JP2000009892A - Iodine removal device of turbine system of atomic power station - Google Patents
Iodine removal device of turbine system of atomic power stationInfo
- Publication number
- JP2000009892A JP2000009892A JP10181720A JP18172098A JP2000009892A JP 2000009892 A JP2000009892 A JP 2000009892A JP 10181720 A JP10181720 A JP 10181720A JP 18172098 A JP18172098 A JP 18172098A JP 2000009892 A JP2000009892 A JP 2000009892A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive iodine
- vacuum pump
- turbine
- condenser
- iodine
- 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.)
- Pending
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- Measurement Of Radiation (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は原子力発電プラント
の運転停止時等に発生するヨウ素の回収と除去を行うた
めの原子力発電所のタービン系ヨウ素除去装置に関す
る。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an apparatus for removing iodine in a turbine of a nuclear power plant for recovering and removing iodine generated when the operation of a nuclear power plant is stopped or the like.
【０００２】[0002]
【従来の技術】原子力発電所では放出放射能を安全に処
理し、低減化することを目的として気体廃棄物処理設備
を設置している。すなわち、図７に示したように原子炉
建屋１内の原子炉２とタービン建屋３内のタービン４と
を主蒸気管５により接続し、タービン４に設けた主復水
器６の下流側に、空気抽出器７，再結合器８，除湿乾燥
器９，活性炭ホールドアップ塔10，排出装置11および排
気筒12を順次直列接続した気体廃棄物処理設備を設置し
ている。2. Description of the Related Art At a nuclear power plant, a gas waste treatment facility is installed for the purpose of safely treating and reducing emitted radioactivity. That is, as shown in FIG. 7, the reactor 2 in the reactor building 1 and the turbine 4 in the turbine building 3 are connected by the main steam pipe 5, and on the downstream side of the main condenser 6 provided in the turbine 4. A gas waste treatment facility in which an air extractor 7, a recombiner 8, a dehumidifier / dryer 9, an activated carbon hold-up tower 10, a discharge device 11, and an exhaust pipe 12 are sequentially connected in series is installed.
【０００３】ここで、タービン４には原子炉２から主蒸
気管５を通して(1) 核分裂ガス（Ｘｅ，Ｋｒ等）、(2)
炉内で放射化される気体（Ｎ16，Ｏ19等）、(3) 放射性
粒子状物質、(4) 炉水の放射線分解により発生するＨ2
およびＯ2 、(5) タービン，復水器に漏入する空気、
(6) 主蒸気，空気抽出器駆動用蒸気が流入する。Here, the turbine 4 passes through the main steam pipe 5 from the nuclear reactor 2 (1) fission gas (Xe, Kr, etc.), (2)
Gas emitted reduction in a furnace (N 16, O 19, etc.), (3) Radioactive particulate matter, H 2 generated by radiolysis of (4) reactor water
And O 2 , (5) air leaking into turbines and condensers,
(6) Main steam and steam for driving the air extractor flow in.
【０００４】また、放射性気体廃棄物中に含まれるヨウ
素はオフガス中でも無機，有機の化学系が存在し、複雑
な挙動をとるが、ヨウ素の捕集にはアルカリ洗浄，活性
炭，ゼオライト等の吸着剤が用いられる。[0004] In addition, iodine contained in radioactive gas waste has an inorganic or organic chemical system even in off-gas and has a complicated behavior. However, iodine is trapped by an adsorbent such as alkali washing, activated carbon and zeolite. Is used.
【０００５】[0005]
【発明が解決しようとする課題】原子力発電プラントの
運転停止時にタービン系統内に存在する放射性ヨウ素を
除去するには系統の部分的な開放を行い、仮設ポンプお
よび仮設フィルタを別途設置している。To remove radioactive iodine present in the turbine system when the operation of the nuclear power plant is stopped, the system is partially opened, and a temporary pump and a temporary filter are separately installed.
【０００６】しかしながら、原子力発電プラントの起動
時においては、タービン系統の部分的な開放を行うこと
ができないため、タービン系統に放射性ヨウ素が存在し
た場合、その除去は困難である。However, when the nuclear power plant is started, it is difficult to partially open the turbine system, so that if radioactive iodine exists in the turbine system, it is difficult to remove it.
【０００７】また、原子力発電プラントの停止時におい
ては、タービン系統の部分的な開放が必要であるため、
短時間での放射性ヨウ素の除去は困難であり、さらに放
射性ヨウ素をタービン系統外に放出してしまう課題があ
る。Further, when the nuclear power plant is stopped, it is necessary to partially open the turbine system.
It is difficult to remove radioactive iodine in a short time, and there is a problem that radioactive iodine is released outside the turbine system.
【０００８】本発明は上記課題を解決するためになされ
たもので、原子力発電プラントの運転停止時，中間停止
時等短期停止後の起動時の原子力発電プラント内の放射
性ヨウ素の回収と除去を行うことができる原子力発電所
のタービン系ヨウ素除去装置を提供することにある。SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and performs recovery and removal of radioactive iodine in a nuclear power plant when the nuclear power plant is started after a short-term stop such as an operation stop or an intermediate stop. It is an object of the present invention to provide a turbine-based iodine removal apparatus for a nuclear power plant.
【０００９】また、本発明は原子力発電プラントの停止
後においてはタービン系統内に存在する放射性ヨウ素を
タービン系統を開放することなく、短時間で除去して放
射性ヨウ素のタービン系統外への放出を防止することが
できる原子力発電所のタービン系ヨウ素除去装置を提供
することにある。Further, the present invention removes radioactive iodine existing in the turbine system in a short time after the nuclear power plant is shut down without opening the turbine system, thereby preventing the release of radioactive iodine out of the turbine system. It is an object of the present invention to provide an apparatus for removing iodine in a turbine of a nuclear power plant.
【００１０】[0010]
【課題を解決するための手段】請求項１の発明は、原子
炉からタービンまでの主蒸気系統の主復水器の下流に位
置し、復水器真空ポンプを含む前記主復水器からタービ
ン建屋外に設置した排気筒までの復水器真空ポンプ系統
に、加熱器と活性炭フィルタを直列接続してなることを
特徴とする。SUMMARY OF THE INVENTION According to the present invention, there is provided a main steam turbine from a reactor to a turbine located downstream of a main condenser and including a condenser vacuum pump. The heater and the activated carbon filter are connected in series to the condenser vacuum pump system up to the exhaust pipe installed outside the building.
【００１１】請求項１の発明によれば、復水器真空ポン
プ系統に放射性ヨウ素を含み復水器真空ポンプにより送
出された流体が流れると、加熱器によって加熱すること
により湿分を除去し、さらに活性炭フィルタにより放射
性ヨウ素を除去することができる。According to the first aspect of the present invention, when a fluid containing radioactive iodine and flowing out of the condenser vacuum pump flows through the condenser vacuum pump system, moisture is removed by heating with the heater, Furthermore, radioactive iodine can be removed by an activated carbon filter.
【００１２】請求項２の発明は、前記復水器真空ポンプ
系統に平行してバイパス系統を設け、このバイパス系統
に前記加熱器と活性炭フィルタを設置するとともに、前
記復水器真空ポンプ系と前記バイパス系統の分岐部に切
替器を設けることを特徴とする。According to a second aspect of the present invention, a bypass system is provided in parallel with the condenser vacuum pump system, and the heater and the activated carbon filter are installed in the bypass system. A switch is provided at a branch of the bypass system.
【００１３】請求項２の発明によれば、必要がある場
合、切替器を使って系統をバイパス系統に切り替え、バ
イパス系統に放射能を含み復水器真空ポンプにより送出
された流体が流れると、加熱器によって加熱することに
より湿分を除去し、さらに活性炭フィルタにより放射性
ヨウ素を除去する。必要がない場合、切替器を使って復
水器真空ポンプ系統に切り替えることにより、加熱器お
よび活性炭フィルタを通過しない系統を選択できる。According to the second aspect of the present invention, if necessary, the system is switched to the bypass system by using the switch, and when the bypass system contains radioactivity and the fluid sent out by the condenser vacuum pump flows, Moisture is removed by heating with a heater, and radioactive iodine is further removed with an activated carbon filter. If it is not necessary, the system that does not pass through the heater and the activated carbon filter can be selected by switching to the condenser vacuum pump system using the switch.
【００１４】請求項３の発明は、前記切替器の上流側に
放射性ヨウ素検出器を設け、この検出器と前記切替器に
接続する記憶手段を設けてなることを特徴とする。請求
項３の発明によれば、タービン系統内の放射性ヨウ素の
濃度を測定する検出器からの信号が記憶手段に入力さ
れ、記憶手段は放射性ヨウ素の濃度に応じた切り替え量
を出力する。切替器は記憶手段からの信号により切り替
え量を制御する。A third aspect of the present invention is characterized in that a radioactive iodine detector is provided on the upstream side of the switch, and storage means for connecting the detector and the switch is provided. According to the invention of claim 3, a signal from a detector for measuring the concentration of radioactive iodine in the turbine system is input to the storage unit, and the storage unit outputs a switching amount according to the concentration of radioactive iodine. The switch controls the amount of switching by a signal from the storage means.
【００１５】請求項４の発明は、前記加熱器の上流側に
流量調整器を設けるか、またはこの流量調整弁の上流側
に放射性ヨウ素検出器を設け、この検出器と前記流量調
整弁に記憶手段を接続してなることを特徴とする。According to a fourth aspect of the present invention, a flow controller is provided upstream of the heater or a radioactive iodine detector is provided upstream of the flow control valve, and the radioactive iodine detector is stored in the detector and the flow control valve. It is characterized by connecting means.
【００１６】請求項４の発明によれば、タービン系統に
放射性ヨウ素を含み復水器真空ポンプにより送出された
流体が流れた場合、必要により流量調整器を使って流量
を制御した後、加熱器によって加熱することにより湿分
を除去し、さらに活性炭フィルタにより放射性ヨウ素を
除去する。According to the fourth aspect of the present invention, when the fluid containing radioactive iodine and sent out by the condenser vacuum pump flows into the turbine system, the flow rate is controlled using a flow rate regulator as necessary, and then the heater is heated. To remove the moisture, and further remove the radioactive iodine with an activated carbon filter.
【００１７】請求項５の発明は、前記活性炭フィルタの
下流側に前記放射性ヨウ素検出器と自動開閉弁を直列接
続してなることを特徴とする。請求項５の発明によれ
ば、タービン系統に放射性ヨウ素を含み復水器真空ポン
プにより送出された気体が流れると、加熱器によって加
熱することにより湿分を除去し、さらに活性炭フィルタ
により放射性ヨウ素を除去する。その後、放射性ヨウ素
検出器によって放射性ヨウ素の濃度を検出し、自動開閉
弁が放射性ヨウ素の濃度に応じ系統の開閉を行う。The invention of claim 5 is characterized in that the radioactive iodine detector and an automatic on-off valve are connected in series downstream of the activated carbon filter. According to the invention of claim 5, when the gas containing radioactive iodine and flowing out of the condenser vacuum pump flows into the turbine system, the heater is used to remove moisture by heating, and further, the radioactive iodine is removed by the activated carbon filter. Remove. Thereafter, the concentration of radioactive iodine is detected by a radioactive iodine detector, and an automatic opening / closing valve opens and closes the system according to the concentration of radioactive iodine.
【００１８】[0018]
【発明の実施の形態】図１により請求項１に対応する発
明に係る原子力発電所のタービン系ヨウ素除去装置の第
１の実施の形態を説明する。なお、図１中、図７と同一
部分には同一符号を付して重複する部分の説明は省略す
る。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention will be described with reference to FIG. In FIG. 1, the same portions as those in FIG. 7 are denoted by the same reference numerals, and the description of the overlapping portions will be omitted.
【００１９】図１中、符号13は復水器真空ポンプ系統
で、この復水器真空ポンプ系統には主復水器６から排気
筒12までの間に復水器ポンプ14，ウォータセパレータ15
および加熱器16と活性炭フィルタ17がバイパス系統18に
接続して設置されている。なお、図１中符号19は給水管
である。In FIG. 1, reference numeral 13 denotes a condenser vacuum pump system. The condenser vacuum pump system includes a condenser pump 14 and a water separator 15 between the main condenser 6 and the exhaust pipe 12.
A heater 16 and an activated carbon filter 17 are connected to a bypass system 18 and installed. In addition, the code | symbol 19 in FIG. 1 is a water supply pipe.
【００２０】しかして、原子炉運転中は原子炉２から主
蒸気管５を通ってタービン（図示せず）へ蒸気が送り込
まれ、タービンで仕事を終えた蒸気は主復水器で凝縮さ
れて復水となる。原子炉運転停止時には真空破壊を行っ
た後、復水器ポンプ14を起動し、主蒸気管５内系統の空
気を吸引し、吸引空気を主復水器６から復水器真空ポン
プ14により送出し、ウォータセパレータ15で気水分離す
る。During operation of the reactor, steam is sent from the reactor 2 through the main steam pipe 5 to a turbine (not shown), and the steam that has completed its work in the turbine is condensed in the main condenser. It will be condensed. When the reactor is shut down, the vacuum is broken, the condenser pump 14 is started, the air in the main steam pipe 5 is sucked, and the suction air is sent out from the main condenser 6 by the condenser vacuum pump 14. Then, water and water are separated by the water separator 15.
【００２１】分離された気相は加熱器16で加熱されて湿
度が減少し、活性炭フィルタ17で含まれている放射性ヨ
ウ素を吸着し、放射能が除去されて無害となった系統流
体は排気筒12から排気される。The separated gas phase is heated by the heater 16 to reduce the humidity, adsorbs the radioactive iodine contained in the activated carbon filter 17, and the harmless system fluid from which the radioactivity has been removed is discharged into an exhaust pipe. Exhausted from 12.
【００２２】本実施の形態によれば、流体に放射性ヨウ
素が含まれた場合、復水器真空ポンプ系統13に本設とし
て加熱器16と活性炭フィルタ17を設置したことにより、
プラントの起動時に系統内を流れる流体中の放射性ヨウ
素を除去でき、プラントの停止時には系統の開放，仮設
ポンプや仮設フィルタの設置を必要とせずに、短時間で
系統内を流れる流体中の放射性ヨウ素を除去することが
できる。According to the present embodiment, when the radioactive iodine is contained in the fluid, the heater 16 and the activated carbon filter 17 are installed in the condenser vacuum pump system 13 as a main unit.
Radioactive iodine in the fluid flowing in the system can be removed when the plant is started, and radioactive iodine in the fluid flowing in the system can be removed in a short time without shutting down the system and installing a temporary pump or temporary filter when the plant is stopped. Can be removed.
【００２３】次に図２により請求項２に対応する発明の
第２の実施の形態を説明する。本実施の形態は、プラン
トの復水器の下流に位置する復水器真空ポンプ系統13に
並行に設置されたバイパス系統18と系統内の流体の流れ
を復水器真空ポンプ系統13，またはバイパス系統18に分
岐する切替器20とバイパス系統18内の流体を加熱する加
熱器16と、系統内を流れる流体中の放射性ヨウ素を除去
する活性炭フィルタ17とから構成されている。Next, a second embodiment of the present invention will be described with reference to FIG. In the present embodiment, a bypass system 18 installed in parallel with a condenser vacuum pump system 13 located downstream of a condenser of a plant and a flow of fluid in the system are condensed by a condenser vacuum pump system 13 or a bypass system. The system includes a switch 20 that branches into a system 18, a heater 16 that heats the fluid in the bypass system 18, and an activated carbon filter 17 that removes radioactive iodine in the fluid flowing in the system.
【００２４】次に、通常時の動作を説明する。原子炉２
の主蒸気管５系統の主復水器６の下流に位置する復水器
真空ポンプ系統13の分岐部から上流を流れる流体中に放
射性ヨウ素が含まれていない場合、復水器真空ポンプ系
統13とバイパス系統18との分岐部に設置されている切替
器20を復水器真空ポンプ13に切り替えることにより流体
は復水器真空ポンプ系統13に導かれる。Next, the normal operation will be described. Reactor 2
When radioactive iodine is not contained in the fluid flowing upstream from the branch of the condenser vacuum pump system 13 located downstream of the main condenser 6 of the main steam pipe 5 The fluid is guided to the condenser vacuum pump system 13 by switching the switch 20 provided at the branch portion between the condenser and the bypass system 18 to the condenser vacuum pump 13.
【００２５】復水器真空ポンプ系統13の分岐部から上流
を流れる流体中に放射性ヨウ素が含まれる場合、復水器
真空ポンプ系統13とバイパス系統18との分岐部に設置さ
れている切替器20を副系統に切り替えることにより流体
はバイパス系統18に導かれ、バイパス系統18に設置され
ている加熱器16によって加熱され、湿度を減少し、活性
炭フィルタ17で流体中に含まれている放射性ヨウ素を吸
着させる。When radioactive iodine is contained in the fluid flowing upstream from the branch of the condenser vacuum pump system 13, the switch 20 installed at the branch between the condenser vacuum pump system 13 and the bypass system 18 is provided. By switching to the sub-system, the fluid is guided to the bypass system 18, is heated by the heater 16 installed in the bypass system 18, reduces the humidity, and removes the radioactive iodine contained in the fluid by the activated carbon filter 17. Adsorb.
【００２６】本実施の形態によれば、流体が流れる系統
は、切替器20により復水器真空ポンプ系統13とバイパス
系統18に切り替えることにより、放射性ヨウ素が含まれ
た流体を選択的にバイパス系統18に流すことができ、活
性炭フィルタ17の寿命を延ばすことができる。According to the present embodiment, the system through which the fluid flows is switched to the condenser vacuum pump system 13 and the bypass system 18 by the switch 20 so that the fluid containing radioactive iodine can be selectively bypassed. 18 and the life of the activated carbon filter 17 can be extended.
【００２７】次に図３により請求項３に対応する発明の
第３の実施の形態を説明する。本実施の形態は、第２の
実施の形態において、実施の形態の切替器20の上流に設
置された系統流体中の放射性ヨウ素の濃度を測定する放
射性ヨウ素検出器21と、この検出器21と切替器20とに電
気的に接続され、放射性ヨウ素の濃度に応じた切り替え
量を予め記憶している記憶手段22を設けたことにある。Next, a third embodiment of the present invention will be described with reference to FIG. This embodiment is different from the second embodiment in that a radioactive iodine detector 21 that measures the concentration of radioactive iodine in a system fluid installed upstream of the switch 20 of the embodiment, The storage means 22 is provided which is electrically connected to the switch 20 and stores in advance the switching amount according to the concentration of radioactive iodine.
【００２８】次に、通常時の動作を説明する。系統流体
の放射能濃度は検出器21によって測定され、測定結果は
検出器21と電気的に接続されている記憶手段22に伝送さ
れ、記憶手段22は入力された放射性ヨウ素の濃度に応じ
た切り替え量を、やはり電気的に接続された切替器20に
伝送する。Next, the normal operation will be described. The radioactivity concentration of the system fluid is measured by the detector 21, and the measurement result is transmitted to the storage means 22 electrically connected to the detector 21, and the storage means 22 is switched according to the concentration of the radioactive iodine inputted. The quantity is transmitted to a switch 20, also electrically connected.
【００２９】切替器20は入力された切り替え量に反応
し、復水器真空ポンプ系統13とバイパス系統18に流れる
流体の量を調整するので、活性炭フィルタ17を最も効率
良く利用できる。また、系統流体中の放射性ヨウ素の濃
度が上昇した場合、切替器20が切り替え量を自動調整す
るので、放射性ヨウ素の環境への放出を防ぐことができ
る。The switch 20 adjusts the amount of fluid flowing through the condenser vacuum pump system 13 and the bypass system 18 in response to the input switching amount, so that the activated carbon filter 17 can be used most efficiently. Further, when the concentration of radioactive iodine in the system fluid increases, the switch 20 automatically adjusts the switching amount, so that the release of radioactive iodine into the environment can be prevented.
【００３０】次に図４により請求項４に対応する発明の
第４の実施の形態を説明する。本実施の形態は、原子炉
の主蒸気系統の主復水器の下流に位置する復水器真空ポ
ンプ系統13と、この復水器真空ポンプ系統13内の流体の
流量を調整する流量調整器23と、復水器真空ポンプ系統
内の流体を加熱する加熱器16と、系統流体中の放射性ヨ
ウ素を除去する活性炭フィルタ17を設けたことにある。Next, a fourth embodiment of the present invention will be described with reference to FIG. This embodiment includes a condenser vacuum pump system 13 located downstream of a main condenser of a main steam system of a nuclear reactor, and a flow regulator for adjusting a flow rate of a fluid in the condenser vacuum pump system 13. 23, a heater 16 for heating the fluid in the condenser vacuum pump system, and an activated carbon filter 17 for removing radioactive iodine in the system fluid.
【００３１】次に、通常時の動作を説明する。原子炉の
主蒸気系統の主復水器の下流に位置する復水器真空ポン
プ系統13内の放射性ヨウ素が含まれた流体は復水器真空
ポンプにより送出される。そして復水器真空ポンプ系統
13に設置されている流量調整器23によって流量を調整さ
れ、加熱器16によって加熱され、湿度を減少し、活性炭
フィルタ17で含んでいる放射性ヨウ素を吸着させ除去す
る。Next, the normal operation will be described. The fluid containing radioactive iodine in the condenser vacuum pump system 13 located downstream of the main condenser of the main steam system of the nuclear reactor is sent out by the condenser vacuum pump. And condenser vacuum pump system
The flow rate is adjusted by a flow rate adjuster 23 installed in 13, the flow rate is adjusted by a heater 16, the humidity is reduced, and the radioactive iodine contained in the activated carbon filter 17 is adsorbed and removed.
【００３２】本実施の形態によれば、復水器真空ポンプ
系統を流れる放射性ヨウ素を含んだ流体の流量を調整す
ることにより加熱器による流体の加熱、活性炭フィルタ
による放射性ヨウ素の捕集効率を上げることができる。According to this embodiment, the flow rate of the fluid containing radioactive iodine flowing through the condenser vacuum pump system is adjusted to increase the heating of the fluid by the heater and the collection efficiency of radioactive iodine by the activated carbon filter. be able to.
【００３３】次に図５により第５の実施の形態を説明す
る。本実施の形態は第４の実施の形態において、流量調
整器４の上流に系統流体中の放射性ヨウ素の濃度を測定
する放射性ヨウ素検出器21と、この検出器21と流量調整
器23とに電気的に接続され、放射性ヨウ素の濃度に応じ
た流量調整量を予め記憶している記憶手段22を設けたこ
とにある。Next, a fifth embodiment will be described with reference to FIG. This embodiment is different from the fourth embodiment in that a radioactive iodine detector 21 for measuring the concentration of radioactive iodine in a system fluid is provided upstream of the flow controller 4, and the detector 21 and the flow controller 23 are electrically connected. The storage means 22 is connected to the storage means and stores in advance a flow rate adjustment amount corresponding to the concentration of radioactive iodine.
【００３４】次に、通常時の動作を説明する。復水器真
空ポンプ系統13の放射性ヨウ素の濃度は検出器21によっ
て測定され、測定結果は検出器21と電気的に接続されて
いる記憶手段22に伝送され、記憶手段22は入力された放
射能濃度に応じた流量調整量を、やはり電気的に接続さ
れた流量調整器23に伝送する。流量調整器23は入力され
た流量調整量に反応し、復水器真空ポンプ系統13に流れ
る流体の流量を調整する。Next, the normal operation will be described. The concentration of radioactive iodine in the condenser vacuum pump system 13 is measured by a detector 21, and the measurement result is transmitted to a storage unit 22 electrically connected to the detector 21, and the storage unit 22 stores the input radioactivity. The flow rate adjustment amount corresponding to the concentration is transmitted to the flow rate regulator 23 which is also electrically connected. The flow controller 23 adjusts the flow rate of the fluid flowing through the condenser vacuum pump system 13 in response to the input flow control amount.
【００３５】本実施の形態によれば、流量調整器23が放
射性ヨウ素の濃度に応じて自動的に復水器真空ポンプ系
統13に流れる流体の量を調整するので、加熱器16による
流体の加熱，活性炭フィルタ17による放射能の捕集の効
率を最適化できる。According to the present embodiment, the flow controller 23 automatically adjusts the amount of fluid flowing through the condenser vacuum pump system 13 in accordance with the concentration of radioactive iodine. In addition, the efficiency of collecting radioactivity by the activated carbon filter 17 can be optimized.
【００３６】次に図６により請求項５に対応する第６の
実施の形態を説明する。本実施の形態は、原子炉の主蒸
気系統の主復水器の下流に位置する復水器真空ポンプ系
統13と、この復水器真空ポンプ系統13内の流体を加熱す
る加熱器16と、系統流体中の放射性ヨウ素を除去する活
性炭フィルタ17と、この活性炭フィルタ17の下流に設置
された系統流体中の放射性ヨウ素の濃度を測定する放射
性ヨウ素検出器21と、この検出器21の下流に設置され、
電気的に信号線25により接続された系統の開閉を制御す
る自動開閉弁24とから構成されている。Next, a sixth embodiment of the present invention will be described with reference to FIG. This embodiment includes a condenser vacuum pump system 13 located downstream of the main condenser of the main steam system of the reactor, a heater 16 for heating the fluid in the condenser vacuum pump system 13, An activated carbon filter 17 for removing radioactive iodine in the system fluid, a radioactive iodine detector 21 for measuring the concentration of radioactive iodine in the system fluid installed downstream of the activated carbon filter 17, and installed downstream of the detector 21 And
An automatic on-off valve 24 for controlling opening and closing of a system electrically connected by a signal line 25 is provided.
【００３７】次に、通常時の動作を説明する。原子炉の
主蒸気系統の主復水器の下流に位置する復水器真空ポン
プ系統13内の放射性ヨウ素が含まれた流体は復水器真空
ポンプにより送出され、加熱器16によって加熱され、湿
度を減少し、活性炭フィルタ17で含んでいる放射性ヨウ
素を吸着させる。Next, the normal operation will be described. The fluid containing radioactive iodine in the condenser vacuum pump system 13 located downstream of the main condenser of the main steam system of the nuclear reactor is sent out by the condenser vacuum pump, heated by the heater 16, And the radioactive iodine contained in the activated carbon filter 17 is adsorbed.
【００３８】さらに、活性炭フィルタ17の下流に設置さ
れた検出器21で放射性ヨウ素除去後の流体の放射能濃度
を再確認し、放射性ヨウ素濃度が規定値より高い場合、
電気的に接続された系統の開閉を自動開閉弁24が系統を
閉止する。Further, the radioactivity concentration of the fluid after the removal of radioactive iodine is reconfirmed by the detector 21 installed downstream of the activated carbon filter 17, and if the radioactive iodine concentration is higher than the specified value,
The automatic open / close valve 24 closes the system to open and close the electrically connected system.
【００３９】本実施の形態によれば、復水器真空ポンプ
系統の活性炭フィルタを通過した流体の放射性ヨウ素の
濃度が高い場合、自動開閉弁24により系統が自動的に閉
止され放射性ヨウ素の環境への放出を避けることができ
る。また、自動開閉弁24の手前に位置する検出器21で放
射性ヨウ素の濃度の変化を測定することによって、活性
炭フィルタの交換時期を知ることができる。According to the present embodiment, when the concentration of radioactive iodine in the fluid that has passed through the activated carbon filter of the condenser vacuum pump system is high, the system is automatically closed by the automatic on-off valve 24 and the environment of radioactive iodine is reduced. Release can be avoided. Further, by measuring the change in the concentration of the radioactive iodine with the detector 21 located in front of the automatic opening / closing valve 24, it is possible to know the replacement time of the activated carbon filter.
【００４０】[0040]
【発明の効果】本発明によれば、原子力発電プラントの
系統に設置することにより、プラントの起動時に放射性
ヨウ素の環境への放出を防ぐことができる。また、プラ
ントの停止時には系統を開放することなく、従来の放射
性ヨウ素除去手段に比較して仮設ポンプ，仮設フィルタ
等の運搬，設置が不要となることにより、短時間，低コ
ストで系統内の放射性ヨウ素を除去できる。According to the present invention, the radioactive iodine can be prevented from being released into the environment when the plant is started by being installed in the system of the nuclear power plant. In addition, when the plant is shut down, the system is not opened, and the transport and installation of temporary pumps and temporary filters are not required as compared with conventional radioactive iodine removal means. Iodine can be removed.
【００４１】さらに、系統流体中の放射性ヨウ素の濃度
を連続測定し、放射性ヨウ素の除去が必要なレベルの流
体の自動選択，流量自動調整を可能にすることにより、
放射性ヨウ素除去終了時期とフィルタ交換時期を特定
し、フィルタの寿命を延ばすことができる。Further, by continuously measuring the concentration of radioactive iodine in the system fluid, it is possible to automatically select a fluid at a level requiring removal of radioactive iodine and to automatically adjust the flow rate.
By specifying the radioactive iodine removal end time and the filter replacement time, it is possible to extend the life of the filter.
【図１】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第１の実施の形態を示す系統図。FIG. 1 is a system diagram showing a first embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図２】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第２の実施の形態を示す系統図。FIG. 2 is a system diagram showing a second embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図３】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第３の実施の形態を示す系統図。FIG. 3 is a system diagram showing a third embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図４】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第４の実施の形態を示す系統図。FIG. 4 is a system diagram showing a fourth embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図５】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第５の実施の形態を示す系統図。FIG. 5 is a system diagram showing a fifth embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図６】本発明に係る原子力発電所のタービン系ヨウ素
除去装置の第６の実施の形態を示す系統図。FIG. 6 is a system diagram showing a sixth embodiment of a turbine-based iodine removing apparatus for a nuclear power plant according to the present invention.
【図７】従来の沸騰水型原子力発電プラントの気体廃棄
物処理装置を示す系統図。FIG. 7 is a system diagram showing a conventional gas waste treatment apparatus of a boiling water nuclear power plant.
１…原子炉建屋、２…原子炉、３…タービン建屋、４…
タービン、５…主蒸気管、６…主復水器、７…空気抽出
器、８…再結合器、９…除湿乾燥器、10…活性炭ホール
ドアップ塔、11…排出装置、12…排気筒、13…復水器真
空ポンプ系統、14…復水器真空ポンプ、15…ウォータセ
パレータ、16…加熱器、17…活性炭フィルタ、18…バイ
パス系統、19…給水管、20…切替器、21…放射性ヨウ素
検出器、22…記憶手段、23…流量調整器、24…自動開閉
弁、25…信号線。1 ... reactor building, 2 ... reactor, 3 ... turbine building, 4 ...
Turbine, 5: Main steam pipe, 6: Main condenser, 7: Air extractor, 8: Recombiner, 9: Dehumidifying dryer, 10: Activated carbon hold-up tower, 11: Discharge device, 12: Exhaust stack, 13 ... condenser vacuum pump system, 14 ... condenser vacuum pump, 15 ... water separator, 16 ... heater, 17 ... activated carbon filter, 18 ... bypass system, 19 ... water supply pipe, 20 ... switcher, 21 ... radioactive Iodine detector, 22: storage means, 23: flow rate regulator, 24: automatic open / close valve, 25: signal line.
Claims (5)
主復水器の下流に位置し、復水器真空ポンプを含む前記
主復水器からタービン建屋外に設置した排気筒までの復
水器真空ポンプ系統に、加熱器と活性炭フィルタを直列
接続してなることを特徴とする原子力発電所のタービン
系ヨウ素除去装置。1. A condenser from a main condenser including a condenser vacuum pump, which is located downstream of a main condenser of a main steam system from a reactor to a turbine, to a stack disposed outside a turbine building. A turbine system iodine removal apparatus for a nuclear power plant, comprising a heater and an activated carbon filter connected in series to a vacuum pump system.
イパス系統を設け、このバイパス系統に前記加熱器と活
性炭フィルタを設置するとともに、前記復水器真空ポン
プ系と前記バイパス系統の分岐部に切替器を設けること
を特徴とする請求項１記載の原子力発電所のタービン系
ヨウ素除去装置。2. A bypass system is provided in parallel with the condenser vacuum pump system, the heater and the activated carbon filter are installed in the bypass system, and a branch between the condenser vacuum pump system and the bypass system is provided. The turbine-system iodine removal apparatus for a nuclear power plant according to claim 1, wherein a switching device is provided in the turbine.
器を設け、この検出器と前記切替器に接続する記憶手段
を設けてなることを特徴とする請求項２記載の原子力発
電所のタービン系ヨウ素除去装置。3. The turbine of a nuclear power plant according to claim 2, further comprising a radioactive iodine detector provided upstream of said switch, and storage means connected to said detector and said switch. System iodine removal equipment.
るか、またはこの流量調整弁の上流側に前記放射性ヨウ
素検出器を設け、この検出器と前記流量調整弁に記憶手
段を接続してなることを特徴とする請求項１ないし２記
載の原子力発電所のタービン系ヨウ素除去装置。4. A flow controller is provided upstream of the heater, or the radioactive iodine detector is provided upstream of the flow control valve, and storage means is connected to the detector and the flow control valve. The turbine-based iodine removal apparatus for a nuclear power plant according to claim 1 or 2, wherein:
性ヨウ素検出器と自動開閉弁を直列接続してなることを
特徴とする請求項１ないし４記載の原子力発電所のター
ビン系ヨウ素除去装置。5. The apparatus according to claim 1, wherein said radioactive iodine detector and an automatic on-off valve are connected in series downstream of said activated carbon filter.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10181720A JP2000009892A (en) | 1998-06-29 | 1998-06-29 | Iodine removal device of turbine system of atomic power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10181720A JP2000009892A (en) | 1998-06-29 | 1998-06-29 | Iodine removal device of turbine system of atomic power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JP2000009892A true JP2000009892A (en) | 2000-01-14 |
Family
ID=16105703
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10181720A Pending JP2000009892A (en) | 1998-06-29 | 1998-06-29 | Iodine removal device of turbine system of atomic power station |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2000009892A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012223254A (en) * | 2011-04-15 | 2012-11-15 | Shinshu Univ | Radioactive material-blocking mask |
| JP2014121702A (en) * | 2012-11-20 | 2014-07-03 | Toshiba Corp | Iodine adsorbent, tank for water treatment, and iodide compound treatment system |
-
1998
- 1998-06-29 JP JP10181720A patent/JP2000009892A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012223254A (en) * | 2011-04-15 | 2012-11-15 | Shinshu Univ | Radioactive material-blocking mask |
| JP2014121702A (en) * | 2012-11-20 | 2014-07-03 | Toshiba Corp | Iodine adsorbent, tank for water treatment, and iodide compound treatment system |
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