JPS58146896A - Particles and elements trapping apparatus - Google Patents

Particles and elements trapping apparatus

Info

Publication number
JPS58146896A
JPS58146896A JP2883782A JP2883782A JPS58146896A JP S58146896 A JPS58146896 A JP S58146896A JP 2883782 A JP2883782 A JP 2883782A JP 2883782 A JP2883782 A JP 2883782A JP S58146896 A JPS58146896 A JP S58146896A
Authority
JP
Japan
Prior art keywords
way valve
particles
iodine
radioactive
collection
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
JP2883782A
Other languages
Japanese (ja)
Inventor
錦引 一男
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP2883782A priority Critical patent/JPS58146896A/en
Publication of JPS58146896A publication Critical patent/JPS58146896A/en
Pending legal-status Critical Current

Links

Landscapes

  • Sampling And Sample Adjustment (AREA)
  • Measurement Of Radiation (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】 本発明は、放射線管理施設に係わり、特に、放射能レベ
ルの高いサンプルの粒子、よう素捕集に好適な粒子、よ
う素捕集装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to radiation control facilities, and particularly to particles of samples with high radioactivity levels, particles suitable for collecting iodine, and an iodine collection device.

放射性物質を含む気体の放出にあたっては、放射性希ガ
ス、放射性よう素、粒子状放射性物質などIIJ定監視
している。このうち、粒子状放射性物質はフィルタに収
集し、放射性よう素は吸着材に吸着させて弁別採取した
後、その放射線レベルを測定する。従来の粒子、よう素
捕#に装置は、比較的、放射能レベルの低い気体を対象
としているので、原子力発電所の冷却材喪失事故のよう
に、濃度の高い放射性物質の放出を伴なう事故において
は、フィルタの取外しなどの操作時に、捕集装置内配管
内に存在する放射性物質からの被曝を受けるという欠点
がある。被曝線量は配管を遮へいすることでも減少でき
るが、事故時に予想される放射能レベルは通常時の10
”〜10@倍にもなり、遮へい材が大量(鉛で101〜
10@の減衰率を得るにはr線エネルギーがα5MeV
で約11〜13crn必要)となる欠点がある。
Regarding the release of gases containing radioactive substances, such as radioactive rare gases, radioactive iodine, and particulate radioactive substances, IIJ is constantly monitoring. Of these, particulate radioactive substances are collected by a filter, and radioactive iodine is adsorbed onto an adsorbent and collected separately, after which its radiation level is measured. Conventional particle and iodine trapping devices target gases with relatively low radioactivity levels, so they cannot be used in situations such as a loss of coolant accident at a nuclear power plant, which involves the release of highly concentrated radioactive materials. In the event of an accident, there is a drawback that during operations such as removing the filter, the user will be exposed to radiation from the radioactive substances present in the pipes within the collection device. Radiation exposure can be reduced by shielding pipes, but the radiation level expected in the event of an accident is 10 times higher than normal levels.
”~10@ times as much, and a large amount of shielding material (lead: 101~
To obtain an attenuation rate of 10@, the r-ray energy must be α5MeV.
The disadvantage is that it requires about 11 to 13 crn).

本発明の目的は、捕集後に捕集装置内に存在する捕集用
フィルタに付着し九以外の放射性物質を清浄な気体(例
えば窒素)で押し出し置換することにより、操作時の被
曝線量を減少する粒子、よう素捕集装置を提供する(あ
る。
The purpose of the present invention is to reduce the exposure dose during operation by extruding and replacing radioactive substances other than those attached to the collection filter in the collection device with clean gas (e.g. nitrogen) after collection. Provides a particle and iodine collection device (there is one).

本発明は、三方弁、二方弁、配管を組み合せ、適切な順
序で開閉させることによ抄、捕集後に捕集装置内配管内
に残存する放射性物質を清浄な気体と置換するようにし
九ものである。
The present invention combines a three-way valve, a two-way valve, and piping, and opens and closes them in an appropriate order to replace radioactive materials remaining in the piping inside the collection device with clean gas after extraction and collection. It is something.

以下、本発明を図面に基づいて説明する・第1図は従来
の実施例で、サンプル入口配管lから入ったサンプルガ
スは捕集材O捕集効率を高めるために加温装置2で加温
され、捕集器4で粒子状放射性物質と放射性よう素が捕
集される。サンプルガスはポンプ7で吸引し、流量計5
、流量制御装置6で一定滝量に制御している。一定時間
捕集した後、補集材を捕集器4から取外して、捕集し九
放射能を分析する0通常運転時のように放射能レベルが
低^場合は、捕集装置内配管内にサンプルガスが存在し
ていても、操作時の被曝線量は問題とならない、しかし
、冷却材喪失事故のように1大量の放射性物質が放出さ
れるような事故の場合は、2・通常レベル0101〜1
06倍の放射能レベルとたる九め、被曝線量は無視でき
ない大きさとなる0本発明は、この被曝線量を減少させ
るもので、第2図が本発明の実施例を示す系統図である
The present invention will be explained below based on the drawings. ・Figure 1 shows a conventional embodiment, in which the sample gas entering from the sample inlet pipe 1 is heated by a heating device 2 to increase the collection efficiency of the collection material O. Particulate radioactive substances and radioactive iodine are collected in the collector 4. The sample gas is sucked in by the pump 7, and the flow meter 5
, the flow rate control device 6 controls the flow rate to be constant. After collecting for a certain period of time, remove the collection material from the collector 4, collect it, and analyze the radioactivity. If the radioactivity level is low as during normal operation, the However, in the case of an accident in which a large amount of radioactive material is released, such as a loss of coolant accident, the exposure dose during operation is not a problem even if sample gas is present in the sample gas. ~1
The radioactivity level is 6 times higher, and the exposure dose becomes a non-negligible amount.The present invention aims to reduce this exposure dose. Fig. 2 is a system diagram showing an embodiment of the present invention.

第2図のように、三方弁、二方弁を組み合せて、これを
適切な順序で開閉し、捕集後に、捕集装置配管内に残有
するサンプルガスを清浄な気体(例えば原子力発電所で
容易に得られる空気、ま危は一般に容易に入手可能な窒
素ガスボンベから供給する窒素など)で置換することに
より冷却材喪失事故時におけるサンプリングに基づく被
曝線量を減少することができる。冷却材喪失事故発生後
のサンプリングの動作状態を第3図から第6図に示す、
第3図から第6図で弁を示す記号のうち三角印が塗しつ
ぶしである方向は閉状態を示し、塗られていない方向は
開状態を示す、第3図はサンプルガスで配管内をパージ
している状態を示し、テンプルガスは、三方弁IG、1
1を経て配管16から流量計5へ流れ、サンプリング個
所から捕集装置までの配管内をサンプルガスで置換する
0次に第4図は捕集器4ヘテンプルガスを流す捕集状態
を示し、サンプルガスは三方弁10,11゜12.13
t−経て捕集6番へ流れ、粒子状放射性物質と放射性よ
う素が捕集される。このとき、放射能レベルが高いので
、サンプルガスの大部分は捕集器4をバイパスして、三
方弁10から二方弁14、配管16★経て流れるように
する0次に第5図は捕集器4及び一部配管内の洗浄状m
t示し、清浄気体は三方弁12から三方弁13を経て捕
集器4内Oサンプルガスを押し出し、置換される。
As shown in Figure 2, a combination of three-way valves and two-way valves are opened and closed in an appropriate order. The exposure dose based on sampling during a loss-of-coolant accident can be reduced by replacing the air with easily available air (such as nitrogen, which is generally supplied from readily available nitrogen gas cylinders). Figures 3 to 6 show the operating status of sampling after a loss of coolant accident occurs.
Among the symbols indicating valves in Figures 3 to 6, the direction in which the triangle mark is filled in indicates the closed state, and the direction in which it is not filled in indicates the open state. Shows the purging state, and the temple gas is from the three-way valve IG, 1.
1, the sample gas flows from the piping 16 to the flow meter 5, and the inside of the piping from the sampling point to the collection device is replaced with the sample gas.Next, FIG. is three-way valve 10,11°12.13
t, and flows to collection No. 6, where particulate radioactive substances and radioactive iodine are collected. At this time, since the radioactivity level is high, most of the sample gas bypasses the collector 4 and flows from the three-way valve 10 to the two-way valve 14 and the pipe 16★. Cleaning condition inside collector 4 and some piping
t, the clean gas pushes out the O sample gas in the collector 4 through the three-way valve 12 and the three-way valve 13, and is replaced.

を九二方弁10から入つ九清浄気体は三方弁11を経て
配管16に流れ、そのルートにあ九る配管内を洗浄置換
する。第6図は第5図の洗浄で残つ九配管部の洗浄状l
It示す−ので、清浄気体は三方弁10と三方弁13か
ら入り、配管16を経て流れ、第5WJgD洗浄と合わ
せ、三方弁10以後のサンプルガスを残らず洗浄置換す
ることがで自る一次に、捕集器4から目的とする捕集材
を取り外す慟本発明によれば、捕集装置内配管内のサン
プルガスを残らず清浄気体で洗浄置換できるので、操作
時の被曝線量を減少することができる効果がある。
The clean gas entering from the two-way valve 10 flows into the pipe 16 via the three-way valve 11, and cleans and replaces the inside of the pipe along its route. Figure 6 shows the cleaning status of the nine piping parts left after cleaning in Figure 5.
It shows that the clean gas enters from the three-way valve 10 and the three-way valve 13, flows through the pipe 16, and, together with the 5th WJgD cleaning, cleans and replaces all the sample gas after the three-way valve 10. According to the present invention, all the sample gas in the piping inside the collection device can be cleaned and replaced with clean gas, reducing the exposure dose during operation. There is an effect that can be done.

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

第1図は従来0粒子、よう素捕集装置の系統図、第2図
は本発明による粒子、よう素捕集装置の系統図、tJE
3図から第6IIgは第2図0動作状態図である。 4・・・捕集器%5・・・流量計、6・・・流量制御装
置、7・・・ポンプ、10.11,12.13・・・三
方弁、14.15・・・二方弁。 81 圀 第2図
Fig. 1 is a system diagram of a conventional zero-particle, iodine collection device, and Fig. 2 is a system diagram of a particle, iodine collection device according to the present invention.
6IIg from FIG. 3 is an operating state diagram of FIG. 20. 4... Collector %5... Flow meter, 6... Flow rate control device, 7... Pump, 10.11, 12.13... Three-way valve, 14.15... Two-way valve. 81 Country map 2

Claims (1)

【特許請求の範囲】[Claims] 1、 サンプルポンプ、流量制御装置、ヒータ、フィル
タホルダより成る粒子、よう素捕集装置において、三方
弁と二方弁を設けたことを特徴とする粒子、よう素捕集
装置。
1. A particle and iodine collection device comprising a sample pump, a flow rate control device, a heater, and a filter holder, characterized in that the device is equipped with a three-way valve and a two-way valve.
JP2883782A 1982-02-26 1982-02-26 Particles and elements trapping apparatus Pending JPS58146896A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2883782A JPS58146896A (en) 1982-02-26 1982-02-26 Particles and elements trapping apparatus

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2883782A JPS58146896A (en) 1982-02-26 1982-02-26 Particles and elements trapping apparatus

Publications (1)

Publication Number Publication Date
JPS58146896A true JPS58146896A (en) 1983-09-01

Family

ID=12259480

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2883782A Pending JPS58146896A (en) 1982-02-26 1982-02-26 Particles and elements trapping apparatus

Country Status (1)

Country Link
JP (1) JPS58146896A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62140434U (en) * 1986-02-26 1987-09-04
JP2013004205A (en) * 2011-06-13 2013-01-07 Nittetsu Elex Co Ltd Control method and control device for cooling water flowing in fuel cell

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62140434U (en) * 1986-02-26 1987-09-04
JP2013004205A (en) * 2011-06-13 2013-01-07 Nittetsu Elex Co Ltd Control method and control device for cooling water flowing in fuel cell

Similar Documents

Publication Publication Date Title
JP2010048765A (en) Iodine sampler
EP2942782B1 (en) Salt filtration system and method of removing a radioactive material from a gas using the same
JPS58146896A (en) Particles and elements trapping apparatus
JPH06130191A (en) Operation of boiling water reactor plant, boiling water reactor plant, and metal injection device
JP2000162387A (en) Method and device for judging exchange timing of chemical filter
JPS629171B2 (en)
Olson et al. Controlling cesium in the coolant of the experimental breeder reactor II
JP2599979B2 (en) Iodine measuring device
JPH0321884A (en) Radioactive material smampling device
JPS58172548A (en) Leak detection of radio active iodine removing filter
KR101494074B1 (en) Complex Apparatus Removable for Airborne Radioactive Materials
JP2586927B2 (en) Tritium-contaminated concrete treatment method and apparatus
JPS6133369B2 (en)
JPS6147595A (en) Device for removing iodine
Bretelle et al. Study of various chemical species behaviour for contamination risk
JP2002365367A (en) Monitoring post system
JPH0743497A (en) Purifying equipment for reactor water
JPS5853760B2 (en) Tritium water vapor removal method
Umber Determination of the physico-chemical I species in the exhausts and stack effluent of a PWR power plant
Snellman Sampling and monitoring of carbon-14 in gaseous effluents from nuclear facilities-a literature survey
JPS6126033B2 (en)
CN111006917A (en) Continuous sampling device for efficiency test of iodine adsorber
Taylor Effluent Treatment Facility emissions monitoring
Hohorst Containment of/sup 220/Rn via adsorption on molecular sieves for HTGR--OGCS
Adrian et al. Testing absolute and activated charcoal filters at Pelindaba