JPH0534495A - Containment vessel vent device - Google Patents

Containment vessel vent device

Info

Publication number
JPH0534495A
JPH0534495A JP3195212A JP19521291A JPH0534495A JP H0534495 A JPH0534495 A JP H0534495A JP 3195212 A JP3195212 A JP 3195212A JP 19521291 A JP19521291 A JP 19521291A JP H0534495 A JPH0534495 A JP H0534495A
Authority
JP
Japan
Prior art keywords
filter
gaseous
containment vessel
solid particle
radioactive
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
JP3195212A
Other languages
Japanese (ja)
Inventor
Akihiko Noya
明彦 野家
Hidetoshi Karasawa
英年 唐澤
Kiyomi Funabashi
清美 船橋
Masao Endo
正男 遠藤
Hisato Tagawa
久人 田川
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 JP3195212A priority Critical patent/JPH0534495A/en
Publication of JPH0534495A publication Critical patent/JPH0534495A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE:To reduce size and weight of a device by reducing relative humidity of steam including radioactive solid particle and gaseous FP so as to increase absorption efficiency, and by providing a filter for which an absorber is used, so as to remove a radioactive material. CONSTITUTION:Steam including solid particle and gaseous FP is sent to a solid particle scavenging filter 1. Several layers of a filter unit for which stainless steel fiber is molded into rectangular shape form the filter 1. Silica gel is filled in the outer periphery of a wire gauze cylinder made of stainless steel, which is sealed in a cylindrical container so as to form a dryer 2, and relative humidity at the exit of the dryer 2 can be reduced by letting the steam run through the inside of the wired gauze. Iodine absorber such as silver alumina is filled in a gas scavenging filter 3, and removing efficiency of radioactive material can be improved, while the size and weight of a device can be reduced.

Description

【発明の詳細な説明】Detailed Description of the Invention

【産業上の利用分野】本発明は原子炉に係り、特に、原
子炉圧力容器から放出される放射性の固体粒子及び気体
状FPを含んだ水蒸気から放射性物質を除去し、環境へ
の放出量を最小にする装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a nuclear reactor, and more particularly, to removing radioactive substances from water vapor containing radioactive solid particles and gaseous FP discharged from a reactor pressure vessel to reduce the amount released to the environment. Regarding the device to minimize.

【従来の技術】従来の技術は、フィルタベント装置付き
格納容器(R. O.Schlueter and R.P. Schumitz,“Filte
red Vented Containment”,Fourth Workshop onContai
nment Integrity, June 15,1988.)に記載のよう
に、事故時の格納容器内圧上昇による格納容器破損を防
ぐために放出された放射性物質の中から気体状FPをプ
ール水中に溶解し、固体粒子をフィルタで除去した後、
環境へ放出するシステムとなっていた。
2. Description of the Related Art The prior art is based on a containment vessel with a filter vent device (ROSchlueter and RP Schumitz, "Filte
red Vented Containment ”, Fourth Workshop on Contai
nment Integrity, June 15, 1988.), in order to prevent damage to the containment vessel due to an increase in pressure inside the containment vessel at the time of an accident, gaseous FP is dissolved in pool water from the released radioactive material to remove solid particles. After removing with a filter
It was a system to release to the environment.

【発明が解決しようとする課題】上記従来技術は、事故
時の格納容器内圧の上昇による格納容器の破損を防ぐた
めにフィルタベントシステムを介した減圧ベントシステ
ムで、放射性物質を除去し、環境への放射能の放出を抑
制するシステムとなっている。従来のシステムでは放射
性の気体状FPの除去にプール水が必要となっている。
プールは放射性固体粒子を捕集するフィルタに比べて寸
法が大きく、格納容器ベント装置全体の小型軽量化の妨
げとなっていた。本発明の目的は、小型軽量な格納容器
ベント装置を提供することにある。
The above-mentioned prior art is a decompression vent system via a filter vent system to prevent damage to the containment vessel due to an increase in the pressure inside the containment vessel in the event of an accident, by removing radioactive substances to protect the environment. It is a system that suppresses the release of radioactivity. Conventional systems require pooled water to remove radioactive gaseous FP.
The size of the pool is larger than that of the filter that collects radioactive solid particles, which hinders the reduction in size and weight of the entire containment vessel vent device. An object of the present invention is to provide a small and lightweight containment vessel vent device.

【課題を解決するための手段】上記目的は、原子炉圧力
容器から放出される放射性の固体粒子及び気体状FPを
含む水蒸気から、放射性の気体状FPを吸着剤を充填し
たフィルタで吸着捕集しベントすることにより達成され
る。
The above-mentioned object is to adsorb and collect radioactive gaseous FP from a water vapor containing radioactive solid particles and gaseous FP discharged from a reactor pressure vessel by a filter filled with an adsorbent. And then vented.

【作用】格納容器ベント装置の作動時には、原子炉圧力
容器から放射性の固体状粒子及び気体状FPが水蒸気に
含まれて放出される。固体粒子はガラス及び金属の繊維
で構成されたフィルタを通過する時、慣性,重力沈降,
拡散等の力で繊維表面に吸着する。気体状FPの分子は
吸着剤の表面に空いている無数の孔内部に、気体の慣性
力によって運ばれ、吸着剤表面に衝突して吸着する。こ
の時、加熱等によって相対湿度を低下させた後吸着操作
を行うことにより、吸着剤表面への水分子の吸着を抑制
し、吸着効率の低下を防止する。
When the containment vessel vent device is activated, radioactive solid particles and gaseous FP are contained in water vapor and discharged from the reactor pressure vessel. When solid particles pass through a filter composed of glass and metal fibers, inertia, gravity settling,
Adsorbs to the fiber surface by the force of diffusion. The molecules of the gaseous FP are carried by the inertial force of the gas into the inside of the innumerable pores vacant on the surface of the adsorbent, and collide with the surface of the adsorbent to be adsorbed. At this time, the adsorption operation is performed after the relative humidity is reduced by heating or the like, so that the adsorption of water molecules on the surface of the adsorbent is suppressed and the adsorption efficiency is prevented from lowering.

【実施例】以下、本発明の実施例について説明する。図
1は格納容器ベント装置を模擬しており、固体粒子捕集
フィルタ1,乾燥器2,気体捕集フィルタ3より構成さ
れる。今回は固体粒子としてCsI粒子、気体状FPと
してI2 を用い実施した。CsI粒子及びI2 を含む水
蒸気は配管を通して固体粒子捕集フィルタ1に送られ
る。フィルタ1は4μmのステンレス繊維を長方形に成
形したフィルタユニットを数段重ねたものである。フィ
ルタの厚さ方向に通気すると粒径約0.3μmのCsI
粒子がフィルタ繊維中に捕集される。フィルタ厚さ20
cm,フィルタ面速度30m/sでの捕集効率は約99.
9% である。乾燥器2はステンレス製金網円筒の外周
にシリカゲルを充填し円筒容器に封入したもので、金網
の内側に水蒸気を通すことにより乾燥器出口での相対湿
度を低下させることができる。気体捕集フィルタ3には
粒径1〜2mmの銀アルミナ等のヨウ素吸着剤が充填され
ており、粒子には直径600Å程度の細孔が空いてい
る。銀添着量10wt%の銀アルミナ吸着剤を湿度90
%で使用した時の除去効率は95%程度であり、乾燥器
の有効長を長くし相対湿度を90%より低下させれば、
100%近い除去効率が得られる。図2は乾燥器の代わ
りにヒータ4を用いて相対湿度を低下させ、吸着を実施
した例である。ヒータ4以外は図1と同じ条件である。
気体分子I2 を含む水蒸気は固体粒子捕集フィルタ1を
通過中に冷却され過飽和の状態となる。ヒータ4でフィ
ルタ3は温度約250℃程度まで加熱され、水蒸気の相
対湿度が低下し、吸着剤の吸着効率が上昇し、ほぼ全量
のI2 を吸着できる。以上により、本実施例から格納容
器ベント装置の小型軽量化が図れる。
EXAMPLES Examples of the present invention will be described below. FIG. 1 is a simulation of a containment vessel venting device, and is composed of a solid particle collecting filter 1, a dryer 2 and a gas collecting filter 3. This time, CsI particles were used as the solid particles and I 2 was used as the gaseous FP. The water vapor containing CsI particles and I 2 is sent to the solid particle collection filter 1 through a pipe. The filter 1 is formed by stacking a plurality of filter units each having a rectangular shape made of stainless steel fiber of 4 μm. When aerated in the thickness direction of the filter, CsI with a particle size of about 0.3 μm
The particles are trapped in the filter fibers. Filter thickness 20
The collection efficiency is about 99.cm at a filter surface speed of 30 m / s.
9%. The dryer 2 is a stainless steel wire mesh cylinder filled with silica gel and sealed in a cylindrical container. By passing water vapor inside the wire mesh, the relative humidity at the dryer outlet can be reduced. The gas collection filter 3 is filled with an iodine adsorbent such as silver alumina having a particle diameter of 1 to 2 mm, and the particles have pores with a diameter of about 600 Å. A silver alumina adsorbent with a silver loading of 10 wt% is used for humidity 90
%, The removal efficiency is about 95%, and if the effective length of the dryer is increased and the relative humidity is reduced below 90%,
A removal efficiency close to 100% is obtained. FIG. 2 shows an example in which the heater 4 is used instead of the drier to reduce the relative humidity and to perform the adsorption. The conditions other than the heater 4 are the same as those in FIG.
The water vapor containing the gas molecule I 2 is cooled while passing through the solid particle collecting filter 1 and becomes supersaturated. The heater 4 heats the filter 3 up to a temperature of about 250 ° C., the relative humidity of water vapor decreases, the adsorption efficiency of the adsorbent increases, and almost all the amount of I 2 can be adsorbed. As described above, the present embodiment can reduce the size and weight of the containment vessel vent device.

【発明の効果】本発明によれば、原子炉圧力容器から放
出された放射性物質を、気体状FPを捕集するフィルタ
を設けた格納容器ベント装置により除去できるので、装
置の小型軽量化が図れ、設計の自由度が増す。
According to the present invention, the radioactive material released from the reactor pressure vessel can be removed by the containment vessel vent device provided with the filter for collecting the gaseous FP, so that the size and weight of the apparatus can be reduced. , The freedom of design increases.

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

【図1】本発明の実施例一の説明図。FIG. 1 is an explanatory diagram of Embodiment 1 of the present invention.

【図2】本発明の第二の実施例の説明図。FIG. 2 is an explanatory diagram of a second embodiment of the present invention.

【符号の説明】[Explanation of symbols]

1…固体粒子捕集フィルタ、2…乾燥器、3…気体捕集
フィルタ、4…ヒータ。
1 ... Solid particle collection filter, 2 ... Dryer, 3 ... Gas collection filter, 4 ... Heater.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 遠藤 正男 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内 (72)発明者 田川 久人 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内   ─────────────────────────────────────────────────── ─── Continued front page    (72) Inventor Masao Endo             1168 Moriyama-cho, Hitachi-shi, Ibaraki Japan             Tate Seisakusho Energy Research Institute (72) Inventor Hisato Tagawa             1168 Moriyama-cho, Hitachi-shi, Ibaraki Japan             Tate Seisakusho Energy Research Institute

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】格納容器から放出される放射性固体粒子及
び気体状FPを含む水蒸気から前記放射性固体粒子及び
前記気体状FPを除去して放出する格納容器ベント装置
において、前記気体状FPを除去するフィルタを設ける
ことにより放射性物質を除去することを特徴とする格納
容器ベント装置。
1. A containment vessel vent device for removing and releasing the radioactive solid particles and the gaseous FP from water vapor containing the radioactive solid particles and the gaseous FP released from the containment vessel, wherein the gaseous FP is removed. A containment vessel venting device, characterized in that radioactive substances are removed by providing a filter.
【請求項2】請求項1において、前記気体状FPを吸着
するため、フィルタ材に吸着剤を用いる格納容器ベント
装置。
2. The containment vessel vent device according to claim 1, wherein an adsorbent is used as a filter material to adsorb the gaseous FP.
【請求項3】請求項1において、吸着効率を向上させる
ため、前記気体状FPを含む水蒸気の相対湿度を低下さ
せる格納容器ベント装置。
3. The containment vessel vent device according to claim 1, wherein the relative humidity of water vapor containing the gaseous FP is reduced to improve adsorption efficiency.
JP3195212A 1991-08-05 1991-08-05 Containment vessel vent device Pending JPH0534495A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3195212A JPH0534495A (en) 1991-08-05 1991-08-05 Containment vessel vent device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3195212A JPH0534495A (en) 1991-08-05 1991-08-05 Containment vessel vent device

Publications (1)

Publication Number Publication Date
JPH0534495A true JPH0534495A (en) 1993-02-09

Family

ID=16337328

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3195212A Pending JPH0534495A (en) 1991-08-05 1991-08-05 Containment vessel vent device

Country Status (1)

Country Link
JP (1) JPH0534495A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20020012798A (en) * 2000-08-08 2002-02-20 이재근 A metallic filter for eliminating the radioactivity of aerosol
JP2014115289A (en) * 2012-12-11 2014-06-26 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system and method for containing severe accident of light water reactor (lwr)
JP2016053488A (en) * 2014-09-03 2016-04-14 日立Geニュークリア・エナジー株式会社 Iodine removal device and nuclear power plant
JP2020082015A (en) * 2018-11-29 2020-06-04 株式会社コベルコ科研 Adsorption tower, and apparatus for removing volatile organic compound in gas

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20020012798A (en) * 2000-08-08 2002-02-20 이재근 A metallic filter for eliminating the radioactivity of aerosol
JP2014115289A (en) * 2012-12-11 2014-06-26 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system and method for containing severe accident of light water reactor (lwr)
US9406407B2 (en) 2012-12-11 2016-08-02 Ge-Hitachi Nuclear Energy Americas Llc Radioactive capture system for severe accident containment of light water reactors (LWRS), and method thereof
JP2016053488A (en) * 2014-09-03 2016-04-14 日立Geニュークリア・エナジー株式会社 Iodine removal device and nuclear power plant
JP2020082015A (en) * 2018-11-29 2020-06-04 株式会社コベルコ科研 Adsorption tower, and apparatus for removing volatile organic compound in gas

Similar Documents

Publication Publication Date Title
RU2620584C1 (en) Adsorbent of radioactive iodine and method of processing of radioactive iodine
US4369048A (en) Method for treating gaseous effluents emitted from a nuclear reactor
JP5781279B2 (en) Radioactive iodine adsorbent and radioactive iodine removal device
US11515051B2 (en) Nuclear power plant
US3658467A (en) System for total iodine retention
US5075084A (en) Process for the removal of iodine and iodine compounds from hydrogen-containing gases and vapors
Mimura et al. Separation of Cesium and Strontium by Potassium Nickel: Hexacyanoferrate (II)-Loaded Zeolite A
US3429655A (en) Method and filter for removing iodine from gases
JPS61274298A (en) Equipment for cleaning atmosphere in a plurality of working zones isolated and closed
JP6524429B2 (en) Radioactive waste treatment system and method
JPH0534495A (en) Containment vessel vent device
JP2012233749A (en) Nuclear facility, and waste water treating apparatus and waste water treating method thereof
Ampelogova et al. Carbon-fiber adsorbent materials for removing radioactive iodine from gases
JP6581945B2 (en) Radioactive iodine adsorbent and radioactive iodine removal device
JPH07181294A (en) Tritium inclusive gas processor
RU2161338C2 (en) Sorption filter medium for cleaning air from radioactive iodine
Maeck et al. Application of Metal Zeolites to Radioiodine Air Cleaning Problems
JPH02112796A (en) Device for treating radioactive gaseous waste
RU2792406C1 (en) Gas purifier for capturing volatile fission products (options)
JPH09197085A (en) Method and device for ventilating nuclea reactor containment vessel
RU2808719C1 (en) Unit for cleaning gas streams from volatile cesium and iodine compounds formed during high-temperature processing of spent nuclear fuel
JPS5954946A (en) Method for detecting leakage from filter filled with silver zeolite
JPS5852199B2 (en) How to use trilithium
RU2059306C1 (en) Filter cleaning gaseous products of breakdown at atomic power plant
RU2346346C2 (en) Silica gel-based sorbing agent for radioiodine recovery