JPS58102199A - Radioactive gaseous waste processing device - Google Patents

Radioactive gaseous waste processing device

Info

Publication number
JPS58102199A
JPS58102199A JP20013981A JP20013981A JPS58102199A JP S58102199 A JPS58102199 A JP S58102199A JP 20013981 A JP20013981 A JP 20013981A JP 20013981 A JP20013981 A JP 20013981A JP S58102199 A JPS58102199 A JP S58102199A
Authority
JP
Japan
Prior art keywords
dehumidifier
exhaust gas
condenser
radioactive
pipe
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
Application number
JP20013981A
Other languages
Japanese (ja)
Inventor
伸夫 菊地
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP20013981A priority Critical patent/JPS58102199A/en
Publication of JPS58102199A publication Critical patent/JPS58102199A/en
Pending legal-status Critical Current

Links

Landscapes

  • Electrical Discharge Machining, Electrochemical Machining, And Combined Machining (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 発明の技術分野 本発明は放射性気体廃棄物処理装置(二関する。[Detailed description of the invention] Technical field of invention The present invention relates to radioactive gaseous waste treatment equipment (2).

発明の技術的背景とその問題点 沸騰゛水彩原子力発電所C;おいては、炉心で発生した
気5体は蒸気とともI:直接タービンを通って主復水器
In導かれ、王復水器内の気体は外部i二排出されるが
、この排ガスの放射詑レベルを下ける目的で、気体廃棄
物処理装置が設けられている。
Technical background of the invention and its problems In a boiling watercolor nuclear power plant, the five gases generated in the reactor core are led together with steam directly through the turbine and into the main condenser. This gas is exhausted to the outside, and a gaseous waste treatment device is provided for the purpose of reducing the radiation level of this exhaust gas.

第1図は従来の放射性気体廃棄物処理装置の概略図であ
って、先ず、この放射性気体廃棄物処理装置について説
明する。
FIG. 1 is a schematic diagram of a conventional radioactive gas waste treatment apparatus, and first, this radioactive gas waste treatment apparatus will be explained.

生後水儲MCより空気抽出器Iにより抽出された排ガス
は、予熱器2にて加熱され、再結合器3C二て排ガス中
の水素と酸素を反応させ、その水にプラント内で再使用
する。再結合器3の出口から排出される残りの排ガスの
温度は約440℃であるが、その大部分は過熱蒸気であ
る。この排ガスは復水器4C:て冷却水と熱交換し、こ
の復水器4の出口では約50℃、相対温度100%の非
凝縮性ガスと表る。この排ガスを活性炭ホールドアツプ
装置7 In導く前に湿分を除く必要があり、そのため
に除湿器5.脱湿器6が設けられている。除fllil
it5は冷却機IOより送られる低温冷媒4二より排ガ
スをθ℃〜lO℃C二除湿するものであり、脱湿器6は
冷凍機11より送られる低温冷媒−二より排ガスな一加
℃〜−30℃に冷やして冷凍脱湿するものであるが、脱
湿b6内では水分が凍結して容器内6二着箱するので冷
凍機11より高温冷媒を脱湿器6内に導いて除糧する設
備が備えられている。このようCユして除湿(7た排ガ
スは活性炭ホールドアツプ装置7にで燃料かられずかな
がら漏れてくる放射性気体を減衰させてしまい、そして
処理の終った排ガスはスタックを通してi出される。な
お、真空ポンプ8は排ガスを下流に吸引送風するため直
二設けられている。
The exhaust gas extracted by the air extractor I from the fresh water storage MC is heated in the preheater 2, and the hydrogen and oxygen in the exhaust gas are reacted in the recombiner 3C, and the resulting water is reused within the plant. The temperature of the remaining exhaust gas discharged from the outlet of the recombiner 3 is about 440°C, and most of it is superheated steam. This exhaust gas exchanges heat with the cooling water in the condenser 4C, and at the outlet of the condenser 4 it appears as a non-condensable gas at a relative temperature of about 50° C. and 100%. It is necessary to remove moisture before introducing this exhaust gas into the activated carbon hold-up device 7 In, and for this purpose, a dehumidifier 5. A dehumidifier 6 is provided. removeflil
It 5 dehumidifies the exhaust gas from θ°C to 10°C from the low-temperature refrigerant 42 sent from the cooler IO, and the dehumidifier 6 dehumidifies the exhaust gas from the low-temperature refrigerant from the refrigerator 11 to 1°C to 10°C. It is cooled to -30°C and dehumidified by freezing, but since the water freezes in the dehumidifier b6 and accumulates inside the container, high-temperature refrigerant is introduced into the dehumidifier 6 from the refrigerator 11 to remove dehydration. There are facilities to do so. In this way, the dehumidified exhaust gas is passed through the activated carbon hold-up device 7 to attenuate the radioactive gas that leaks from the fuel, and the treated exhaust gas is discharged through the stack. Two vacuum pumps 8 are provided in order to suck and blow exhaust gas downstream.

ところで、復水器4の下流の系統内を流れる排カスの量
は原子炉の運転状態により例えば110万KW級の沸騰
水戸プラントでは4 ’/l〜40♂/Lと変化するた
め除湿器5及び脱湿器6 Cおける熱負付も定格に対し
l(1〜100%の範囲で変化する。
By the way, the amount of waste gas flowing in the system downstream of the condenser 4 changes from 4'/l to 40♂/l in a 1.1 million KW class boiling Mito plant depending on the operating condition of the reactor, so the dehumidifier 5 The heat load on the dehumidifier 6C also varies from 1 to 100% of the rating.

この負荷範囲をすべてカバーするため冷却機lOおよび
冷凍機11には除湿器5および脱湿i 61−送り込む
冷媒を熱負荷C二合わせて制御するための複雑な制御機
構とめんどうな調整作業とが要求された。
In order to cover all of this load range, the cooler 1O and the refrigerator 11 are equipped with a dehumidifier 5 and a dehumidifier I61, and a complicated control mechanism and troublesome adjustment work to control the refrigerant to be sent together with the heat load C2. I was demanded to.

しかしながら、脱湿16Fi除湿器5に比べて熱交換量
が約1と小さく、また、冷凍脱湿を行うため排ガスを多
少冷やし過ぎても支障がなく、比較的調整も容易である
。これC二対して、除湿器5は冷やし過ぎると容器内に
水分が着箱して機能低下を招くため、精度の高い温度制
御が要求されており、また、熱交換量も大きいためvI
4整が峻しく、%≦ユ小負負荷時おいて冷却サイクルに
ハンチング等の乱れが生じ易い姉の欠点があった。
However, compared to the dehumidifying 16Fi dehumidifier 5, the amount of heat exchange is small, about 1, and since the dehumidifying process is performed by freezing, there is no problem even if the exhaust gas is cooled a little too much, and adjustment is relatively easy. On the other hand, if the dehumidifier 5 is cooled too much, moisture will settle inside the container and cause a decline in functionality, so highly accurate temperature control is required, and the amount of heat exchange is large, so vI
The disadvantage of the older sister was that the 4 adjustment was steep and disturbances such as hunting were likely to occur in the cooling cycle under small negative loads (%≦Y).

発明の目的 本発明は上記したような欠点を解消するもので、熱負荷
状態の安定した調整の容易な放射性気体廃棄物処理装置
を提供することを目的とするものである。
OBJECTS OF THE INVENTION The present invention solves the above-mentioned drawbacks, and an object thereof is to provide a radioactive gas waste treatment apparatus in which the heat load condition can be stably adjusted and easily adjusted.

発明の構成 本発明は、上記の目的を達成するために、沸騰水形原子
力発電所の主復水器から抽出された排ガスを活性炭ホー
ルドアツプ装置C二て処置するための前処理設備として
予熱器、再結合暢、復水器。
Structure of the Invention In order to achieve the above object, the present invention provides a preheater as pretreatment equipment for treating exhaust gas extracted from the main condenser of a boiling water nuclear power plant using an activated carbon hold-up device C. , recombination, condenser.

除湿益、脱湿器を備えた放射性気体廃棄物処理装置にお
いて、前記復水器入口配管から前記除湿器入口配管に排
ガスをバイパスさせるバイパス配管を設け、このバイパ
ス配管中の排ガスの流量を前記除湿器の熱負荷により制
御する制御機構を備えており、そしてこの制御機構は除
湿器入口配管に設けた流量検知器よりの信号を受けてバ
イパス配管−二設置された弁を制御するようC二構成さ
れている放射性気体廃棄物処理装置である。
In a radioactive gas waste processing apparatus equipped with a dehumidifier, a bypass pipe is provided to bypass the exhaust gas from the condenser inlet pipe to the dehumidifier inlet pipe, and the flow rate of the exhaust gas in the bypass pipe is adjusted to the dehumidifier. It is equipped with a control mechanism that controls according to the heat load of the dehumidifier, and this control mechanism receives a signal from a flow rate detector installed in the dehumidifier inlet piping to control the valve installed in the bypass piping. This is a radioactive gas waste treatment equipment.

発明の実施例 本発明の一実施例な第2図を参照して説明する。Examples of the invention An embodiment of the present invention will be explained with reference to FIG. 2.

第2図C二図示したようC;復水器入口配管13と除湿
器入口配管14を連通するよう5二バイパス配管12を
設ける。このバイパス配管12にはバイパス配管12を
流れる排ガスの流量を調整するための弁15が設けられ
ている。この弁15Fiバイパス配管12と除湿器入口
配管14との合流点より上流の除湿器入口配管14に設
けられた流量検知器16よりの信号を受けて弁開閉制御
を行うコントローラ171:より制御される。さらに、
バイパス配管12の除湿器入口配管14への合流点は除
湿器5人口付近の配管中で凝縮したドレンが除湿器5(
二導かれるような位置に設けである。なお、J11!2
図について説明した上記以外の構成について第1図の従
来の放射性気体廃棄物処理装置と全く1町−であるので
、その説明については省略する。
As shown in FIG. 2C, a bypass pipe 12 is provided so that the condenser inlet pipe 13 and the dehumidifier inlet pipe 14 communicate with each other. This bypass pipe 12 is provided with a valve 15 for adjusting the flow rate of exhaust gas flowing through the bypass pipe 12. Controlled by a controller 171 that controls opening and closing of the valve in response to a signal from a flow rate sensor 16 provided on the dehumidifier inlet pipe 14 upstream from the confluence of the valve 15Fi bypass pipe 12 and the dehumidifier inlet pipe 14. . moreover,
The confluence point of the bypass piping 12 to the dehumidifier inlet piping 14 is where the condensed water condensed in the piping near the dehumidifier 5 is connected to the dehumidifier 5 (
It is placed in a position where it can be guided. In addition, J11!2
Since the configuration other than the above explained with reference to the figure is completely the same as the conventional radioactive gas waste treatment apparatus shown in FIG. 1, the explanation thereof will be omitted.

発明の作用 次に、上記のように構成された放射性気体廃棄物処理装
置の作用について説明する。
Operation of the Invention Next, the operation of the radioactive gas waste treatment apparatus configured as described above will be explained.

今、復水器4の出口の排ガス流量が減少すると、流量検
出器16よりの信号を受けてコントローラ17が弁15
を開き、復水器4−二人いる前の高温の排ガスをバイパ
ス配管12を経由して除湿器入口配管14I=流入する
ようにし、除湿器5(二流入する排ガスの熱負荷を高め
る。また、復水器4の出口の排ガス流量が増加すると、
弁15が閉じ、復水器4の入口の尚温排ガスは除湿器入
口配管14に流入しなくなる〇一方、冷却機10の冷却
サイクルは負荷が加チ〜100 *では容易に安定する
ので、弁15の作動は復水器4の出口流量が定格流量の
半分より少い範囲C二おいてのみ行うようCニし、中流
量時〜大流に時区−おいては全閉となるよう1二設定す
る。そして、弁15の作動範囲内での復水器4の出口流
量時においてt/i、弁15が全開となっても除湿器5
での耕カスの熱負荷は定格負荷より小さくなるようバイ
パス配管12ハ復水器入ロ配管131m較べて充分小さ
いサイズのものを用いる。このよう1:弁15の作動範
囲を限定しておくことにより、弁15の開度なそれ程高
精度5二制御することなく除湿器5の熱負荷変動範囲を
冷却機lOの冷却サイクルが容易C二安定し得る範囲C
;抑えることができ、コントローラ17も簡単な構造の
ものが使用できる。さらに、復水器4における熱負荷は
除湿器j+=おける熱負荷の1000倍以上であり、バ
イパス流量は復水器4I:流入する排ガスー二較べて少
量であるので、バイパス流れ1二よる復水器4の負荷変
動は何等問題とならないし、また、系統全体の不安定の
原因となることもない。
Now, when the exhaust gas flow rate at the outlet of the condenser 4 decreases, the controller 17 receives a signal from the flow rate detector 16 and the valve 15
Open the condenser 4 and allow the high temperature exhaust gas from flowing into the dehumidifier inlet pipe 14I via the bypass pipe 12 to increase the heat load of the exhaust gas flowing into the dehumidifier 5. , when the exhaust gas flow rate at the outlet of the condenser 4 increases,
The valve 15 closes, and the still hot exhaust gas at the inlet of the condenser 4 no longer flows into the dehumidifier inlet pipe 14. On the other hand, the cooling cycle of the cooler 10 is easily stabilized when the load is +100*. The valve 15 is operated only in a range C2 where the outlet flow rate of the condenser 4 is less than half of the rated flow rate, and is fully closed in the range from medium flow to large flow. Set 12. Even if the valve 15 is fully open at t/i when the flow rate is at the outlet of the condenser 4 within the operating range of the valve 15, the dehumidifier 5
The size of the bypass piping 12 and the condenser input piping 131 is sufficiently smaller than the 131 m of condenser entry piping so that the heat load of the plowed waste in the pipe is smaller than the rated load. In this way, 1: By limiting the operating range of the valve 15, the cooling cycle of the cooler 10 can be easily controlled by controlling the heat load fluctuation range of the dehumidifier 5 without having to control the opening degree of the valve 15 with such high precision. Bistable range C
;The controller 17 can also have a simple structure. Furthermore, the heat load in the condenser 4 is more than 1000 times the heat load in the dehumidifier j+=, and the bypass flow rate is smaller than that in the condenser 4I: the inflowing exhaust gas. Fluctuations in the load on the water dispenser 4 do not pose any problems and do not cause instability of the entire system.

上記第2図1−示した実施例ではコントローラ170制
御入力を復水器4の出口の排ガス流量としたが、エンタ
ξピー計等の熱負荷測定器を用いて系統中の排ガスの熱
負荷を制御入力としてもよい0この場合は検知位置をバ
イパス配管12と除湿器入口配管14の合流点より下流
の除湿6入ロ配管14とし、検知位置での熱負荷を一定
とする。ような弁15の開度制御を行うことI:より、
除湿器5に流れ込む排ガスの熱負荷がはソ一定となるよ
う番−する。
In the embodiment shown in FIG. 2 1 above, the controller 170 control input is the exhaust gas flow rate at the outlet of the condenser 4, but the heat load of the exhaust gas in the system is measured using a heat load measuring device such as an entertameter. In this case, the detection position is set to the dehumidifier 6-input pipe 14 downstream from the confluence of the bypass pipe 12 and the dehumidifier inlet pipe 14, and the heat load at the detection position is kept constant. To control the opening degree of the valve 15 as follows:
The heat load of the exhaust gas flowing into the dehumidifier 5 is controlled to be constant.

このことにより、冷却機lOの冷媒制御轡はさらに簡単
なものI:なり、また、冷却機10の運転状態も常に一
定とすることができる。
As a result, the refrigerant control of the cooler 10 becomes simpler, and the operating state of the cooler 10 can also be kept constant.

発明の詳細 な説明したよう1;、本発明I:よれに1放射性気体廃
棄物処理装置を流れる排ガスの熱負荷変動範把な小さく
することができるので、除湿器に排ガスを冷却するため
の冷媒を供給する冷却機の冷却サイクルの調整が容易と
なり、また、負荷変動範囲を冷却サイクルの安定領域5
二抑えられるため冷却機の制御機構を簡単なものとする
ことができ、したがって、放射性気体廃棄物処理装置の
低価格化およびコンパクト化が可$154:なる等の効
果を奏するものでめる0
Detailed description of the invention 1; Invention I: Therefore, 1 The heat load fluctuation of the exhaust gas flowing through the radioactive gaseous waste treatment equipment can be reduced within a range, so the refrigerant for cooling the exhaust gas in the dehumidifier is used. This makes it easier to adjust the cooling cycle of the cooler that supplies
2, the control mechanism of the chiller can be simplified, and the radioactive gas waste treatment equipment can be made cheaper and more compact.

【図面の簡単な説明】[Brief explanation of the drawing]

m1図は従来の放射性気体廃棄物処理rI&置を示す概
略系統図、第2図は本発明の一実施例を示す放射性気体
−乗物処理装置の概略系統図である。
Fig. m1 is a schematic system diagram showing a conventional radioactive gas waste treatment rI & system, and Fig. 2 is a schematic system diagram of a radioactive gas-vehicle processing apparatus showing an embodiment of the present invention.

Claims (1)

【特許請求の範囲】[Claims] (1)  沸騰水形原子力発電所の主復水器から抽出さ
れた排カスを活性縦ホールドアツプ装置覆二て処理する
ための前処理設備として予熱器、再結合器。 伽水益、除湿器、脱m器をこの順序C二配管接続した放
射性気体廃棄物処理装置Cおいて、前記復水器入目配管
から前記除湿器入口配管に排ガスをノ(イバスさせるバ
イパス配管を設け、この)(イノくス配智中の排ガスの
流量を前記除湿器の熱負荷によ°り制御する制御機構を
設けたことを特徴とする放射性気体廃棄物処理装置。 (2J  前記制御機構は除湿器入口配管ζ=設けられ
た#L蓋検知器よりの信号を受けて〕くイノくス配管に
設置された弁を制御するよう5二構成されて%l)るこ
とを特徴とする特許請求の範H第1項g二記載の放射性
気体廃棄物処理装置。
(1) A preheater and a recombiner are used as pre-treatment equipment to treat waste gas extracted from the main condenser of a boiling water nuclear power plant by covering it with an active vertical hold up device. In a radioactive gas waste treatment equipment C in which two pipes are connected in this order, a dehumidifier, a dehumidifier, and a dehumidifier, bypass piping is used to divert exhaust gas from the condenser entry pipe to the dehumidifier inlet pipe. and a control mechanism for controlling the flow rate of exhaust gas during the Innox distribution according to the heat load of the dehumidifier. The mechanism is characterized in that it receives a signal from the #L lid detector installed in the dehumidifier inlet pipe and controls the valve installed in the inox pipe. A radioactive gaseous waste treatment apparatus according to claim H, item g, and 2.
JP20013981A 1981-12-14 1981-12-14 Radioactive gaseous waste processing device Pending JPS58102199A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP20013981A JPS58102199A (en) 1981-12-14 1981-12-14 Radioactive gaseous waste processing device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP20013981A JPS58102199A (en) 1981-12-14 1981-12-14 Radioactive gaseous waste processing device

Publications (1)

Publication Number Publication Date
JPS58102199A true JPS58102199A (en) 1983-06-17

Family

ID=16419435

Family Applications (1)

Application Number Title Priority Date Filing Date
JP20013981A Pending JPS58102199A (en) 1981-12-14 1981-12-14 Radioactive gaseous waste processing device

Country Status (1)

Country Link
JP (1) JPS58102199A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20210063057A (en) * 2019-11-22 2021-06-01 한국수력원자력 주식회사 Radioactive gas removal device that improves cfvs performance by lowering the pressure of the filtration exhaust container

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20210063057A (en) * 2019-11-22 2021-06-01 한국수력원자력 주식회사 Radioactive gas removal device that improves cfvs performance by lowering the pressure of the filtration exhaust container

Similar Documents

Publication Publication Date Title
US9815016B2 (en) Carbon dioxide capturing system and method of operating the same
CN108983602A (en) A kind of Auto-disturbance-rejection Control for fast reactor power and coolant outlet temperature
JPS58102199A (en) Radioactive gaseous waste processing device
JPS61149899A (en) Controller for concentration of combustible gas
GB1031158A (en) Improvements in nuclear reactors and methods of operating the same
JPH0529013A (en) Fuel cell power generation system
CN114754350B (en) Heat recovery system, method and device
JPS62138794A (en) Nuclear reactor feedwater-temperature controller
SU462833A1 (en) Method of controlling the polymerization process of propylene
US3151031A (en) Method of regulating the operation of homogeneous nuclear reactors
JPS61234398A (en) Method of operating radioactive gas waste treater
JPS5977012A (en) Reheating type steam turbine plant
JPS61223598A (en) Radioactive gas waste treating method
JPH02107998A (en) Cooling water equipment for nuclear reactor auxiliaries
CN114242284A (en) Nuclear reactor thermal hydraulic test system and regulation and control method
JPS58160Y2 (en) Nuclear plant gaseous waste treatment equipment
JPS6138498A (en) Radioactive gas waste processing device
JPS58102197A (en) Device for operating and monitoring feedwater heater bypass valve of reactor
JPS5924163B2 (en) Cooling water circulation circuit in converter exhaust gas treatment equipment
JPH05149108A (en) Drum level control device for compound cycle power generation plant
JPH049280B2 (en)
JPH05118203A (en) Power generation control device in exhaust heat utilization system
Vadachkoriya et al. Low-temperature vertical channels of the IRT-2000 reactor
JPS6266197A (en) Method of processing radioactive gas waste
JPS58111795A (en) Off-gas processing device