JPS6358299A - Pyrolytic processing method and pyrolytic processor for radioactive chemically decontaminated waste liquor - Google Patents
Pyrolytic processing method and pyrolytic processor for radioactive chemically decontaminated waste liquorInfo
- Publication number
- JPS6358299A JPS6358299A JP20155586A JP20155586A JPS6358299A JP S6358299 A JPS6358299 A JP S6358299A JP 20155586 A JP20155586 A JP 20155586A JP 20155586 A JP20155586 A JP 20155586A JP S6358299 A JPS6358299 A JP S6358299A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- chemical decontamination
- radioactive
- pyrolysis
- tower
- 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
Links
- 239000002699 waste material Substances 0.000 title claims description 56
- 230000002285 radioactive effect Effects 0.000 title claims description 36
- 238000003672 processing method Methods 0.000 title 1
- 239000007788 liquid Substances 0.000 claims description 50
- 238000009390 chemical decontamination Methods 0.000 claims description 41
- 238000000197 pyrolysis Methods 0.000 claims description 30
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 27
- 238000005979 thermal decomposition reaction Methods 0.000 claims description 20
- 229910044991 metal oxide Inorganic materials 0.000 claims description 13
- 150000004706 metal oxides Chemical class 0.000 claims description 13
- 238000000034 method Methods 0.000 claims description 13
- 150000001875 compounds Chemical class 0.000 claims description 12
- 239000013522 chelant Chemical class 0.000 claims description 11
- 239000002738 chelating agent Chemical class 0.000 claims description 11
- 150000007524 organic acids Chemical class 0.000 claims description 9
- 238000000354 decomposition reaction Methods 0.000 claims description 6
- 235000005985 organic acids Nutrition 0.000 claims description 6
- 230000001590 oxidative effect Effects 0.000 claims description 3
- 238000007599 discharging Methods 0.000 claims description 2
- 239000000463 material Substances 0.000 claims description 2
- 239000007789 gas Substances 0.000 description 24
- 239000010802 sludge Substances 0.000 description 13
- 239000002245 particle Substances 0.000 description 11
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 description 9
- KRKNYBCHXYNGOX-UHFFFAOYSA-N citric acid Chemical compound OC(=O)CC(O)(C(O)=O)CC(O)=O KRKNYBCHXYNGOX-UHFFFAOYSA-N 0.000 description 9
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N Iron oxide Chemical compound [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 6
- 239000000498 cooling water Substances 0.000 description 6
- BDAGIHXWWSANSR-UHFFFAOYSA-N methanoic acid Natural products OC=O BDAGIHXWWSANSR-UHFFFAOYSA-N 0.000 description 6
- 230000005855 radiation Effects 0.000 description 5
- 239000003795 chemical substances by application Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 239000012530 fluid Substances 0.000 description 4
- 238000010438 heat treatment Methods 0.000 description 4
- 238000002347 injection Methods 0.000 description 4
- 239000007924 injection Substances 0.000 description 4
- 239000002901 radioactive waste Substances 0.000 description 4
- 238000007711 solidification Methods 0.000 description 4
- 230000008023 solidification Effects 0.000 description 4
- OSWFIVFLDKOXQC-UHFFFAOYSA-N 4-(3-methoxyphenyl)aniline Chemical compound COC1=CC=CC(C=2C=CC(N)=CC=2)=C1 OSWFIVFLDKOXQC-UHFFFAOYSA-N 0.000 description 3
- KCXVZYZYPLLWCC-UHFFFAOYSA-N EDTA Chemical compound OC(=O)CN(CC(O)=O)CCN(CC(O)=O)CC(O)=O KCXVZYZYPLLWCC-UHFFFAOYSA-N 0.000 description 3
- 206010073306 Exposure to radiation Diseases 0.000 description 3
- 235000015165 citric acid Nutrition 0.000 description 3
- 235000019253 formic acid Nutrition 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 3
- 235000006408 oxalic acid Nutrition 0.000 description 3
- 238000005202 decontamination Methods 0.000 description 2
- 230000003588 decontaminative effect Effects 0.000 description 2
- 229910000000 metal hydroxide Inorganic materials 0.000 description 2
- 150000004692 metal hydroxides Chemical class 0.000 description 2
- 229910021645 metal ion Inorganic materials 0.000 description 2
- 239000000843 powder Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 150000007513 acids Chemical class 0.000 description 1
- 238000013019 agitation Methods 0.000 description 1
- 239000003990 capacitor Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 238000009997 thermal pre-treatment Methods 0.000 description 1
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
[発明の目的]
(産業上の利用分野)
本発明は、原子力施設で使用された放射性化学除染廃液
の熱分解処理方法および熱分解処理装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a thermal decomposition treatment method and a thermal decomposition treatment apparatus for radioactive chemical decontamination waste liquid used in nuclear facilities.
(従来の技術)
原子力発電所等の原子力施設においては、機器、配管等
の表面に生成した酸化鉄被膜に放飼性物質が取込、↓れ
て放射線被爆の線源となるため、機器・配管等の表面に
付着したこの酸化鉄被膜を化学除染剤で溶解除去する化
学除染処理が行なわれている。原子力発電所におけるこ
のような化学除染処理においては、月利への腐蝕が少な
く取扱いが容易なことから一般に、クエン酸、シュウ酸
、ギ酸等の有)幾酸とEDTA等のキレ−1へ剤を主成
分とした化学除染剤が使用されている。(Prior art) In nuclear power facilities such as nuclear power plants, free-range substances are incorporated into the iron oxide film that forms on the surfaces of equipment, piping, etc., and become a source of radiation exposure. Chemical decontamination treatment is performed to dissolve and remove this iron oxide film adhering to the surfaces of pipes and the like using a chemical decontamination agent. In such chemical decontamination treatment at nuclear power plants, chemical acids such as citric acid, oxalic acid, and formic acid and EDTA are generally used because they cause less corrosion and are easier to handle. Chemical decontamination agents based on decontaminants are used.
現在のところ、このように多量の右lJ、M、キレ−ト
剤およびキレート化合物を含んだ廃液を原子力発電所の
放射性廃棄物処理設備で処理する技術は命立されていな
いため、化学除染剤を使用することにより発生したtI
i則性化学除染聞液は、仮設の同化装置で他の廃棄物と
は別個に同化処理されている。At present, there is no technology available to treat such large amounts of waste fluid containing chelating agents and chelate compounds in nuclear power plant radioactive waste treatment equipment, so chemical decontamination is necessary. tI generated by using the agent
I-regulated chemical decontamination fluid is assimilated separately from other waste in a temporary assimilation device.
(発明が解決しようとする問題点)
しかしながら、大規模な化学除染が実施された場合には
、除去された多量の放射性物質が放射性化学除染廃液中
に含まれることとなり、この同化作業の際に多量の放射
線被爆を受けるおそれが生じ、しかも高線ωの放射性化
学除染廃液の同化体を多量に貯蔵保管する必要が生じ、
廃棄物処理における大きな負担となっていた。(Problem to be solved by the invention) However, when large-scale chemical decontamination is carried out, a large amount of removed radioactive substances will be contained in the radioactive chemical decontamination waste liquid, and this assimilation work will be difficult. At the same time, there is a risk of being exposed to a large amount of radiation, and it is also necessary to store and store a large amount of assimilated radioactive chemical decontamination waste liquid with high ω radiation.
This was a huge burden on waste disposal.
本発明は、放射性化学除染廃液中の有機酸、キレート剤
およびキレート化合物を既存の放射性廃棄物処理設備で
処理可能なように分解して放射性化学除染廃液処理のた
めの特別な固化装置や同化体貯蔵設備を不要にするとと
もに、放射線被爆を起こし易い放射性化学除染廃液の同
化処理作業を容易にした放射性化学除染廃液の熱分解処
理方法d3よび熱分解処理装置を提供することを目的と
する。The present invention provides a special solidification device and a special solidification device for treating radioactive chemical decontamination waste liquid by decomposing organic acids, chelating agents, and chelate compounds in radioactive chemical decontamination waste liquid so that they can be treated with existing radioactive waste treatment equipment. An object of the present invention is to provide a thermal decomposition treatment method d3 for radioactive chemical decontamination waste liquid and a thermal decomposition treatment apparatus that eliminate the need for assimilate storage equipment and facilitate the assimilation process of radioactive chemical decontamination waste liquid that is likely to cause radiation exposure. shall be.
[発明の構成]
(問題点を解決するための手段)
本発明の放射性化学除染廃液の熱分解処理方法は、原子
力1M段で発生した有機酸、キレート剤おJ、びキレ−
1・化合物を含む放射性化学除染廃液を酸化性雰囲気下
で加熱して熱分解させ、発生した水蒸気と熱分解ガスと
をそれぞれ1」[見逃理系で処理して系外に排出すると
ともに、残留した放射性金属酸化物を貯蔵容器に貯蔵す
ることを特徴としており、また本発明の放射性化学除染
廃液の熱分解処理装置は、流動床形成物質を収容した熱
分解塔と、この熱分解塔の下部から塔内に加熱気体を供
給する加熱気体供給系と、この熱分解塔内へ原子力施設
で発生した@機酸、キレート剤およびキレート化合物を
含む放射性化学除染廃液を供給する廃液供給系と、前記
熱分解塔内で発生した水蒸気と熱分解ガスとを処理する
排気処理系と、前記熱分解塔内に残留した放射性金属酸
化物を排出して貯蔵容器に充填する分解残渣処理系とを
有することを特徴としている。[Structure of the Invention] (Means for Solving the Problems) The thermal decomposition treatment method for radioactive chemical decontamination waste liquid of the present invention is a method for thermally decomposing radioactive chemical decontamination waste liquid, which uses organic acids, chelating agents, and chelating agents generated in the nuclear 1M stage.
1. Radioactive chemical decontamination waste liquid containing compounds is heated in an oxidizing atmosphere to thermally decompose it, and the generated water vapor and thermal decomposition gas are each treated in a scientific system and discharged outside the system. The remaining radioactive metal oxide is stored in a storage container, and the thermal decomposition treatment apparatus for radioactive chemical decontamination waste liquid of the present invention includes a thermal decomposition column containing a fluidized bed forming material, and this thermal decomposition column. A heated gas supply system that supplies heated gas into the tower from the bottom of the pyrolysis tower, and a waste liquid supply system that supplies radioactive chemical decontamination waste liquid containing organic acid, chelating agents, and chelate compounds generated at nuclear facilities into this pyrolysis tower. , an exhaust treatment system for treating water vapor and pyrolysis gas generated in the pyrolysis tower, and a decomposition residue treatment system for discharging radioactive metal oxides remaining in the pyrolysis tower and filling them into a storage container. It is characterized by having the following.
(作用)
本発明の熱分解処理方法においては、化学除染剤の主成
分となっているクエン酸、シュウ酸、ギ酸のような有機
酸、EDTAのようなキレート剤J5.J、びキレート
化合物が、酸化雰囲気下の加熱により熱分解し、水蒸気
とCo、CO2、No、N02.1−12等の熱分解ガ
スを発生する。そしてキレート化合物中の金属、フリー
の金属イオン、金属水酸化物等は酸化されて金属酸化物
となる。(Function) In the thermal decomposition treatment method of the present invention, organic acids such as citric acid, oxalic acid, and formic acid, which are the main components of the chemical decontamination agent, and chelating agents such as EDTA J5. The J and chelate compounds are thermally decomposed by heating in an oxidizing atmosphere, generating water vapor and thermal decomposition gases such as Co, CO2, No, and N02.1-12. Then, the metal, free metal ions, metal hydroxide, etc. in the chelate compound are oxidized to become metal oxides.
ここで生成された水蒸気や熱分解ガスは凝縮器を含む排
気処理系で処理される。一方、放射性化学除染廃液中の
放射能の大部分を含む分解残渣の金属酸化物スラッジは
、移送してスラッジ貯蔵容器に貯蔵される。The steam and pyrolysis gas generated here are treated in an exhaust treatment system that includes a condenser. Meanwhile, the decomposition residue metal oxide sludge containing most of the radioactivity in the radioactive chemical decontamination waste liquid is transferred and stored in a sludge storage container.
(実施例)
以下、本発明の一実施例を図面を参照しながら説明する
。 −
第1図は本発明の一実施例の放射性化学除染廃液の熱分
解処理装置の構成を概略的に示す図である。(Example) Hereinafter, an example of the present invention will be described with reference to the drawings. - FIG. 1 is a diagram schematically showing the configuration of a thermal decomposition treatment apparatus for radioactive chemical decontamination waste liquid according to an embodiment of the present invention.
この実施例の熱分解処理装置は、第1図に示すように、
熱分解塔10、加熱気体供給系20、放射性化学除染廃
液供給系30、排気処理系40、分解残渣処理系50を
主体として構成されている。As shown in FIG. 1, the pyrolysis treatment apparatus of this embodiment has the following features:
It is mainly composed of a thermal decomposition tower 10, a heated gas supply system 20, a radioactive chemical decontamination waste liquid supply system 30, an exhaust treatment system 40, and a decomposition residue treatment system 50.
熱分解塔10は縦形容器であってスクリーン11により
上下2室に分けられ、上部室12には粒径が数μ■〜数
百μmの鉄粉または酸化鉄粉からなる熱媒体粒子13が
充填されている。The pyrolysis tower 10 is a vertical container divided into two upper and lower chambers by a screen 11, and the upper chamber 12 is filled with heat carrier particles 13 made of iron powder or iron oxide powder with a particle size of several μm to several hundred μm. has been done.
加熱気体供給系20は、熱分解塔10の頂部に11旧」
する水蒸気・排ガス排出管β1に一喘を接続し、他端を
熱分解塔10の下部室14に接続された循環配管p2と
、この循環配管、22の途中に接続された、循還元弁2
1、ブロア22、ヒータ23Lt3よび循環弁24とか
ら構成されている。The heated gas supply system 20 is connected to the top of the pyrolysis column 10.
A circulation pipe p2 is connected at one end to the steam/exhaust gas discharge pipe β1 and the other end is connected to the lower chamber 14 of the pyrolysis tower 10, and a circulation return valve 2 connected in the middle of this circulation pipe 22.
1, a blower 22, a heater 23Lt3, and a circulation valve 24.
放射性化学除染廃液供給系30は、原子htii設で発
生した有機酸、キレート剤およびキレート化合物を含む
放射性化学除染廃液を収容した廃液りンク31、この廃
液タンク31と熱分解塔10の頂部とを結ぶ廃液供給管
J:13およびこの廃液供給管J23の途中に接続され
た廃液供給ポンプ32、廃液供給弁33とからなる。The radioactive chemical decontamination waste liquid supply system 30 includes a waste liquid link 31 containing radioactive chemical decontamination waste liquid containing an organic acid, a chelating agent, and a chelate compound generated in the atomic htii facility, this waste liquid tank 31, and the top of the pyrolysis tower 10. It consists of a waste liquid supply pipe J:13 connecting the waste liquid supply pipe J:13, a waste liquid supply pump 32, and a waste liquid supply valve 33 connected in the middle of this waste liquid supply pipe J23.
排気処理系40は、水蒸気・排ガス排出管λ1に排気弁
41、排気流量調整弁42を介して接続されたコンデン
サ43と、このコンデンナ43の気相部にベント弁44
を介して接続された排気管λ4とを有しており、コンデ
ンサ43には冷却水弁45を介して冷却水注入管β5と
、凝縮水弁46を介して凝縮水移送管β6が接続されて
いる。The exhaust treatment system 40 includes a condenser 43 connected to the water vapor/exhaust gas discharge pipe λ1 via an exhaust valve 41 and an exhaust flow rate adjustment valve 42, and a vent valve 44 in the gas phase of the condenser 43.
A cooling water injection pipe β5 is connected to the condenser 43 via a cooling water valve 45, and a condensed water transfer pipe β6 is connected to the condenser 43 via a condensed water valve 46. There is.
さらに分解残渣排出系50は、それぞれ熱分解塔10に
接続された、移送水弁51を備えた移送水注入管ぶ7と
、空気注入弁52を備えた空気注入管β8と、スラッジ
移送弁53を備えたスラッジ移送管ぶ9とから構成され
ている。Further, the decomposition residue discharge system 50 includes a transfer water injection pipe 7 equipped with a transfer water valve 51, an air injection pipe β8 equipped with an air injection valve 52, and a sludge transfer valve 53, which are connected to the pyrolysis tower 10, respectively. It is composed of a sludge transfer pipe 9 equipped with a sludge transfer pipe 9.
次にこの装置を用いた放射性化学除染廃液の処理方法を
第2図および第3図を参照しながら説明する。Next, a method for treating radioactive chemical decontamination waste liquid using this apparatus will be explained with reference to FIGS. 2 and 3.
なお第2図および第3図に示した各種弁のうち括弧を付
していない弁は開状態にあることを示し、符号を付した
弁は閉状態にあることを示している。Of the various valves shown in FIGS. 2 and 3, valves without parentheses indicate that they are in an open state, and valves with symbols indicate that they are in a closed state.
放射性化学除染廃液の熱分解処理を行うに際しては、第
2図に示すように、まず加熱気体供給系20の循環元弁
21、循環弁24を開ぎブロワ22およびヒーター23
を起動させて熱風を熱分解塔10の下部から送入し、熱
媒体粒子13を200°C以上に加熱するととらに流動
層を形成さける。When carrying out thermal decomposition treatment of radioactive chemical decontamination waste liquid, as shown in FIG.
is activated to send hot air from the lower part of the pyrolysis tower 10 to heat the heat carrier particles 13 to 200° C. or higher, while also forming a fluidized bed.
次いで廃液タンク31からを液供給ポンプ32により廃
液元弁33を介して放射性化学除染廃液を熱分解塔10
に供給し、その上部から噴霧する。Next, the radioactive chemical decontamination waste liquid is transferred from the waste liquid tank 31 by the liquid supply pump 32 through the waste liquid main valve 33 to the thermal decomposition tower 10.
and spray from the top.
熱媒体粒子13からなる流動層上に落下した放射性化学
除染廃液は熱媒体粒子13からの伝熱により、水分が蒸
発され、また溶解していたクエン酸、シュウ酸、ギ酸の
ような有機酸、EDTAのようなキレート剤およびキレ
ート化合物等は熱分解して水蒸気とCo、CO2、NO
,NO2、ト12等の熱分解ガスを生成し、金属分は金
属酸化物となる。このうち水蒸気と熱分解ガスは熱分解
塔10の−F部から水蒸気・排カス排出管J2.1を通
って排出され循環元弁21を介して循環配管β2中に入
り、ヒータ23により加熱されつつ熱分解塔10と水蒸
気・排ガス排出管β1との間を循環して放射性化学除染
廃液を加熱、分解する。The radioactive chemical decontamination waste liquid that has fallen onto the fluidized bed made of heat transfer particles 13 has its water evaporated due to heat transfer from the heat transfer particles 13, and dissolved organic acids such as citric acid, oxalic acid, and formic acid. , chelating agents and chelate compounds such as EDTA are thermally decomposed to produce water vapor and Co, CO2, NO.
, NO2, and 12 are generated, and the metal components become metal oxides. Of these, steam and pyrolysis gas are discharged from the -F section of the pyrolysis tower 10 through the steam/waste discharge pipe J2.1, enter the circulation pipe β2 via the circulation source valve 21, and are heated by the heater 23. The radioactive chemical decontamination waste liquid is heated and decomposed by circulating between the pyrolysis tower 10 and the steam/exhaust gas discharge pipe β1.
放射性化学除染廃液の熱分解処理で発生した水蒸気と熱
分解ガスが増加して加熱気体供給系の内圧が上2′する
と、排気弁41と排気流量調整弁42が聞かれ循環気体
の一部がコンデンサ43に送られる。When the internal pressure of the heated gas supply system rises by 2' due to the increase in water vapor and pyrolysis gas generated during the pyrolysis treatment of radioactive chemical decontamination waste liquid, the exhaust valve 41 and the exhaust flow rate adjustment valve 42 are turned on and a portion of the circulating gas is removed. is sent to the capacitor 43.
この循環気体の一部の排気は、排気弁41と排気流量調
節弁42とを常時開として熱分解処理工程中連続的に排
気さけること−し可能であり、また初見時にブロア22
を停止して、加熱循環と排気とを交互に行なうことによ
り、循環加熱流体中に混入した金属酸化物スラッジと熱
媒体粒子13の流出を避けるようにしてもよい。Part of this circulating gas can be exhausted by keeping the exhaust valve 41 and the exhaust flow rate control valve 42 open at all times to avoid exhausting the gas continuously during the thermal decomposition process.
The metal oxide sludge and heat medium particles 13 mixed in the circulating heating fluid may be prevented from flowing out by stopping the heating circulation and exhausting the heating fluid alternately.
コンデンサ−43に送られた循環気体中の水蒸気は冷却
されて凝縮水となり、空気や熱分解ガスはベント弁44
を通して既存の排気設備に排出される。なおコンデンサ
−43は、冷却水弁45を通つて供給された冷却水で冷
却され、水蒸気と熱分解ガスの熱を吸収した冷却水と水
蒸気の凝縮水とは凝縮水弁46を通って凝縮水移送管β
6により既存の放射性廃棄物処11設漏へ送られて処理
される。Water vapor in the circulating gas sent to the condenser 43 is cooled and becomes condensed water, and air and pyrolysis gas are sent to the vent valve 44.
is discharged through the existing exhaust system. The condenser 43 is cooled with cooling water supplied through the cooling water valve 45, and the cooling water that has absorbed the heat of the steam and pyrolysis gas and the condensed water of the steam are converted into condensed water through the condensed water valve 46. Transfer pipe β
6, the waste is sent to the existing radioactive waste disposal facility 11 for treatment.
一方、熱分解塔10中の熱分解により生じたキレート化
合物中の金属、フリーの金属イオンあるいは金属水酸化
物等は酸化されて金属酸化物として残留し、この金属酸
化物スラッジは乾固して微粉末となり、熱媒体粒子13
とともに流動層粒子の一部を構成する。On the other hand, metals, free metal ions, metal hydroxides, etc. in the chelate compound generated by thermal decomposition in the pyrolysis tower 10 are oxidized and remain as metal oxides, and this metal oxide sludge is dried and solidified. It becomes a fine powder and becomes heat carrier particles 13.
Together with these particles, they form part of the fluidized bed particles.
このようにして塔内には金属酸化物スラッジのみが蓄積
され、所定量が蓄積されたところで、第3図に示すよう
にブロア22とヒータ23を停止し、廃液供給弁33と
循環元弁21と循環弁24とを開にし、代わりに移送水
弁51と空気元弁52とスラッジ移送弁53とを開にし
て熱分解塔10内へ移送水と空気を注入し、熱分解塔1
0内の熱媒体粒子13と金属酸化物スラッジとを移送水
中に懸濁撹拌ざV、移送水とともに図示を省略したスラ
ッジ貯蔵タンクへ排出する。なお注入した空気は水恭気
・排ガス排出管β1から排気設備へυ1出される。In this way, only metal oxide sludge is accumulated in the tower, and when a predetermined amount has been accumulated, the blower 22 and heater 23 are stopped, and the waste liquid supply valve 33 and circulation source valve 21 are stopped, as shown in FIG. and circulation valve 24, and instead open the transfer water valve 51, air source valve 52, and sludge transfer valve 53 to inject transfer water and air into the pyrolysis tower 10.
The heat transfer medium particles 13 and metal oxide sludge in the transfer water are suspended in the transfer water through an agitation tube V, and discharged together with the transfer water to a sludge storage tank (not shown). Note that the injected air is discharged from the water/air/exhaust gas discharge pipe β1 to the exhaust equipment υ1.
な、9以上の実施例では、ヒータ23のみを熱源として
加熱分解を行なった例について説明したが、廃液供給系
30や熱分解塔10にヒータを取付けて放射性化学除染
廃液の予熱や熱分解塔10の外部加熱を行なうようにし
てもよい。In the above embodiments, an example was described in which thermal decomposition was performed using only the heater 23 as a heat source. The column 10 may also be heated externally.
[発明の効果]
以上説明したように本発明によれば、bt’J’J性化
学除染廃液を熱分解処理して放射性化学除染廃液中の有
機酸、キレート剤およびキレート化合物を熱分解して水
蒸気、熱分解ガスおよび金属酸化物としたので既存のI
J!l射性廃棄物処理設備で容易に処理することが可能
である。[Effects of the Invention] As explained above, according to the present invention, bt'J'J chemical decontamination waste liquid is thermally decomposed to thermally decompose organic acids, chelating agents, and chelate compounds in the radioactive chemical decontamination waste liquid. Since the water vapor, pyrolysis gas and metal oxide were
J! It can be easily disposed of using radioactive waste treatment equipment.
本発明によれば、tiJIQ旧生化学除染廃液のための
専用の固化装置や高濃度放射能を含んだ放射性化学除染
廃液の同化体を貯蔵するための貯蔵設面が不要となり、
高い減容率を達成することができる。According to the present invention, there is no need for a dedicated solidification device for tiJIQ old biochemical decontamination waste liquid or a storage facility for storing assimilated radioactive chemical decontamination waste liquid containing high concentration radioactivity.
A high volume reduction rate can be achieved.
また敢則線被爆の多い放射性化学除染廃液の固化作業お
よび固化体の取扱作業が不要となって、設備費、および
除染作用に伴なう敢則線被爆が大幅に低減され、原子力
発電所等の原子力施設にお(プる化学除染処理をより容
易に行なうことが可能となる。In addition, solidification of radioactive chemical decontamination waste liquid and handling of solidified waste, which are often exposed to radiation from radiation, are no longer necessary, and equipment costs and exposure to radiation from radiation caused by decontamination are significantly reduced, and nuclear power generation This makes it easier to carry out chemical decontamination treatment at nuclear facilities such as nuclear facilities.
第1図は本発明の放射性化学除染廃液の熱分前処]!I
l!装置の描込を概略的に示す図、第2図は本発明の方
法の熱分解工程を説明するための図、第3図は本発明の
方法のスラッジ移送工程を説明するための図である。
10・・・・・・・・・熱分解塔
11・・・・・・・・・スクリーン
12・・・・・・・・・上部室
13・・・・・・・・・熱媒体粒子
14・・・・・・・・・下部室
20・・・・・・・・・加熱気体供給系21・・・・・
・・・・循環元弁
22・・・・・・・・・ブロア
23・・・・・・・・・ヒータ
24・・・・・・・・・循環弁
30・・・・・・・・・廃液供給系
31・・・・・・・・・廃液タンク
32・・・・・・・・・廃液供給ポンプ33・・・・・
・・・・廃液供給弁
40・・・・・・・・・排気凝縮系
41・・・・・・・・・排気弁
42・・・・・・・・・排気流量調整弁43・・・・・
・・・・コンデンサ
44・・・・・・・・・ベント弁
45・・・・・・・・・冷却水弁
46・・・・・・・・・凝縮水弁47
50・・・・・・・・・分解残漬排出装置51・・・・
・・・・・移送水弁
52・・・・・・・・・空気元弁
53・・・・・・・・・スラッジ移送弁代理人 弁理士
則 近 憲 缶
周 三俣弘文Figure 1 shows the thermal pretreatment of radioactive chemical decontamination waste liquid according to the present invention]! I
l! A diagram schematically showing a drawing of the apparatus, FIG. 2 is a diagram for explaining the pyrolysis step of the method of the present invention, and FIG. 3 is a diagram for explaining the sludge transfer step of the method of the present invention. . 10...Pyrolysis tower 11...Screen 12...Upper chamber 13...Heat carrier particles 14 ...... Lower chamber 20 ... Heated gas supply system 21 ...
...Circulation source valve 22...Blower 23...Heater 24...Circulation valve 30...・Waste liquid supply system 31... Waste liquid tank 32... Waste liquid supply pump 33...
... Waste liquid supply valve 40 ... Exhaust condensing system 41 ... Exhaust valve 42 ... Exhaust flow rate adjustment valve 43 ...・・・
...Condenser 44...Vent valve 45...Cooling water valve 46...Condensed water valve 47 50... ... Decomposition residue discharge device 51 ...
・・・・・・Transfer water valve 52・・・・・・・・・Air source valve 53・・・・・・・・・Sludge transfer valve agent Patent attorney Nori Chika Ken Shu Kanshu Hirofumi Mitsumata
Claims (2)
キレート化合物を含む放射性化学除染廃液を酸化性雰囲
気下で加熱して熱分解させ、発生した水蒸気と熱分解ガ
スとを排気処理系で処理して系外に排出するとともに、
残留した放射性金属酸化物を貯蔵容器に貯蔵することを
特徴とする放射性化学除染廃液の熱分解処理方法。(1) Radioactive chemical decontamination waste liquid containing organic acids, chelating agents, and chelate compounds generated at nuclear facilities is heated in an oxidizing atmosphere to thermally decompose it, and the generated water vapor and thermal decomposition gas are treated in an exhaust treatment system. and discharge it out of the system,
A method for thermally decomposing radioactive chemical decontamination waste liquid, the method comprising storing residual radioactive metal oxides in a storage container.
解塔の下部から塔内に加熱気体を供給する加熱気体供給
系と、この熱分解塔内へ原子力施設で発生した有機酸、
キレート剤およびキレート化合物を含む放射性化学除染
廃液を供給する廃液供給系と、前記熱分解塔内で発生し
た水蒸気と熱分解ガスとを処理する排気処理系と、前記
熱分解塔内に残留した放射性金属酸化物を排出して貯蔵
容器に充填する分解残渣処理系とを有することを特徴と
する放射性化学除染廃液の熱分解処理装置。(2) A pyrolysis tower containing a fluidized bed forming material, a heated gas supply system that supplies heated gas from the lower part of the pyrolysis tower into the tower, and an organic acid generated at a nuclear facility into the pyrolysis tower.
a waste liquid supply system that supplies a radioactive chemical decontamination waste liquid containing a chelating agent and a chelate compound; an exhaust treatment system that processes water vapor and pyrolysis gas generated in the pyrolysis tower; 1. A thermal decomposition treatment apparatus for radioactive chemical decontamination waste liquid, comprising a decomposition residue treatment system for discharging radioactive metal oxides and filling them into a storage container.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP20155586A JPS6358299A (en) | 1986-08-29 | 1986-08-29 | Pyrolytic processing method and pyrolytic processor for radioactive chemically decontaminated waste liquor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP20155586A JPS6358299A (en) | 1986-08-29 | 1986-08-29 | Pyrolytic processing method and pyrolytic processor for radioactive chemically decontaminated waste liquor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6358299A true JPS6358299A (en) | 1988-03-14 |
Family
ID=16442986
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP20155586A Pending JPS6358299A (en) | 1986-08-29 | 1986-08-29 | Pyrolytic processing method and pyrolytic processor for radioactive chemically decontaminated waste liquor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6358299A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2005315641A (en) * | 2004-04-27 | 2005-11-10 | Toshiba Corp | Treating method and treating device of decontamination waste liquid |
-
1986
- 1986-08-29 JP JP20155586A patent/JPS6358299A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2005315641A (en) * | 2004-04-27 | 2005-11-10 | Toshiba Corp | Treating method and treating device of decontamination waste liquid |
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