（活性炭処理部）２２を配置したものである。 (Fourth embodiment)
FIG. 5 is a flowchart showing a fourth embodiment of the radioactive substance-containing water treatment apparatus in the nuclear power plant according to the present invention. This embodiment is configured as a primary water treatment apparatus for a PWR nuclear power plant, and a pleated cartridge filter 12, a cation exchange resin, and an anion exchange resin are used as a chemical volume control system for primary water. In the apparatus in which the floor-type desalting tower 10 is installed in this order and the primary water 14 from the reactor containment vessel is sequentially passed through the filter 12 and the desalting tower 10 and then sent to the volume control tank 16, the filter 12 An activated carbon layer (activated carbon treatment part) 22 is arranged inside the pleated filter media 20 (upstream side) so as to form a filtration layer.

本実施形態の処理装置は、第３実施形態の処理装置と同様の作用効果を奏する。また、フィルタとして図３に示した一体型フィルタを用いれば、既設の設備をそのまま利用して本発明を容易に実施することができる。   The processing apparatus of this embodiment has the same effects as the processing apparatus of the third embodiment. Moreover, if the integrated filter shown in FIG. 3 is used as a filter, the present invention can be easily implemented using existing facilities as they are.

本発明の処理装置は、上述した実施形態に限定されるものではない。例えば、第１〜第４実施形態において、活性炭処理部を他の箇所に設けてもよく、複数箇所に設けてもよい。   The processing apparatus of this invention is not limited to embodiment mentioned above. For example, in the first to fourth embodiments, the activated carbon treatment unit may be provided in another location, or may be provided in a plurality of locations.

本発明に係る原子力発電所における放射性物質含有水の処理装置の第１実施形態を示すフロー図である。It is a flowchart which shows 1st Embodiment of the processing apparatus of the radioactive substance containing water in the nuclear power station which concerns on this invention. 本発明に係る原子力発電所における放射性物質含有水の処理装置の第２実施形態を示すフロー図である。It is a flowchart which shows 2nd Embodiment of the processing apparatus of the radioactive substance containing water in the nuclear power station which concerns on this invention. カートリッジフィルタと活性炭カートリッジとの一体型フィルタを示すもので、（ａ）は作製工程を示す図、（ｂ）はカートリッジフィルタおよび活性炭カートリッジの断面を示す図である。1A and 1B show an integrated filter of a cartridge filter and an activated carbon cartridge, in which FIG. 1A shows a manufacturing process, and FIG. 2B shows a cross section of the cartridge filter and the activated carbon cartridge. 本発明に係る原子力発電所における放射性物質含有水の処理装置の第３実施形態を示すフロー図である。It is a flowchart which shows 3rd Embodiment of the processing apparatus of the radioactive substance containing water in the nuclear power station which concerns on this invention. 本発明に係る原子力発電所における放射性物質含有水の処理装置の第４実施形態を示すフロー図である。It is a flowchart which shows 4th Embodiment of the processing apparatus of the radioactive substance containing water in the nuclear power station which concerns on this invention. ＰＷＲ型原子力発電所における１次系水の浄化系の一例を示すフロー図である。It is a flowchart which shows an example of the purification system of the primary system water in a PWR type nuclear power plant.

符号の説明Explanation of symbols

１０ 脱塩塔
１２ カートリッジフィルタ
１４ １次系水
１６ 体積制御タンク
１８ イオン交換樹脂層
２０ フィルタメディア
２２ 活性炭層（活性炭処理部） DESCRIPTION OF SYMBOLS 10 Desalination tower 12 Cartridge filter 14 Primary system water 16 Volume control tank 18 Ion exchange resin layer 20 Filter media 22 Activated carbon layer (activated carbon processing part)

Claims (3)

原子力発電所における脱塩塔を備えた放射性物質含有水の浄化系において、前記脱塩塔内のイオン交換樹脂層の上流側または下流側に前記放射性物質含有水を活性炭に接触させる活性炭処理部を設けたことを特徴とする原子力発電所における放射性物質含有水の処理装置。   In the purification system of radioactive substance-containing water provided with a desalting tower in a nuclear power plant, an activated carbon treatment unit for bringing the radioactive substance-containing water into contact with activated carbon upstream or downstream of the ion exchange resin layer in the desalting tower An apparatus for treating radioactive material-containing water in a nuclear power plant characterized by being provided. 原子力発電所におけるフィルタを備えた放射性物質含有水の浄化系において、前記フィルタ内に前記放射性物質含有水を活性炭に接触させる活性炭処理部を設けたことを特徴とする原子力発電所における放射性物質含有水の処理装置。   In a purification system for radioactive substance-containing water provided with a filter in a nuclear power plant, an activated carbon treatment unit for bringing the radioactive substance-containing water into contact with the activated carbon is provided in the filter. Processing equipment. 前記活性炭の充填量をＶｍ３、処理流量をＱｍ３／ｈとしたときに、前記活性炭からの不純物溶出量が、Ｃｌ（ｇ／ｍ３／ｈ）≦０．０５Ｑ／Ｖ、Ｆ（ｇ／ｍ３／ｈ）≦０．１５Ｑ／Ｖ、Ｎａ（ｇ／ｍ３／ｈ）≦０．０３Ｑ／Ｖであることを特徴とする請求項１または２に記載の原子力発電所における放射性物質含有水の処理装置。 When the filling amount of the activated carbon is Vm 3 and the treatment flow rate is Qm 3 / h, the impurity elution amount from the activated carbon is Cl (g / m 3 /h)≦0.05 Q / V, F (g / m 3 /h)≦0.15Q/V,Na(g/m 3 radioactive substance-containing water in a nuclear power plant according to claim 1 or 2, characterized in that a /h)≦0.03Q/V Processing equipment.
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