JPS59112294A - Device for removing radioactive iodine from nuclear fuel reprocessing plant - Google Patents

Device for removing radioactive iodine from nuclear fuel reprocessing plant

Info

Publication number
JPS59112294A
JPS59112294A JP57221806A JP22180682A JPS59112294A JP S59112294 A JPS59112294 A JP S59112294A JP 57221806 A JP57221806 A JP 57221806A JP 22180682 A JP22180682 A JP 22180682A JP S59112294 A JPS59112294 A JP S59112294A
Authority
JP
Japan
Prior art keywords
radioactive iodine
iodine
nuclear fuel
silver
fuel reprocessing
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
JP57221806A
Other languages
Japanese (ja)
Inventor
賀計 近藤
清美 船橋
浦田 恵
正之 斉藤
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 JP57221806A priority Critical patent/JPS59112294A/en
Publication of JPS59112294A publication Critical patent/JPS59112294A/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
    • 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
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Treating Waste Gases (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】 本発明は核燃料再処理工場において発生する放射性沃素
除去装置に係り、特に放射性沃素を効率的にかつ経済的
に除去するに好適な装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an apparatus for removing radioactive iodine generated in a nuclear fuel reprocessing plant, and particularly to an apparatus suitable for efficiently and economically removing radioactive iodine.

核燃料再処理工場の剪断・溶解工程におけるオフガス処
理系統中に含有する放射性沃素の除去設備において、従
来はアルカリ吸収液を用いた湿式法あるいは銀を添着し
た吸着材を用いた乾式法か採用されていた。然るに湿式
法においてはアルカリ洗浄法の場合、その除去効率か約
10と低い上、大量に発生する廃液の処理に問題があっ
た。一方銀を添着した吸着材を用いた乾式法においては
高価な銀を大量に必要とするためコスト高になる欠的が
あった。
Conventionally, equipment for removing radioactive iodine contained in off-gas treatment systems during the shearing and melting processes of nuclear fuel reprocessing plants has adopted either a wet method using an alkaline absorption liquid or a dry method using an adsorbent impregnated with silver. Ta. However, in the wet method, in the case of the alkaline cleaning method, the removal efficiency was as low as about 10, and there were problems in processing the waste liquid generated in large quantities. On the other hand, the dry method using a silver-impregnated adsorbent requires a large amount of expensive silver, resulting in high costs.

本発明の目的は湿式法あるいは乾式法による放射性沃素
の除去設備の前段に、沃素を粗除去する銀以外の金属を
添着した吸着材を置き、沃素の除去効率を一層高めるこ
とと更には経済的な装置を提供することにある。
The purpose of the present invention is to place an adsorbent impregnated with a metal other than silver that roughly removes iodine in the front stage of radioactive iodine removal equipment using a wet method or a dry method, thereby further increasing the iodine removal efficiency and making it more economical. The goal is to provide a device that is

沃素の除去用吸着材に対して、銀系統以外の金属でも、
基礎的な実験によって鉛、銅、カドミウム等の金属が比
較的除去性能に優れ、銀にかわる吸着材として注目され
ていたが、銀に比較してその除去効率か低いところに難
があるとされ実用化はなされていなかった。本発明はこ
れら銀以外の金属を添着した吸着材を従来の除去設備と
組合わせることによって従来の設備における沃素除去に
要する負荷を低減し、高い除去効率と経済的な放射性沃
素の除去設備ラフ6複したものである。
For adsorbents for removing iodine, metals other than silver can also be used.
Basic experiments have shown that metals such as lead, copper, and cadmium have relatively excellent removal performance, and have attracted attention as adsorbents that can replace silver. It had not been put into practical use. The present invention reduces the load required for iodine removal in conventional equipment by combining these adsorbents impregnated with metals other than silver with conventional removal equipment, and achieves high removal efficiency and economical radioactive iodine removal equipment Rough 6. It is a duplicate.

以下、本発明の一実施例を図により説明する。−1,2
U銀以外の金属全添着した吸着材である。
Hereinafter, one embodiment of the present invention will be described with reference to the drawings. -1,2
U This is an adsorbent that is completely impregnated with metals other than silver.

本発明においては、核燃料再処理剪断・俗解工程にて発
生した放射性沃素を含んだガスか、吸着塔1を通過する
ことにより、下記の反応式によって吸着除去される。
In the present invention, gas containing radioactive iodine generated in the nuclear fuel reprocessing shearing/composition process passes through the adsorption tower 1 and is adsorbed and removed according to the following reaction formula.

MX+L→IVI I 2      (1)(1)式
において、Mは鉛、銅、カドミウム等の鉄以外の金網を
示し、Xはゼオン−f I−等の母材を示す。これら金
属全添着した吸着材の除去効率j(11定の一例を表1
に示す。表から明らかなように一般に相対湿度がゼロ以
外では除去効率は低い。再処理オフガス組成のような高
湿度(除温において90%以上)、高沃素濃度(数io
ppm以上)下では例えばPbXの場合の除去効率は約
80%である。
MX+L→IVI I 2 (1) In the formula (1), M represents a metal mesh other than iron such as lead, copper, or cadmium, and X represents a base material such as Zeon-f I-. Table 1 shows an example of the removal efficiency j (11 constant) of the adsorbent completely impregnated with these metals.
Shown below. As is clear from the table, the removal efficiency is generally low at relative humidity other than zero. High humidity (more than 90% in temperature removal) and high iodine concentration (several io
For example, in the case of PbX, the removal efficiency is about 80%.

表1 単体ヨウ素の除去性能 本発明によrしは、例えばPbXを前段に使用した場合
約80係の沃素が除去され、後段の湿式除去設備ないし
は乾式除去設備に送られる沃素濃度は20俸程度に低減
されつる。このように1にて沃素の粗除去を行うと七が
できるので、後段の沃素除去設備の沃素負荷は低減され
る。湿式法と組合わせた場合、沃素の除去効率を向上で
きる効果かめる。また銀吸着材を用いた乾式法の場合に
は、銀の使用量を低減できる効果かめる。
Table 1 Removal performance of elemental iodine According to the present invention, for example, when PbX is used in the first stage, about 80 parts of iodine is removed, and the iodine concentration sent to the wet or dry removal equipment in the second stage is about 20 parts. Reduced to vine. In this way, if iodine is roughly removed in step 1, step 7 can be obtained, so the iodine load on the subsequent iodine removal equipment is reduced. When combined with the wet method, the effect of improving iodine removal efficiency can be seen. Furthermore, in the case of a dry method using a silver adsorbent, the amount of silver used can be reduced.

1にて沃素が飽和される迄吸着された後は、2に切換え
て運転を行う。使用済の吸着材はそのままドラム缶等に
詰めて貯蔵する。鉛、銅等の金属は比較的安価なのでそ
のit処分されてもコスト的には安価に済ませることが
できる。2にて切換運転を行っている間に次の運転に備
える。
After iodine is adsorbed to saturation in step 1, the operation is switched to step 2. Used adsorbents are packed into drums and stored as is. Metals such as lead and copper are relatively inexpensive, so even if they are disposed of it, the cost can be reduced. While the switching operation is being performed in step 2, preparations are made for the next operation.

本発明なよれば、核燃料再処理工程オフガス処理系統中
の放射性沃素の除去効率を、従来の湿式法と組合わせた
場合、鉛を使用するとすると約5倍に高ぬる効果がある
。(鉛のDFは前述より約5である)また湿式法におけ
る沃素含鳴廃液中の沃素量の低減化か可能で、後続の廃
沿処理を容易にする効果がある。また銀添着吸着材と組
合わせた場合には、オフガス中の沃素濃度の急激な変動
に対して、銀天添着吸着材の濃度変動によるDFの低下
等の悪影響ヲ防1卜することができる。
According to the present invention, when combined with the conventional wet method, the removal efficiency of radioactive iodine in the off-gas treatment system of the nuclear fuel reprocessing process is about five times higher than when lead is used. (The DF of lead is about 5 as described above) It is also possible to reduce the amount of iodine in the iodine-containing waste liquid in the wet method, which has the effect of facilitating the subsequent waste treatment. In addition, when combined with a silver-impregnated adsorbent, it is possible to prevent adverse effects such as a decrease in DF due to changes in the concentration of the silver-impregnated adsorbent in response to sudden changes in the iodine concentration in the off-gas.

例えば年間600tの使用済軽水炉燃料を再処理した時
に発生する放射性沃素の量は約160 kgである。(
燃焼度40,000MWD/lで、667日燃焼後、5
年冷却し再処理するとした)。この沃素を全量銀で吸着
する場合(ケースA)と、前段に例えば鉛添着吸着材を
置いた場合(ケースB)にそれぞれ必袈な銀の所要量全
比較すると、化学量論的にケースAの」島台が約193
kg、ケースBの場合は銀が約39kgで、鉛が約80
kgであり、銀の所要量を約154kg低減化可能で、
コスト的に約1/4に押さえることか可能である。
For example, the amount of radioactive iodine generated when 600 tons of spent light water reactor fuel is reprocessed per year is about 160 kg. (
After 667 days of combustion at a burnup of 40,000MWD/l, 5
). Comparing the total amount of silver required when all of this iodine is adsorbed by silver (Case A) and when a lead-impregnated adsorbent is placed in the front stage (Case B), stoichiometrically, Case A The island is approximately 193
kg, in case B, silver is about 39 kg and lead is about 80 kg.
kg, it is possible to reduce the amount of silver required by approximately 154 kg,
It is possible to reduce the cost to about 1/4.

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

第1図は本発明による核燃料再処理施設からの放射性沃
素の除去装置のフローシートである。 1.2・・・吸着塔、3・・・放射性沃素の除去設備。
FIG. 1 is a flow sheet of an apparatus for removing radioactive iodine from a nuclear fuel reprocessing facility according to the present invention. 1.2...Adsorption tower, 3...Radioactive iodine removal equipment.

Claims (1)

【特許請求の範囲】 1、湿式法あるいは乾式法放射性沃素除去設備の前段に
放射性沃素の粗除去を行う装置を設けたことを特徴とす
る核燃料再処理施設からの放射性沃素の除去装置。 2、放射性沃素の粗除去を・行う装置において、鉛。 銅、カドミウム等の銀以外の金属を添着した吸着材を設
けたことを特徴とする特許請求範囲第1項に記載の核燃
料再処理施設からの放射性沃素の除去装置。
[Scope of Claims] 1. An apparatus for removing radioactive iodine from a nuclear fuel reprocessing facility, characterized in that a device for roughly removing radioactive iodine is provided upstream of a wet or dry method radioactive iodine removal facility. 2. Lead in equipment that roughly removes radioactive iodine. An apparatus for removing radioactive iodine from a nuclear fuel reprocessing facility according to claim 1, further comprising an adsorbent impregnated with a metal other than silver, such as copper or cadmium.
JP57221806A 1982-12-20 1982-12-20 Device for removing radioactive iodine from nuclear fuel reprocessing plant Pending JPS59112294A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57221806A JPS59112294A (en) 1982-12-20 1982-12-20 Device for removing radioactive iodine from nuclear fuel reprocessing plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57221806A JPS59112294A (en) 1982-12-20 1982-12-20 Device for removing radioactive iodine from nuclear fuel reprocessing plant

Publications (1)

Publication Number Publication Date
JPS59112294A true JPS59112294A (en) 1984-06-28

Family

ID=16772485

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57221806A Pending JPS59112294A (en) 1982-12-20 1982-12-20 Device for removing radioactive iodine from nuclear fuel reprocessing plant

Country Status (1)

Country Link
JP (1) JPS59112294A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6147595A (en) * 1984-08-15 1986-03-08 株式会社日立製作所 Device for removing iodine
WO2016104553A1 (en) * 2014-12-26 2016-06-30 ラサ工業株式会社 Filler for filter vent, and filter vent device

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6147595A (en) * 1984-08-15 1986-03-08 株式会社日立製作所 Device for removing iodine
JPH0565837B2 (en) * 1984-08-15 1993-09-20 Hitachi Ltd
WO2016104553A1 (en) * 2014-12-26 2016-06-30 ラサ工業株式会社 Filler for filter vent, and filter vent device
JPWO2016104553A1 (en) * 2014-12-26 2017-10-05 ラサ工業株式会社 Filter vent filler and filter vent device

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