JP7273740B2 - Pollution suspension treatment equipment - Google Patents

Pollution suspension treatment equipment Download PDF

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JP7273740B2
JP7273740B2 JP2020019309A JP2020019309A JP7273740B2 JP 7273740 B2 JP7273740 B2 JP 7273740B2 JP 2020019309 A JP2020019309 A JP 2020019309A JP 2020019309 A JP2020019309 A JP 2020019309A JP 7273740 B2 JP7273740 B2 JP 7273740B2
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suspension
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contaminated suspension
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JP2021124437A (en
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直樹 田嶋
恒雄 大村
紘子 澤田
玲菜 三澤
直希 宮澤
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Toshiba Corp
Toshiba Energy Systems and Solutions Corp
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Description

本発明は、汚染懸濁液処理装置に関する。 The present invention relates to contaminated suspension treatment equipment.

放射性核種を含む汚染懸濁液を処理するために、さまざまな技術が提案されている。 Various techniques have been proposed to treat contaminated suspensions containing radionuclides.

汚染懸濁液は、海水や地下水などに由来した浮遊物質（ＳＳ；Ｓｕｓｐｅｎｄｅｄ Ｓｏｌｉｄｓ）などの固体成分（微粒子）が懸濁した懸濁水であって、汚染懸濁液は、放射性核種が水に溶解していると共に、放射性核種が固体成分に付着している。このため、たとえば、砂濾過などの濾過フィルタで汚染懸濁液から固体成分を濾物として分離して除去した後に、汚染懸濁液の濾液から放射性核種（放射性セシウム，放射性ストロンチウムなど）を吸着材に吸着させることで除去している。 Contaminated suspension is suspension water in which solid components (fine particles) such as suspended solids (SS) derived from seawater, groundwater, etc. are suspended. and the radionuclide is attached to the solid component. For this reason, for example, after separating and removing the solid components from the polluted suspension with a filtration filter such as sand filtration, the radionuclides (radioactive cesium, radioactive strontium, etc.) from the filtrate of the polluted suspension removed by adsorption.

特許第６２８９８８４号Patent No. 6289884

東京電力ホールディングス株式会社，“第三セシウム吸着装置 Cs除去性能未達事象への対応状況について”，［online］，2018.11.29，［2020.01.08検索］，インターネット＜URL:https://www.meti.go.jp/earthquake/nuclear/decommissioning/committee/osensuitaisakuteam/2018/12/3-1-3.pdf＞Tokyo Electric Power Company Holdings, Inc., “Response status to failure to achieve Cs removal performance of third cesium adsorption device”, [online], 2018.11.29, [searched 2020.01.08], Internet <URL: https://www. meti.go.jp/earthquake/nuclear/decommissioning/committee/osensuitaisakuteam/2018/12/3-1-3.pdf＞

しかしながら、上記の関連技術では、汚染懸濁液から固体成分を十分に除去することが困難であって、放射性核種を除去する処理を効率的に実行することが容易でない場合がある。 However, it may be difficult to sufficiently remove the solid components from the contaminated suspension with the above-mentioned related techniques, and it may not be easy to efficiently carry out the treatment to remove the radionuclides.

したがって、本発明が解決しようとする課題は、汚染懸濁液から放射性核種を効率的に除去可能な汚染懸濁液処理装置を提供することである。 Accordingly, the problem to be solved by the present invention is to provide a contaminated suspension treatment apparatus capable of efficiently removing radionuclides from contaminated suspensions.

実施形態の汚染懸濁液処理装置は、固液分離機構と回収機構と貯蔵部とを備え、放射性核種を含む汚染懸濁液を処理する。固液分離機構は、汚染懸濁液よりも固体成分が濃縮された濃縮液と、汚染懸濁液から固体成分が除去された濾液とに、汚染懸濁液を分離する。回収機構は、固液分離機構において分離された濃縮液から液体成分を除去することによって固体成分を回収する。貯蔵部は、固液分離機構に供給する汚染懸濁液を貯蔵する。汚染懸濁液処理装置は、回収機構において濃縮液から除去された液体成分を貯蔵部に戻すように構成されている。

A contaminated suspension processing apparatus according to an embodiment includes a solid-liquid separation mechanism, a recovery mechanism, and a storage unit , and processes contaminated suspension containing radionuclides. The solid-liquid separation mechanism separates the contaminated suspension into a concentrate in which the solid components are more concentrated than the contaminated suspension and a filtrate in which the solid components are removed from the contaminated suspension. The recovery mechanism recovers the solid component by removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism. The reservoir stores the contaminated suspension to be supplied to the solid-liquid separation mechanism. The contaminated suspension treatment apparatus is configured to return liquid components removed from the concentrate in the recovery mechanism to the reservoir.

本発明によれば、汚染懸濁液から放射性核種を効率的に除去可能な汚染懸濁液処理装置を提供することができる。 ADVANTAGE OF THE INVENTION According to this invention, the contaminated suspension processing apparatus which can remove a radionuclide efficiently from a contaminated suspension can be provided.

図１は、第１実施形態に係る汚染懸濁液処理装置を模式的に示す図である。FIG. 1 is a diagram schematically showing a contaminated suspension treatment apparatus according to a first embodiment. 図２は、第２実施形態に係る汚染懸濁液処理装置を模式的に示す図である。FIG. 2 is a diagram schematically showing a contaminated suspension treatment apparatus according to a second embodiment. 図３は、第３実施形態に係る汚染懸濁液処理装置を模式的に示す図である。FIG. 3 is a diagram schematically showing a contaminated suspension treatment apparatus according to a third embodiment.

＜第１実施形態＞
［Ａ］汚染懸濁液処理装置
図１は、第１実施形態に係る汚染懸濁液処理装置を模式的に示す図である。 <First embodiment>
[A] Contaminated Suspension Processing Apparatus FIG. 1 is a diagram schematically showing a contaminated suspension processing apparatus according to the first embodiment.

図１に示すように、本実施形態において、汚染懸濁液処理装置は、汚染懸濁液貯蔵部１０と固液分離機構２０と吸着機構３０と回収機構４０と回収液貯蔵部５０とを備え、放射性核種を含む汚染懸濁液から放射性核種を除去するための処理を実行するように構成されている。 As shown in FIG. 1, in this embodiment, the contaminated suspension treatment apparatus includes a contaminated suspension storage unit 10, a solid-liquid separation mechanism 20, an adsorption mechanism 30, a recovery mechanism 40, and a recovered liquid storage unit 50. , configured to perform a process for removing radionuclides from a contaminated suspension containing radionuclides.

以下より、汚染懸濁液処理装置を構成する各部について順次説明する。 Each part constituting the contaminated suspension treatment apparatus will be sequentially described below.

［Ａ－１］汚染懸濁液貯蔵部１０
汚染懸濁液貯蔵部１０は、タンクを備えており、汚染懸濁液を貯蔵する。汚染懸濁液は、海水や地下水などに由来した浮遊物質などの固体成分が懸濁した汚染水である。汚染懸濁液は、放射性セシウム，放射性ストロンチウムなどの放射性核種を含み、放射性核種が水に溶解していると共に、放射性核種が固体成分に付着している。 [A-1] Contaminated suspension storage unit 10
The contaminated suspension reservoir 10 comprises a tank and stores the contaminated suspension. Contaminated suspension is contaminated water in which solid components such as suspended matter derived from seawater, groundwater, etc. are suspended. Contaminated suspensions contain radionuclides, such as radioactive cesium, radioactive strontium, etc., which are dissolved in water and which are attached to solid components.

［Ａ－２］固液分離機構２０
固液分離機構２０は、汚染懸濁液貯蔵部１０から配管Ｐ１０を介して汚染懸濁液が供給される。固液分離機構２０においては、汚染懸濁液は、汚染懸濁液よりも固体成分が濃縮された濃縮液（濾物）と、汚染懸濁液から固体成分が除去された濾液とに分離される。 [A-2] Solid-liquid separation mechanism 20
The solid-liquid separation mechanism 20 is supplied with the contaminated suspension from the contaminated suspension reservoir 10 through the pipe P10. In the solid-liquid separation mechanism 20, the contaminated suspension is separated into a concentrated liquid (filtrate) in which solid components are more concentrated than the contaminated suspension and a filtrate in which solid components are removed from the contaminated suspension. be.

固液分離機構２０は、たとえば、セラミックフィルタ、金属フィルタ、膜ろ過、砂ろ過などの濾過装置で構成されている。この他に、固液分離機構２０は、サイクロンやデカンタなどの遠心分離装置で構成されていてもよく、蒸発分離装置によって固液分離を行うように構成されていてもよい。更に、固液分離機構２０は、上記した各手段を適宜組み合わせて構成されていてもよい。たとえば、金属フィルタで粗分離を行った後にセラミックスフィルタで精密分離を行うように組み合わせるによって分離効率を高めることができる。 The solid-liquid separation mechanism 20 is composed of, for example, a filtering device such as a ceramic filter, a metal filter, a membrane filter, or a sand filter. In addition, the solid-liquid separation mechanism 20 may be configured by a centrifugal separator such as a cyclone or a decanter, or may be configured to perform solid-liquid separation by an evaporator. Furthermore, the solid-liquid separation mechanism 20 may be configured by appropriately combining the above-described means. For example, separation efficiency can be enhanced by performing coarse separation with a metal filter and then fine separation with a ceramics filter.

［Ａ－３］吸着機構３０
吸着機構３０は、固液分離機構２０で濾液として分離された液体成分が、固液分離機構２０から配管Ｐ２０ａを介して供給される。吸着機構３０は、イオン交換樹脂や多孔質物質などの吸着材が容器に充填されている。吸着機構３０において、固液分離機構２０で分離された濾液は、濾液に溶解している放射性核種が吸着材によって吸着される。 [A-3] Adsorption mechanism 30
The adsorption mechanism 30 is supplied with the liquid component separated as the filtrate by the solid-liquid separation mechanism 20 from the solid-liquid separation mechanism 20 via the pipe P20a. In the adsorption mechanism 30, a container is filled with an adsorbent such as an ion exchange resin or a porous material. In the adsorption mechanism 30, radionuclides dissolved in the filtrate separated by the solid-liquid separation mechanism 20 are adsorbed by an adsorbent.

［Ａ－４］回収機構４０
回収機構４０は、固液分離機構２０で濾物として分離された濃縮液が、固液分離機構２０から配管Ｐ２０ｂを介して供給される。回収機構４０は、固液分離機構２０において分離された濃縮液から液体成分を除去することによって固体成分を回収するために設けられている。 [A-4] Collection mechanism 40
The recovery mechanism 40 is supplied with the concentrated liquid separated as the filtrate by the solid-liquid separation mechanism 20 from the solid-liquid separation mechanism 20 via the pipe P20b. The recovery mechanism 40 is provided to recover the solid component by removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism 20 .

本実施形態では、回収機構４０は、加熱機構４１を有し、加熱機構４１を用いて濃縮液を加熱し、濃縮液に含まれる液体成分を蒸発させることによって、固体成分の回収を行うように構成されている。この他に、回収機構４０は、たとえば、沈降分離によって、濃縮液の固体成分を沈降させた後に、上澄み液を除去するように構成されていてもよい。回収された固体成分は、たとえば、ドラム缶などの廃棄物容器に充填され、保管される。 In this embodiment, the recovery mechanism 40 has a heating mechanism 41, and the heating mechanism 41 is used to heat the concentrated liquid to evaporate the liquid component contained in the concentrated liquid, thereby recovering the solid component. It is configured. Alternatively, the recovery mechanism 40 may be configured to sediment the solid components of the concentrate, for example by sedimentation, and then remove the supernatant. The collected solid components are filled in a waste container such as a drum can, for example, and stored.

［Ａ－５］回収液貯蔵部５０
回収液貯蔵部５０は、回収機構４０において濃縮液から除去された液体成分が、回収機構４０から配管Ｐ４０を介して回収液として供給される。回収液貯蔵部５０は、タンクを備えており、回収機構４０から供給された回収液を貯蔵する。回収液貯蔵部５０は、たとえば、回収機構４０において濃縮液の加熱で蒸発された蒸発成分が冷却されることで液化した液体成分を貯蔵する。この他に、回収機構４０において沈降分離によって濃縮液の固体成分を沈降させた場合には、沈降分離で生じた上澄み液を回収液貯蔵部５０が貯蔵してもよい。 [A-5] Recovery liquid storage unit 50
The liquid component removed from the concentrated liquid in the recovery mechanism 40 is supplied to the recovered liquid storage unit 50 as recovered liquid from the recovery mechanism 40 via the pipe P40. The recovered liquid storage unit 50 has a tank and stores the recovered liquid supplied from the recovery mechanism 40 . The recovered liquid storage unit 50 stores, for example, a liquid component that is liquefied by cooling the evaporated component that is evaporated by heating the concentrated liquid in the recovery mechanism 40 . In addition, when the solid component of the concentrate is sedimented by sedimentation in the recovery mechanism 40, the recovered liquid storage unit 50 may store the supernatant liquid generated by the sedimentation.

また、回収液貯蔵部５０は、配管Ｐ５０を介して、汚染懸濁液貯蔵部１０に連通するように構成されている。このため、回収機構４０において濃縮液から除去され、回収液貯蔵部５０で貯蔵された液体成分は、配管Ｐ５０を経由して、汚染懸濁液貯蔵部１０に戻される。汚染懸濁液貯蔵部１０に戻された液体成分は、汚染懸濁液貯蔵部１０に貯蔵された汚染懸濁液に混合され、上記したように、汚染懸濁液として汚染懸濁液処理装置を構成する各部において処理される。 Also, the recovered liquid storage unit 50 is configured to communicate with the contaminated suspension storage unit 10 via a pipe P50. Therefore, the liquid components removed from the concentrated liquid in the recovery mechanism 40 and stored in the recovered liquid storage section 50 are returned to the contaminated suspension storage section 10 via the pipe P50. The liquid component returned to the contaminated suspension reservoir 10 is mixed with the contaminated suspension stored in the contaminated suspension reservoir 10, and, as described above, the contaminated suspension treatment equipment is used as the contaminated suspension. are processed in each unit that constitutes the

なお、図示を省略しているが、各部への移送は、ポンプなどの機器を用いて実行される。 Although illustration is omitted, transfer to each part is performed using equipment such as a pump.

［Ｂ］まとめ
以上のように、本実施形態の汚染懸濁液処理装置では、汚染懸濁液よりも固体成分が濃縮された濃縮液と、汚染懸濁液から固体成分が除去された濾液とに、汚染懸濁液が固液分離機構２０で分離される。そして、固液分離機構２０で分離された濃縮液から液体成分を除去することによって、回収機構４０において固体成分が回収される。このため、本実施形態では、汚染懸濁液から固体成分を十分に除去可能であるので、放射性核種を除去する処理を効率的に実行することができる。また、吸着機構３０においては、固液分離機構２０で固体成分が除去された濾液について吸着処理を行うので、吸着性能を高めることができる。 [B] Summary As described above, in the contaminated suspension treatment apparatus of the present embodiment, the concentrated liquid in which the solid components are more concentrated than the contaminated suspension and the filtrate in which the solid components are removed from the contaminated suspension First, the contaminated suspension is separated in the solid-liquid separation mechanism 20 . By removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism 20 , the solid component is recovered by the recovery mechanism 40 . Therefore, in this embodiment, the solid components can be sufficiently removed from the contaminated suspension, so that the treatment for removing radionuclides can be performed efficiently. Further, in the adsorption mechanism 30, since the filtrate from which solid components have been removed by the solid-liquid separation mechanism 20 is subjected to adsorption treatment, the adsorption performance can be enhanced.

本実施形態の汚染懸濁液処理装置は、固液分離機構２０に供給する汚染懸濁液を貯蔵する汚染懸濁液貯蔵部１０を有し、回収機構４０において濃縮液から除去された液体成分を汚染懸濁液貯蔵部１０に戻すように構成されている。このため、濃縮液から除去された液体成分に含まれる放射性核種を、より確実に除去することができる。 The contaminated suspension treatment apparatus of this embodiment has a contaminated suspension storage unit 10 for storing the contaminated suspension to be supplied to the solid-liquid separation mechanism 20, and the liquid component removed from the concentrated liquid in the recovery mechanism 40. to the contaminated suspension reservoir 10. Therefore, the radionuclides contained in the liquid component removed from the concentrated liquid can be removed more reliably.

さらに、本実施形態では、回収機構４０は、加熱機構４１を有し、加熱機構４１を用いて濃縮液を加熱することによって固体成分の回収を行う。このため、本実施形態では、回収した固体成分の減容化を容易に実現することができる。 Furthermore, in the present embodiment, the recovery mechanism 40 has a heating mechanism 41, and the heating mechanism 41 is used to heat the concentrated liquid to recover the solid component. Therefore, in the present embodiment, volume reduction of the collected solid components can be easily realized.

［Ｃ］変形例
上記の実施形態では、固液分離機構２０の下流側に吸着機構３０が設けられている場合について説明しているが、これに限らない。固液分離機構２０の上流側に吸着機構３０が設けられていてもよい。この場合には、吸着機構３０に充填されている吸着材の微粉末を固液分離機構２０において固体成分として分離することができる。 [C] Modification In the above-described embodiment, the case where the adsorption mechanism 30 is provided downstream of the solid-liquid separation mechanism 20 is described, but the present invention is not limited to this. An adsorption mechanism 30 may be provided upstream of the solid-liquid separation mechanism 20 . In this case, the fine powder of the adsorbent filled in the adsorption mechanism 30 can be separated as a solid component in the solid-liquid separation mechanism 20 .

＜第２実施形態＞
図２は、第２実施形態に係る汚染懸濁液処理装置を模式的に示す図である。 <Second embodiment>
FIG. 2 is a diagram schematically showing a contaminated suspension treatment apparatus according to a second embodiment.

図２に示すように、本実施形態においては、回収機構４０と吸着材容器６０との間に配管Ｐ６０が介在している。この点、および、関連する点を除き、本実施形態は、第１実施形態の場合（図１参照）と同様である。このため、重複する事項に関しては適宜説明を省略する。 As shown in FIG. 2, a pipe P60 is interposed between the recovery mechanism 40 and the adsorbent container 60 in this embodiment. Except for this point and related points, this embodiment is the same as the case of the first embodiment (see FIG. 1). Therefore, descriptions of overlapping items will be omitted as appropriate.

本実施形態において、吸着材容器６０は、たとえば、吸着塔を構成しており、放射性核種を吸着した使用済みの吸着材が充填されている。放射性核種を吸着した使用済みの吸着材は、吸着材容器６０から配管Ｐ６０を経由して回収機構４０に移送される。 In this embodiment, the adsorbent container 60 constitutes, for example, an adsorption tower, and is filled with used adsorbents that have adsorbed radionuclides. The used adsorbent that has adsorbed radionuclides is transferred from the adsorbent container 60 to the recovery mechanism 40 via the pipe P60.

使用済みの吸着材に吸着された放射性核種は、崩壊熱を発している。このため、回収機構４０では、放射性核種の崩壊熱によって濃縮液が加熱され、濃縮液に含まれる液体成分が蒸発する。このように、本実施形態では、使用済みの吸着材を活用することで、濃縮液に含まれる固体成分の回収を効率的に実行可能である。 Radionuclides adsorbed on the spent adsorbent emit decay heat. Therefore, in the recovery mechanism 40, the concentrated liquid is heated by the decay heat of the radionuclide, and the liquid component contained in the concentrated liquid is evaporated. Thus, in this embodiment, by utilizing the used adsorbent, it is possible to efficiently recover the solid components contained in the concentrate.

＜第３実施形態＞
図３は、第３実施形態に係る汚染懸濁液処理装置を模式的に示す図である。 <Third Embodiment>
FIG. 3 is a diagram schematically showing a contaminated suspension treatment apparatus according to a third embodiment.

図３に示すように、本実施形態においては、回収機構４０と吸着材容器６０との間には、配管Ｐ４０ｂが介在している。この点、および、関連する点を除き、本実施形態は、第２実施形態の場合（図２参照）と同様である。このため、重複する事項に関しては適宜説明を省略する。 As shown in FIG. 3, a pipe P40b is interposed between the recovery mechanism 40 and the adsorbent container 60 in this embodiment. Except for this point and related points, this embodiment is the same as the case of the second embodiment (see FIG. 2). Therefore, descriptions of overlapping items will be omitted as appropriate.

本実施形態においては、回収機構４０に供給された濃縮液が回収機構４０から配管Ｐ４０ｂを経由して吸着材容器６０に移送される。吸着材容器６０に充填されている吸着材は、使用済みであって、放射性核種を吸着しており、放射性核種が崩壊熱を発している。このため、吸着材容器６０では、放射性核種の崩壊熱によって濃縮液が加熱され、濃縮液に含まれる液体成分が蒸発する。このように、本実施形態では、使用済みの吸着材を活用することで、濃縮液に含まれる固体成分に付着している放射性核種が、吸着材容器６０において回収され、保管可能である。 In this embodiment, the concentrated liquid supplied to the recovery mechanism 40 is transferred from the recovery mechanism 40 to the adsorbent container 60 via the pipe P40b. The adsorbent filled in the adsorbent container 60 has been used, adsorbs radionuclides, and the radionuclides generate decay heat. Therefore, in the adsorbent container 60, the concentrated liquid is heated by the decay heat of the radionuclide, and the liquid component contained in the concentrated liquid is evaporated. Thus, in this embodiment, by utilizing the used adsorbent, radionuclides adhering to the solid components contained in the concentrated liquid can be recovered and stored in the adsorbent container 60.

＜その他＞
なお、本発明は上述した実施形態そのままに限定されるものではなく、実施段階では、上述した実施例以外にも様々な形態で実施することができる。本発明は、発明の要旨を逸脱しない範囲で、種々の省略、追加、置き換え、変更を行うことができる。これら実施形態やその変形は、発明の範囲や要旨に含まれるとともに、特許請求の範囲に記載された発明とその均等の範囲に含まれる。 <Others>
It should be noted that the present invention is not limited to the above-described embodiment as it is, and in the implementation stage, it can be implemented in various forms other than the above-described embodiment. Various omissions, additions, replacements, and modifications can be made to the present invention without departing from the gist of the invention. These embodiments and modifications thereof are included in the scope and gist of the invention, and are included in the scope of the invention described in the claims and equivalents thereof.

１０…汚染懸濁液貯蔵部、２０…固液分離機構、３０…吸着機構、４０…回収機構、４１…加熱機構、５０…回収液貯蔵部、６０…吸着材容器、Ｐ１０…配管、Ｐ２０ａ…配管、Ｐ２０ｂ…配管、Ｐ４０…配管、Ｐ４０ｂ…配管、Ｐ５０…配管、Ｐ６０…配管 DESCRIPTION OF SYMBOLS 10... Contamination suspension storage part 20... Solid-liquid separation mechanism 30... Adsorption mechanism 40... Recovery mechanism 41... Heating mechanism 50... Recovered liquid storage part 60... Adsorbent container P10... Piping P20a... Piping, P20b...Piping, P40...Piping, P40b...Piping, P50...Piping, P60...Piping

Claims (4)

放射性核種を含む汚染懸濁液を処理する汚染懸濁液処理装置であって、
前記汚染懸濁液よりも固体成分が濃縮された濃縮液と、前記汚染懸濁液から固体成分が除去された濾液とに、前記汚染懸濁液を分離する固液分離機構と、
前記固液分離機構において分離された前記濃縮液から液体成分を除去することによって前記固体成分を回収する回収機構と、
前記固液分離機構に供給する前記汚染懸濁液を貯蔵する貯蔵部と
を有し、
前記回収機構において前記濃縮液から除去された液体成分を前記貯蔵部に戻すように構成されている、
汚染懸濁液処理装置。 A contaminated suspension processing apparatus for processing a contaminated suspension containing a radionuclide,
a solid-liquid separation mechanism for separating the contaminated suspension into a concentrated liquid in which the solid components are more concentrated than the contaminated suspension and a filtrate in which the solid components are removed from the contaminated suspension;
a recovery mechanism for recovering the solid component by removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism ;
a storage unit for storing the contaminated suspension to be supplied to the solid-liquid separation mechanism;
has
configured to return liquid components removed from the concentrate in the recovery mechanism to the reservoir ;
Contamination suspension treatment equipment. 前記回収機構は、加熱機構を有し、前記加熱機構を用いて前記濃縮液を加熱することによって前記固体成分の回収を行うとともに、加熱時の蒸気成分を前記貯蔵部に戻すように構成されている、
請求項１に記載の汚染懸濁液処理装置。 The recovery mechanism has a heating mechanism, and is configured to recover the solid component by heating the concentrated liquid using the heating mechanism, and to return the vapor component during heating to the storage unit. there is
A contaminated suspension treatment apparatus according to claim 1 . 放射性核種を含む汚染懸濁液を処理する汚染懸濁液処理装置であって、
前記汚染懸濁液よりも固体成分が濃縮された濃縮液と、前記汚染懸濁液から固体成分が除去された濾液とに、前記汚染懸濁液を分離する固液分離機構と、
前記固液分離機構において分離された前記濃縮液から液体成分を除去することによって前記固体成分を回収する回収機構と
を備え、
放射性核種を吸着した吸着材が充填されている吸着剤容器から前記吸着材を前記回収機構に移送するように構成されている、
汚染懸濁液処理装置。 A contaminated suspension processing apparatus for processing a contaminated suspension containing a radionuclide,
a solid-liquid separation mechanism for separating the contaminated suspension into a concentrated liquid in which the solid components are more concentrated than the contaminated suspension and a filtrate in which the solid components are removed from the contaminated suspension;
a recovery mechanism for recovering the solid component by removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism;
with
configured to transfer the adsorbent from the adsorbent container filled with the adsorbent that adsorbs the radionuclide to the recovery mechanism,
Contamination suspension treatment equipment. 放射性核種を含む汚染懸濁液を処理する汚染懸濁液処理装置であって、
前記汚染懸濁液よりも固体成分が濃縮された濃縮液と、前記汚染懸濁液から固体成分が除去された濾液とに、前記汚染懸濁液を分離する固液分離機構と、
前記固液分離機構において分離された前記濃縮液から液体成分を除去することによって前記固体成分を回収する回収機構と
を備え、
放射性核種を吸着した吸着材が充填されている吸着剤容器に前記濃縮液を移送するように構成されている、
汚染懸濁液処理装置。 A contaminated suspension processing apparatus for processing a contaminated suspension containing a radionuclide,
a solid-liquid separation mechanism for separating the contaminated suspension into a concentrated liquid in which the solid components are more concentrated than the contaminated suspension and a filtrate in which the solid components are removed from the contaminated suspension;
a recovery mechanism for recovering the solid component by removing the liquid component from the concentrated liquid separated by the solid-liquid separation mechanism;
with
configured to transfer the concentrated liquid to an adsorbent container filled with an adsorbent that adsorbs a radionuclide;
Contamination suspension treatment equipment.
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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013186025A (en) 2012-03-09 2013-09-19 Hitachi-Ge Nuclear Energy Ltd Treatment apparatus and treatment method of decontamination waste liquid
JP2014071025A (en) 2012-09-28 2014-04-21 Toshiba Corp Solid-liquid separation method and solid-liquid separation device
JP2016017798A (en) 2014-07-07 2016-02-01 株式会社タクマ Apparatus and method for treating fly ash
JP2016223905A (en) 2015-05-29 2016-12-28 株式会社東芝 Radioactive liquid effluent processor and processing method thereof
JP2019060731A (en) 2017-09-27 2019-04-18 日立Ｇｅニュークリア・エナジー株式会社 Contaminated water treatment equipment, and operation method of contaminated water treatment equipment

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5495062A (en) * 1994-09-12 1996-02-27 Commodore Laboratories, Inc. Methods of decontaminating nuclear waste-containing soil

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013186025A (en) 2012-03-09 2013-09-19 Hitachi-Ge Nuclear Energy Ltd Treatment apparatus and treatment method of decontamination waste liquid
JP2014071025A (en) 2012-09-28 2014-04-21 Toshiba Corp Solid-liquid separation method and solid-liquid separation device
JP2016017798A (en) 2014-07-07 2016-02-01 株式会社タクマ Apparatus and method for treating fly ash
JP2016223905A (en) 2015-05-29 2016-12-28 株式会社東芝 Radioactive liquid effluent processor and processing method thereof
JP2019060731A (en) 2017-09-27 2019-04-18 日立Ｇｅニュークリア・エナジー株式会社 Contaminated water treatment equipment, and operation method of contaminated water treatment equipment

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