JPS6082999A - Radioactive gas waste treater - Google Patents

Radioactive gas waste treater

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Publication number
JPS6082999A
JPS6082999A JP19197583A JP19197583A JPS6082999A JP S6082999 A JPS6082999 A JP S6082999A JP 19197583 A JP19197583 A JP 19197583A JP 19197583 A JP19197583 A JP 19197583A JP S6082999 A JPS6082999 A JP S6082999A
Authority
JP
Japan
Prior art keywords
container
radioactive
activated carbon
delay device
gas
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
JP19197583A
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP19197583A priority Critical patent/JPS6082999A/en
Publication of JPS6082999A publication Critical patent/JPS6082999A/en
Pending legal-status Critical Current

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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] 本発明は原子力発電プラントの放射性気体廃棄物処理装
置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a radioactive gaseous waste treatment device for a nuclear power plant.

[発明の技術的背景] 洲騰水型原子力発電プラントの放射性気体廃棄物処理装
置は、一般に第1図に示ブように、主復水器から連結さ
れる空気抽出器1、予熱器2、再結合器3、復水器4、
除湿器5、脱湿器6、前置フィルタ7a、7b、主吸着
遅延装置8、フィルタ9、真空ポンプ10及びスタック
11が順次直列に配管接続された構成となっている。原
子炉運転中、主復水器から空気抽出器1ひ抽出された1
11ガスは原子炉内で生成されたH2.02や短寿命高
放射性の放射化ガス(酸素、窒素のアイソ1−一プ等)
及び長寿命の放射化ガスくクリア1ヘン、4−セノン等
)を含み、空気抽出器1駆動用の多ωの水蒸気で希釈さ
れている。この排ガスは、まず予熱器2で加熱され、再
結合器3で酸水素再結合反応により水素が除去され、復
水器4にて大部分の水蒸気が凝縮し減容される。復水器
4を流出した71fカスは大部分が空気で、その伯は放
射化ガスと小量の水蒸気を含んでいるか、下流の遅延装
置に用いられる吸着剤の性能維持のため除湿器5及び脱
湿器6で露点−30℃程度まで除湿乾燥される。
[Technical Background of the Invention] A radioactive gas waste treatment system for a Zhouteng water nuclear power plant generally includes an air extractor 1, a preheater 2, and a main condenser connected to each other, as shown in FIG. recombiner 3, condenser 4,
A dehumidifier 5, a dehumidifier 6, prefilters 7a and 7b, a main adsorption delay device 8, a filter 9, a vacuum pump 10, and a stack 11 are connected in series with piping. During reactor operation, one air extractor was extracted from the main condenser.
11 gases include H2.02 generated in the nuclear reactor and short-lived highly radioactive activated gases (oxygen, nitrogen iso-1-1, etc.)
and long-lived activated gas (clear 1-hen, 4-senone, etc.), and is diluted with multi-ω water vapor for driving the air extractor 1. This exhaust gas is first heated in a preheater 2, hydrogen is removed by an oxyhydrogen recombination reaction in a recombiner 3, and most of the water vapor is condensed in a condenser 4 to reduce its volume. Most of the 71f waste that has flowed out of the condenser 4 is air, and it contains activated gas and a small amount of water vapor, or it is used in the dehumidifier 5 and The dehumidifier 6 dehumidifies and dries the material to a dew point of about -30°C.

遅延装置は最上流に配される前置フィルタ7a、7bと
その下流の主吸着遅延装置8とから成り、主吸着遅延装
置8は吸着剤として活性炭を内部に充填した複数の活性
炭塔8a 、 8b 、 8cを直列に配管1と続され
て(M成され、ここで長ズテ命核1Φ(主にクリプトン
、キセノン)を吸着遅延し、放射能を許容値Jメ下まで
減衰させる。短万命核種はここに至るまでにか4τり減
衰づるが、減衰か不充分なまま主吸着遅延装置8に供給
されると吸着剤である活性炭が崩壊熱や放射2次効果等
の悪影響により消耗し、寿命が低減するという問題があ
る。
The delay device consists of prefilters 7a, 7b disposed at the most upstream side and a main adsorption delay device 8 downstream thereof, and the main adsorption delay device 8 includes a plurality of activated carbon columns 8a, 8b filled with activated carbon as an adsorbent. , 8c is connected in series with pipe 1 (M is formed), where it adsorbs and delays the life nucleus 1Φ (mainly krypton and xenon) and attenuates the radioactivity to below the permissible value. The life nuclide has been attenuated for about 4τ up to this point, but if it is supplied to the main adsorption delay device 8 with insufficient attenuation, the activated carbon that is the adsorbent will be consumed due to negative effects such as decay heat and secondary radiation effects. , there is a problem that the service life is reduced.

そのため、遅延装置の最上流に前置フィルタ7a、7b
を設けて主成@遅延装置8に短寿命核種が入いりこまな
いようにしている。また、前置フィルタ7a、7bは固
体崩壊生成物や湿分の濾過を行い、主眼@遅延装置8内
の活性炭を保護しく−いる。
Therefore, prefilters 7a and 7b are provided at the most upstream side of the delay device.
is provided to prevent short-lived nuclides from entering the main @delay device 8. Further, the pre-filters 7a and 7b filter solid decay products and moisture, and protect the activated carbon in the main target@delay device 8.

特に湿分または水分は活11炭の機能を・低下さぼるば
かりでなく、流体の圧力10失を増大させ、遂には系統
の運転を停止させるに至るため、通常結上流側で充分に
除湿が行なわれているか、万一除湿器5、++52湿器
6が故障したり、起動・停止時や定期点検中の誤操作に
より遅延装置Nに水分か流入づる可能性があるため、前
置フィルタ7a 、7bにて主吸着遅延装置8への流入
を防止しCいる。
In particular, moisture or moisture not only reduces the function of live coal but also increases fluid pressure loss, eventually leading to system operation being stopped, so sufficient dehumidification is usually not carried out on the upstream side of the condensation. If the dehumidifier 5, ++52 humidifier 6 malfunctions, or there is a possibility that moisture may flow into the delay device N due to incorrect operation during startup/stop or periodic inspection, the prefilters 7a, 7b may This prevents the water from flowing into the main adsorption delay device 8.

このように前置フィルタ7a 、7bは主吸着遅延装置
8の保護を主目的としているため、遅延時間は短くてよ
く、従って吸る剤たる活性炭は小h1でJ、いが活性炭
塔8a、8b、C3(〕内の活性炭と較べて、内部に充
填された活性炭の劣化か名しく、除って交換頻度も増大
するため、一般に充填物の交換が可能な構造となってお
り、また、第1図に示すように2系列設(jられ、前後
に隔離弁12a、12b 、13a 、13bを設〔プ
て交Tj vJfJ運転を”f lヒにしCいる。
In this way, the prefilter 7a, 7b has the main purpose of protecting the main adsorption delay device 8, so the delay time can be short. Therefore, the activated carbon serving as the adsorption agent is small h1 and J, and the activated carbon tower 8a, 8b is Compared to the activated carbon in C3 (), the activated carbon filled inside is likely to deteriorate and the frequency of replacement increases, so the structure is generally such that the filling can be replaced. As shown in Fig. 1, two lines are installed, and isolation valves 12a, 12b, 13a, and 13b are installed at the front and rear to make the AC operation "f l h".

主吸着遅延装置8を出た排ガスはフィルタ9にて詰゛過
された後貝窄ポンプ10にてスタック11へ台かれ人気
へ放出される。
The exhaust gas exiting the main adsorption delay device 8 is blocked by a filter 9, and then sent to a stack 11 by a shell pump 10 and discharged to the public.

尚、第1図中において、符号14は起動・停止1侍やス
クラム時にj非カスをスタック11ヘバイパス、あるい
は主復水器へ再循環させるための配管であり、15及び
16はその際系統の流路を切替えるための弁である。
In Fig. 1, reference numeral 14 is a pipe for recirculating non-residues to the stack 11 or to the main condenser during start-up/stop or scram; This is a valve for switching the flow path.

さC1前記前置フィルタ7a、7bの構造は第2図に示
すように、円筒状の上部胴17、円すい状の下部1i!
if 18を有し、上部胴17上端には車数19か、ま
/、二下部胴18下端には充填物取出し恒20か接続さ
れている。前記平板19には充填物充填口21、カス入
口22及びガス出口23が設(プられ、カス人1121
は容器内部にガスを導入する尋人管24に接続され、尋
人管24は容器内の充jaI層内部に質端に濾別25を
有して開口していう。
As shown in FIG. 2, the structure of the prefilter 7a, 7b is a cylindrical upper body 17 and a conical lower part 1i!
If 18, 19 cars are connected to the upper end of the upper shell 17, and a filling outlet 20 is connected to the lower end of the lower shell 18. The flat plate 19 is provided with a filler filling port 21, a waste inlet 22, and a gas outlet 23.
is connected to a gas tube 24 that introduces gas into the container, and the gas tube 24 opens into the filled JaI layer inside the container with a filter 25 at its end.

充填物は充填物充填口21の蓋26を聞(プて充填され
るが、直列25の存在によりカス流入部で充填物の安忠
角により空間27が形成される。
The filler is filled by pushing through the lid 26 of the filler filling port 21, and due to the presence of the series 25, a space 27 is formed by the angle of the filler at the waste inflow portion.

また、充填層下部は充填物11ン出管20の下部に設(
づられた支持板28により支えられている。充填物取出
管20は床29を肖通し−C階下に通し゛CJシリ、充
填物取出しの際の遮蔽が考り橙されCいる。
In addition, the lower part of the packed bed is installed at the lower part of the outlet pipe 20 for the packed material 11 (
It is supported by a tilted support plate 28. The filling material removal pipe 20 passes through the floor 29 to the lower floor.

充填物の取出しは取出管ゐ30を聞け、前記支持板28
が連結された盲板31を引き抜くことにより支持板28
がスライドし、充填物を下方に落下させて行うが、充填
物か窩れだ場合を除けば、全Cを取り出す必要はなく、
trll 壊牛成物の最も豊富な空間27の付近までを
取り出しC交換1ればJζい。
To take out the filling, use the take-out pipe 30 and the support plate 28.
By pulling out the blind plate 31 connected to the support plate 28
This is done by sliding the C and letting the filling fall downward, but there is no need to take out all the C unless it is a filling or a cavity.
trll If you take out the vicinity of space 27 where the adult bull adult is most abundant and exchange C1, it will be Jζ.

充填物としては前述のように活性炭塔8a、8b、8c
に充填されているものと同じ活性炭を用いる仙、玄武吉
を破砕した」ノン1−も用いられる。
As for the packing, activated carbon columns 8a, 8b, 8c are used as described above.
``Non 1'', which is made by crushing Genbukichi, is also used, which uses the same activated carbon that is filled in the charcoal.

この場合には吸着効果はなく、前置フィルタ7a、7b
は遅延装置の一部ではなく、遅延装置保護のフィルタと
見做すべきであるが、熱や放DI線による劣化は活性炭
よりも起りにりく、充填物の寿命は長くなる。しかし、
水分の充填層内への(U人(、二際しCは圧損が増大す
るため、や(ま(つ交1襲を余(k% <される。
In this case, there is no adsorption effect, and the prefilter 7a, 7b
Although it should be considered a delay device protection filter rather than part of the delay device, it is less susceptible to deterioration from heat and DI radiation than activated carbon, and the life of the fill is longer. but,
Because the pressure loss increases when moisture enters the packed bed, the pressure loss increases.

「背射技術の問題点」 以」二連へ7j従来の前置フィルタにおいて1よ以−■
讐のような問題点かあった。
"Problems with backlighting technology" 7j In the conventional prefilter, 1 - ■
There were problems like enemies.

Jな4つら、通常ガスは第2図に矢印で示I、1υ女l
く、カス人口22より尋人口24を通り、2+1j27
に−C充填層内へ拡がり、充填層を上方へ確4してガス
出1:+ 2 aより容器外へ流出するか、定検6(’
rに。j、る糸ll″A停止時、系統が負圧に保たれた
状態で一ト流の人気に通ずる弁を誤って聞けた場合、逆
?ん力X年し、空間27を形成する安息角がガスの逆i
fjによつCくずれ、心入管24内に充填物か吸し\込
JこれC充填物の逆流飛散が牛し、その結果配(、+r
、σ)閉塞が起こり系KjCの運転かできなくなるに芋
る。
The four J-type gases are indicated by arrows in Figure 2.I, 1υwomanl
, from Kasu population 22 to fathom population 24, 2+1j27
-C spreads into the packed bed, moves the packed bed upwards and flows out of the container from gas exit 1: + 2 a, or regular inspection 6 ('
to r. j, When A is stopped and the system is kept under negative pressure, if you accidentally hear the valve that leads to the popularity of the Itto flow, the reverse thrust will be X years and the angle of repose that forms the space 27. is the inverse i of gas
C collapses due to fj, and the filling material is sucked into the heart inlet tube 24. This causes the filling material to flow back and scatter, resulting in discharge (,+r
, σ) Blockage occurs and system KjC cannot operate.

また、このJ、うな誤操作が起きない場合でも、j皇子
炉スクラムの際には、系統流量が増大Jるため第1図の
弁]5を聞けて配管14より主復水器へ排ガスを環流さ
せるか、主復水器の真ψ度が高いため除湿器5以降の下
流側のカスら主復水器へ引き込よれる1、そのため逆流
が生じ、前置ノイルタフa、/b内の充填物の逆流飛散
現象か生じる。
In addition, even if this erroneous operation does not occur, during a scram of the Oji reactor, the system flow rate will increase, so the exhaust gas will be recirculated from the pipe 14 to the main condenser by listening to valve 5 in Figure 1. Otherwise, due to the high purity of the main condenser, the waste on the downstream side after the dehumidifier 5 is drawn into the main condenser 1, resulting in a backflow and the filling in the pre-noil toughs a and /b. A phenomenon of backflow scattering of objects occurs.

充填物の逆流飛散はサンドの場合よりも比Φの小さい活
性炭の場合により顕署である。
Backflow scattering of the filler is more noticeable in the case of activated carbon with a small ratio Φ than in the case of sand.

また、第2図に示1−前置フィルタは光屓物父模の際、
充填物の取り出しを階下で行うものの、取出鴛20の上
部に充填物を受()る容器をi〆lい(充填物を落手J
せるため、充填′Iυ)の粉末か周囲+L jID散じ
、作業者の放用線波はくの恐ね5かある仙、充填物が水
分e゛湿っている場合、ちγ子かく9′つさ合つC流下
し匈く、作業か困難であるという欠点かあった。
In addition, as shown in Fig. 2, the 1-prefilter is
Although the filling is to be taken out downstairs, a container for receiving the filling is placed above the take-out container 20.
Because of this, there is a risk that the powder of the filling (Iυ) will be scattered around +LjID, and the radiation waves of the worker may be exposed to radiation waves. The disadvantage was that the C flowed down and was difficult to work on.

[発明の目的」 本発明は、以上Jへた従来の敢用性気体廃東物処理装置
に用いられ−Cいる前置フィルタの欠点を改善し、充填
物の逆流飛散を防止でき、充填物の交1φが容易かつ安
全に行なうことができる前置フィルタを有する放射性気
体開東物処理装置を1hi供することを目的とする。
[Object of the Invention] The present invention improves the drawbacks of the pre-filter used in the conventional gaseous waste treatment equipment as described above, prevents the backflow of the filling material, and prevents the filling material from scattering. The object of the present invention is to provide a radioactive gas open matter processing apparatus having a pre-filter that can easily and safely carry out the intersection of 1φ.

[発明の概要j 本発明は遅延装Jの最上流に配される前置吸る容器は気
密を保つ外胴と吸着剤を充填した着脱自在の内胴の2重
(1′4造により形成され、内用の寸法(J、放q・J
性固体廃棄物貯蔵用ドラム缶に収納Qきる大きさになっ
ている。このため、吸着剤は内胴ごと取り出しCドラム
缶に収め、また充填も内胴ごと外圧内に装着し−C行え
、交換作業性及び安全性を向上さじるとともに、吸着剤
充填1−のカス流入615分の1υi商情を大きくしか
つ網を設置プることによって吸着剤の逆流飛散を防止で
きる。また、吸着剤交換に先立って前ii’7吸着器内
を−L]′ブ■」−でさ、しかもエノノブローにより湿
分を帯びた空気を一ト流側へ戻すことにより主吸着遅延
装置に」ニアブ[」−による湿分の侵入が生じないよう
な配管配置を構成しにし−Cいる。
[Summary of the invention j The present invention is that the pre-suction container disposed at the most upstream side of the delay device J has a double layer (1'4 structure) consisting of an airtight outer shell and a removable inner shell filled with an adsorbent. and internal dimensions (J,
It is large enough to be stored in a drum can for solid waste storage. For this reason, the adsorbent can be taken out with the inner shell and placed in a C drum, and the filling can be carried out by installing the inner shell together with the external pressure. By increasing the size of 1/615 υi and installing a net, backflow scattering of the adsorbent can be prevented. In addition, before exchanging the adsorbent, the inside of the adsorber is heated with -L]'b■'-, and the air tinged with moisture is returned to the flow side by the enono blow to the main adsorption delay device. The piping arrangement must be configured to prevent moisture intrusion due to niobium.

[発明の実施例1 以下、第3図から第、4図を参照して本発明による放射
性気体廃果物処理装置の構成を述へる。
[Embodiment 1 of the Invention] Hereinafter, the configuration of a radioactive gas waste fruit processing apparatus according to the present invention will be described with reference to FIGS. 3 to 4.

第3図におい(、主吸着遅延装置8の上流に並列に設置
された前置吸着器32a 、32bを設(J、その前後
に隔離弁12a、12b、IC3a、1.3bを設ける
。隔離弁12a、12bと前置吸着器32a、32fz
7)間の配管1(tJ +Lめブf L33 a 、:
33bを有する空気流入ff134a、34bをIE 
bx L、また、前置吸着器32a、33bと隔離弁1
3′1.I、13bとの間の配管からは戻り[Ii:i
35a 、 3 bbを分岐し、戻り配管35d、35
b <よ、中1iil iJ止め弁36a 、3611
を設けて、弁1(5と除:W S5の間の配管に連結す
る。前記空気流入室34.I、34bの上流側は空気供
給装置に接続さ4する。また、37は前置吸着器32a
 、32bの前後〕A即を測定監視するための差圧ii
j ”Lある。
In FIG. 3, pre-adsorbers 32a and 32b are installed in parallel upstream of the main adsorption delay device 8. 12a, 12b and preadsorption device 32a, 32fz
7) Piping 1 between (tJ + L) f L33 a,:
IE air inflow ff134a, 34b with 33b
bx L, also pre-adsorbers 32a, 33b and isolation valve 1
3'1. Return from the piping between I and 13b [Ii:i
35a, 3bb are branched and return piping 35d, 35
b <yo, middle 1iil iJ stop valve 36a, 3611
is provided and connected to the piping between valve 1 (5) and WS5. The upstream sides of the air inlet chambers 34.I and 34b are connected to an air supply device 4. vessel 32a
, before and after 32b] Differential pressure ii for measuring and monitoring A
j ” There is L.

上記以外の構成は第1図と同様C6)す、圓−の番号は
同一の機器を一示ず。
The configuration other than the above is the same as in FIG.

前記前置吸着器の構造は、1i−2図に示−4−31、
うに、ガス入口38及びガス出口39を(Jする円筒状
の外胴40の上部にはフランジ41かに)けらゼし、1
・部にはトレン管42を右する鎖扱43が設置ノI〕れ
ている。
The structure of the preadsorption device is shown in Figure 1i-2-4-31,
2, the gas inlet 38 and the gas outlet 39 are cut out (the upper part of the cylindrical outer body 40 has a flange 41), and 1
- A chain handle 43 for connecting the drain pipe 42 is installed in the section.

外胴40内の下部には円筒状内胴44を配置し支持する
ための円環状支持台45が設けられている。内ll11
4IIIは上面および上面に円環状のフランジ部46.
47を有し、下側のフランジ部47の内径部には網48
が張設されて内胴44内に充填された活性炭の充填層を
支えている。また、フランジ部47の下面にはガスケッ
ト49が設けられ、内胴44の自重によりフランジ部4
7と支持台45の間のガスのリークを防止している。さ
らに、内胴44の上側のフランジ部46にはネジで着脱
自在な吊り具50が取付けられている。
An annular support base 45 is provided at the lower part of the outer shell 40 for arranging and supporting the cylindrical inner shell 44 . Inner 11
4III has an annular flange portion 46 on the upper surface and the upper surface.
47, and the inner diameter part of the lower flange part 47 has a mesh 48.
is stretched to support the packed bed of activated carbon filled in the inner shell 44. Further, a gasket 49 is provided on the lower surface of the flange portion 47, and the weight of the inner shell 44 causes the flange portion to
Gas leakage between the support base 45 and the support base 45 is prevented. Furthermore, a hanger 50 is attached to the flange portion 46 on the upper side of the inner body 44 and is detachably attached with a screw.

外胴40の内面上部には支持板51が設けられ、内胴/
14を上から押して固定するための押え板52をボルト
締めで取付けられるようになっている。
A support plate 51 is provided on the upper part of the inner surface of the outer shell 40, and the inner shell/
A presser plate 52 for pressing and fixing 14 from above can be attached by tightening bolts.

押え板52は一文字、三また、あるいは十文字の形状を
してa5す、その形状により支持板51は2個、3個ま
たは4個が外胴40の内面の同一円周状に設けられる。
The presser plate 52 is shaped like a single character, a triple or a cross, and depending on the shape, two, three or four support plates 51 are provided on the same circumference on the inner surface of the outer shell 40.

容器最上部には器53がフランジ41にボルト締めで取
付けられ、容器内の気密を保つ−Cいる。
At the top of the container, a container 53 is attached to the flange 41 with bolts to keep the inside of the container airtight.

前記内胴44の外形寸法は原子力発電所内で放射性固体
廃棄物を貯蔵するのに用いられる容積200℃のドラム
缶内に収納できる大きさである。
The outer dimensions of the inner shell 44 are such that it can be accommodated in a drum can with a capacity of 200° C. which is used to store radioactive solid waste within a nuclear power plant.

内胴44は蓋53、押え板52を取りはずして取り出す
ことができ、また容器内に装むすることができる。この
際、内胴44を所定の位買に装着できるにう支持台45
には中央部分に内胴14外周に合わせた凹みが設(プら
れてガイドの役目を果し、また、支持板51も内胴44
を垂直に吊り下すだめのガイドの役目を果寸。
The inner body 44 can be taken out by removing the lid 53 and the presser plate 52, and can also be loaded into a container. At this time, a support stand 45 is used to attach the inner shell 44 to a predetermined position.
is provided with a recess in the center that matches the outer circumference of the inner shell 14 (which serves as a guide).
It serves as a guide for suspending objects vertically.

次に上記実施例の作用を説明する。Next, the operation of the above embodiment will be explained.

排ガスは空気抽出器1により放射性気体廃棄物処理装置
に抽出され、予熱器2、再結合器3、復水器4、除湿器
5、脱湿器6を経て水素除去、除湿乾燥された後前置吸
着器32a内に流入する。
The exhaust gas is extracted by the air extractor 1 to the radioactive gas waste processing equipment, and passed through the preheater 2, recombiner 3, condenser 4, dehumidifier 5, and dehumidifier 6 to remove hydrogen, dehumidify, and dry. It flows into the stationary adsorption device 32a.

この際、前置吸着器32bは隔離弁12b、13bが閉
じて待機の状態にある。また、止め弁33a 、33b
 、36a 、36bは閉どなっている。
At this time, the preadsorption device 32b is in a standby state with the isolation valves 12b and 13b closed. In addition, stop valves 33a and 33b
, 36a and 36b are closed.

第4図中、符号38のガス入口から前置吸着器内に流入
した排ガスは!$548の隙間を通って活性炭充填層内
に流入し、ここで短寿命核種の吸着遅延および固体崩壊
生成物等の不純物の濾過が行なわれた後、カス出口39
より容器外に流出し、主吸着遅延装置8で長寿命核種の
吸着遅延が行なわれ゛C充分放射能が減衰した後、フィ
ルタ9、真空ポンプ10を経てスタック11から大気に
放出される。
In Fig. 4, the exhaust gas flowing into the pre-adsorption device from the gas inlet 38 is! The waste flows into the activated carbon packed bed through a gap of $548, where it delays the adsorption of short-lived nuclides and filters impurities such as solid decay products, and then flows to the waste outlet 39.
After the long-lived nuclide adsorption is delayed by the main adsorption delay device 8 and the radioactivity is sufficiently attenuated, it is released from the stack 11 into the atmosphere via the filter 9 and the vacuum pump 10.

一方、前述したように系統内に逆流が生じた場合には、
前置吸着器の内胴44には網48が設けられて活性炭を
支えているため、活性炭の逆流飛散は生じない。
On the other hand, if backflow occurs in the system as mentioned above,
Since the inner shell 44 of the pre-adsorber is provided with a net 48 to support the activated carbon, the activated carbon does not scatter in a reverse flow.

ところで活性炭の逆流飛散が生じる最小流速は実験によ
り約1 m/sであることが判っており、また、カスの
逆流流mはせいせい0.1+n3/S程度であるため内
胴44内の流速は0.4 m/s程度で活性炭逆流飛散
流速より小さい。従って第4図にJ5いてガス入口38
とカス出口39の流れ方向を逆にして用いても問題はな
いが、湿分が流入した際のドレン排出を考慮ずれば第4
図に矢印で示した通りの流れ方向が望しい。
By the way, it has been experimentally determined that the minimum flow velocity at which activated carbon backflow scatters is about 1 m/s, and since the backflow flow m of dregs is approximately 0.1+n3/S, the flow velocity inside the inner shell 44 is It is about 0.4 m/s, which is smaller than the activated carbon backflow scattering flow velocity. Therefore, in Figure 4, J5 is the gas inlet 38.
There is no problem even if the flow direction of the waste outlet 39 is reversed, but if the drain discharge when moisture enters is taken into consideration, the fourth
The flow direction is preferably as indicated by the arrow in the figure.

さて、前置吸着器32aに何らかの原因で水分が流入し
、活性炭が濡れた場合に(ユ差圧泪37で測定される着
圧が上Rすることにより検知される。
Now, if moisture flows into the pre-adsorption device 32a for some reason and the activated carbon gets wet (this is detected when the contact pressure measured by the differential pressure 37 rises).

前置吸着器b いは活性炭自体の劣化にJzり使用できなくなった場合
には隔離弁12a、13aを閉じ、隔離弁12b、13
bを聞け−C前置吸着器32bに切替える。その後前置
吸着器32a内の活性炭の交換を行うが、それに先立つ
C止め弁33a 、36aを開け、前置吸着器32a内
を空気Cエア10−するのが前置吸着器32a内の放射
能を減衰さけ作業の安全性をより高める上で効果がある
。エアブロ−により放射能や湿分を帯びた空気は上流側
の除湿器5直前に戻されるため、下流の主吸着遅延装置
8に湿分を送る恐れはない。6し、この上アブローを定
検等のプラント停止時に行う場合には弁16を閉じ、除
湿器5.1152湿器6を運転しで行えばよい。
If the pre-adsorber b or the activated carbon itself deteriorates and becomes unusable, close the isolation valves 12a and 13a, and close the isolation valves 12b and 13.
Listen to b-C Switch to pre-adsorber 32b. Thereafter, the activated carbon in the pre-adsorber 32a is replaced, but prior to that, the C stop valves 33a and 36a are opened and the air C air 10- is pumped through the pre-adsorber 32a to remove the radioactivity in the pre-adsorber 32a. This is effective in reducing damping and increasing work safety. Since air tinged with radioactivity and moisture due to air blowing is returned immediately before the dehumidifier 5 on the upstream side, there is no risk of sending moisture to the main adsorption delay device 8 on the downstream side. 6. If the above blow-out is to be carried out when the plant is stopped for regular inspections, etc., the valve 16 may be closed and the dehumidifier 5, 1152 and humidifier 6 may be operated.

前置吸着器の活性炭の交換は、器53、押え板52を取
りはずし、活性炭を内胴44といっしょに吊り具50で
吊り上げて取り出し、そのまま放射性固体廃棄物貯蔵用
のドラム缶に収納し、吊り貝50も取りはずして内胴4
4内に入れ、ドラム缶に蓋をして貯藏庵説に運ぶ。その
後、新しい活性炭を充填した内胴44を装着する。
To replace the activated carbon in the pre-adsorber, remove the container 53 and the holding plate 52, lift the activated carbon together with the inner shell 44 using the lifting device 50, store it in a drum for radioactive solid waste storage, and then remove the activated carbon from the hanging shell. 50 is also removed and the inner body 4
4, put the lid on the drum, and transport it to Yuzoan Theory. Thereafter, the inner shell 44 filled with new activated carbon is installed.

この交換作業は大部分遠隔操作が可能であるため、作業
中の放射線被ばくはほとんどなく、著しく作業の安全性
が向上するとともに、作業時間も大幅に短縮される。
Since most of this replacement work can be done remotely, there is almost no radiation exposure during the work, significantly improving work safety and significantly reducing work time.

前置吸着器はその上流にてかなり減衰している知ステ命
核種の吸着遅延及び固体崩壊生成物や湿分の瀘過を行う
ものであるため、内部に充填される活性炭は小苗でよく
特許請求の範囲で述べた寸法の内胴に満たされる量で一
般にはよいが、プラントの容量が大きくそれでは不充分
な場合には前置吸着器を2台以上直列に接続しても差し
つかえない。この場合、活性炭の交換は必要に応じて特
定の前置吸着器に対して行えばよい。
The pre-adsorber delays the adsorption of bionuclides which are considerably attenuated upstream, and filters out solid decay products and moisture. In general, it is sufficient to fill the inner shell with the dimensions stated in the claims, but if the capacity of the plant is large and this is insufficient, two or more pre-adsorbers may be connected in series. In this case, the activated carbon may be exchanged for a specific preadsorption device as needed.

また、戻り配管35a 、35bは第3図に示す位置に
限らず例えば除湿器5と脱湿器6の間の配管に接続する
ことも可能である。
Further, the return pipes 35a and 35b are not limited to the positions shown in FIG. 3, but may be connected to a pipe between the dehumidifier 5 and the dehumidifier 6, for example.

[発明の効果] 本発明に係る放射性気体廃棄物処理装置によれば、前置
吸着器内の活性炭の逆流飛散を防止でき、また、前置吸
着器の活性炭の交換を短時間で容易かつ安全に実施でき
るため、主吸着遅延装置に対する保護効果の信頼性を向
上できる効果がある。
[Effects of the Invention] According to the radioactive gas waste treatment apparatus according to the present invention, it is possible to prevent backflow scattering of activated carbon in the preadsorption device, and the activated carbon in the preadsorption device can be easily and safely replaced in a short time. Therefore, the reliability of the protection effect on the main adsorption delay device can be improved.

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

第1図は従来の放射性気体廃棄物処理装置を示す概略系
統図、第2図は従来の前置フィルタの構造を示す縦断面
図、第3図は本発明による放射性気体廃棄物処理装置の
一実施例を示づ“概略系統図、第4図は本発明による前
置吸着器を示す縦断面図である。 1・・・・・・・・・・・・空気抽出器2・・・・・・
・・・・・・予熱器 3・・・・・・・・・・・・再結合器 4・・・・・・・・・・・・復水器 5・・・・・・・・・・・・除湿器 6・・・・・・・・・・・・脱湿器 7a、7b・・・前置フィルタ 8・・・・・・・・・・・・主吸着遅延装置8a 、8
1) 、80−活性炭塔 9・・・・・・・・・・・・フィルタ 10・・・・・・・・・・・・真空ポンプ11・・・・
・・・・・・・・スタック12a、12b、13a、1
3b ・・・・・・・・・・・・隔離弁 14・・・・・・・・・・・・配 管 15.16・・・弁 17・・・・・・・・・・・・上部胴 18・・・・・・・・・・・・下部胴 19・・・・・・・・・・・・平 板 20・・・・・・・・・・・・充填物取出し管21・・
・・・・・・・・・・充填物充填口22・・・・・・・
・・・・・ガス入口23・・・・・・・・・・・・カス
出口24・・・・・・・・・・・・導入管 25・・・・・・・・・・・・直列 26・・・・・・・・・・・・蓋 27・・・・・・・・・・・・空 間 28・・・・・・・・・・・・支持板 29・・・・・・・・・・・・床 30・・・・・・・・・・・・取出し管器31・・・・
・・・・・・・・古根 32a、32b・・・前置吸着器 33a、33b−・・止め弁 34a、34b・・・カス流入管 35a、35b・・・戻り配管 36a、36b・・・止め弁 37・・・・・・・・・・・・差圧訓 38・・・・・・・・・・・・ガス入口39・・・・・
・・・・・・・ガス出口40・・・・・・・・・・・・
外 胴 41・・・・・・・・・・・・フランジ42・・・・・
・・・・・・・ドレン管43・・・・・・・・・・・・
鏡板 44・・・・・・・・・・・・内 胴 45・・・・・・・・・・・・支持台 46・・・・・・・・・・・・フランジ部・17・・・
・・・・・・・・・フランジ部48・・・・・・・・・
・・・網 49・・・・・・・・・・・・ガスク゛ット50・・・
・・・・・・・・・吊り具 b1・・・・・・・・・・・・支持板 52・・・・・・・・・・・・押え板 53・・・・・・・・・・・・薔 代理人弁理士 須 山 佐 − 第1図 011 第 2 図 第3図 4 9 1リ II
Fig. 1 is a schematic system diagram showing a conventional radioactive gas waste treatment device, Fig. 2 is a vertical cross-sectional view showing the structure of a conventional prefilter, and Fig. 3 is an illustration of a radioactive gas waste treatment device according to the present invention. FIG. 4 is a longitudinal sectional view showing a pre-adsorption device according to the present invention. 1. Air extractor 2.・・・
・・・・・・Preheater 3・・・・・・・・・・・・Recombiner 4・・・・・・・・・・・・Condenser 5・・・・・・・・・...Dehumidifier 6...Dehumidifier 7a, 7b...Prefilter 8...Main adsorption delay device 8a, 8
1) ,80-Activated carbon tower 9...Filter 10...Vacuum pump 11...
......Stacks 12a, 12b, 13a, 1
3b......Isolation valve 14...Piping 15.16...Valve 17... Upper shell 18...Lower shell 19...Flat plate 20...Filling material removal pipe 21・・・
・・・・・・・・・Filling material filling port 22・・・・・・・
...... Gas inlet 23 ...... Dregs outlet 24 ...... Introductory pipe 25 ...... Series 26......Lid 27...Space 28...Support plate 29... ...... Floor 30 ...... Takeout tube 31 ...
... Old roots 32a, 32b... Pre-adsorption device 33a, 33b... Stop valve 34a, 34b... Waste inflow pipe 35a, 35b... Return pipe 36a, 36b...・Stop valve 37...Differential pressure control 38...Gas inlet 39...
・・・・・・Gas outlet 40・・・・・・・・・・・・
Outer body 41...Flange 42...
・・・・・・Drain pipe 43・・・・・・・・・・・・
End plate 44...Inner body 45...Support stand 46...Flange section 17...・
......Flange part 48...
... Net 49 ... Gas Quot 50 ...
...... Hanging tool b1 ...... Support plate 52 ...... Pressing plate 53 ...... ...Patent attorney Sa Suyama - Figure 1 011 Figure 2 Figure 3 4 9 1 Li II

Claims (3)

【特許請求の範囲】[Claims] (1)原子力発電所の放射性排ガスを処理するために内
部に吸着剤を充填した複数の容器から成る遅延装置を有
する放射性気体廃棄物処理装置におい一01前記遅延装
置の最も上流に配置される前置吸着容器(ま外部との気
密を保つ外用と、この外胴内に着脱可能に配置されかつ
吸着剤が充填された内胴との2正枯造に形成したことを
特徴とする放射性気体廃棄物処理装置。
(1) In a radioactive gaseous waste treatment equipment having a delay device consisting of a plurality of containers filled with adsorbent to treat radioactive exhaust gas from a nuclear power plant, 101 before being placed at the most upstream position of the delay device. Radioactive gas disposal characterized by being formed into a double-sided structure with an external adsorption container (an external container that maintains airtightness with the outside) and an inner container that is removably placed inside this outer container and filled with an adsorbent. Material processing equipment.
(2)吸着剤を充填した内胴の外形寸法が、原子力発電
所の放射性固体廃棄物貯蔵用のドラム缶内に収納できる
大きさであることを特徴とする特許請求の範囲第1項記
載の放射性気体廃棄物処理装置。
(2) The radioactivity according to claim 1, characterized in that the outer dimensions of the inner shell filled with the adsorbent are of a size that can be stored in a drum for storing radioactive solid waste at a nuclear power plant. Gaseous waste treatment equipment.
(3)′!l延装置最上流の容器は、2台以上並列に配
し、各容器の前後に隔離弁を設け、上流側隔離弁と容器
との間の配管に空気流入管を接続し、かつ、容器と下流
側隔離弁との間の配管より上流側への戻り配管を分岐し
たことを特徴とする特¥[請求の範囲第1項記載の放射
性気体ff!!東物処理!!i11??。
(3)′! Two or more containers at the most upstream side of the extension device are arranged in parallel, with isolation valves installed before and after each container, and an air inflow pipe connected to the piping between the upstream isolation valve and the container. A feature characterized in that the return piping to the upstream side is branched from the piping between the downstream side isolation valve [radioactive gas ff according to claim 1]! ! Tomono processing! ! i11? ? .
JP19197583A 1983-10-14 1983-10-14 Radioactive gas waste treater Pending JPS6082999A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP19197583A JPS6082999A (en) 1983-10-14 1983-10-14 Radioactive gas waste treater

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP19197583A JPS6082999A (en) 1983-10-14 1983-10-14 Radioactive gas waste treater

Publications (1)

Publication Number Publication Date
JPS6082999A true JPS6082999A (en) 1985-05-11

Family

ID=16283547

Family Applications (1)

Application Number Title Priority Date Filing Date
JP19197583A Pending JPS6082999A (en) 1983-10-14 1983-10-14 Radioactive gas waste treater

Country Status (1)

Country Link
JP (1) JPS6082999A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2020094875A (en) * 2018-12-11 2020-06-18 三菱重工業株式会社 Radioactive gas treatment device, radioactive material treatment system, and reactor facility

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2020094875A (en) * 2018-12-11 2020-06-18 三菱重工業株式会社 Radioactive gas treatment device, radioactive material treatment system, and reactor facility
WO2020121580A1 (en) * 2018-12-11 2020-06-18 三菱重工業株式会社 Radioactive gas processing device, radioactive substance processing system, and nuclear reactor facility

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