JPH0752238B2 - Radiocarbon treatment method - Google Patents
Radiocarbon treatment methodInfo
- Publication number
- JPH0752238B2 JPH0752238B2 JP1110883A JP11088389A JPH0752238B2 JP H0752238 B2 JPH0752238 B2 JP H0752238B2 JP 1110883 A JP1110883 A JP 1110883A JP 11088389 A JP11088389 A JP 11088389A JP H0752238 B2 JPH0752238 B2 JP H0752238B2
- Authority
- JP
- Japan
- Prior art keywords
- radiocarbon
- radioactive
- treatment method
- gas
- waste
- 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.)
- Expired - Lifetime
Links
- 238000000034 method Methods 0.000 title claims description 18
- 239000002699 waste material Substances 0.000 claims description 18
- 239000007788 liquid Substances 0.000 claims description 17
- 229910052799 carbon Inorganic materials 0.000 claims description 15
- 230000002285 radioactive effect Effects 0.000 claims description 14
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 13
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 claims description 11
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 claims description 11
- 239000002901 radioactive waste Substances 0.000 claims description 11
- 239000007789 gas Substances 0.000 claims description 7
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 7
- AYJRCSIUFZENHW-UHFFFAOYSA-L barium carbonate Chemical compound [Ba+2].[O-]C([O-])=O AYJRCSIUFZENHW-UHFFFAOYSA-L 0.000 claims description 6
- RQPZNWPYLFFXCP-UHFFFAOYSA-L barium dihydroxide Chemical compound [OH-].[OH-].[Ba+2] RQPZNWPYLFFXCP-UHFFFAOYSA-L 0.000 claims description 6
- 229910001863 barium hydroxide Inorganic materials 0.000 claims description 6
- 239000011347 resin Substances 0.000 claims description 6
- 229920005989 resin Polymers 0.000 claims description 6
- 238000007711 solidification Methods 0.000 claims description 6
- 230000008023 solidification Effects 0.000 claims description 6
- 239000000126 substance Substances 0.000 claims description 6
- 239000003054 catalyst Substances 0.000 claims description 5
- 239000010949 copper Substances 0.000 claims description 4
- -1 iron ion Chemical class 0.000 claims description 4
- 239000010426 asphalt Substances 0.000 claims description 3
- 239000004568 cement Substances 0.000 claims description 3
- 229910052742 iron Inorganic materials 0.000 claims description 3
- JPVYNHNXODAKFH-UHFFFAOYSA-N Cu2+ Chemical compound [Cu+2] JPVYNHNXODAKFH-UHFFFAOYSA-N 0.000 claims description 2
- 239000012736 aqueous medium Substances 0.000 claims description 2
- 229910001431 copper ion Inorganic materials 0.000 claims description 2
- 238000006243 chemical reaction Methods 0.000 description 8
- 235000019441 ethanol Nutrition 0.000 description 7
- 238000006864 oxidative decomposition reaction Methods 0.000 description 6
- 239000005416 organic matter Substances 0.000 description 5
- 238000001179 sorption measurement Methods 0.000 description 5
- 239000002912 waste gas Substances 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- OKKJLVBELUTLKV-UHFFFAOYSA-N Methanol Chemical compound OC OKKJLVBELUTLKV-UHFFFAOYSA-N 0.000 description 3
- 229910002091 carbon monoxide Inorganic materials 0.000 description 3
- 229910052760 oxygen Inorganic materials 0.000 description 3
- 239000004215 Carbon black (E152) Substances 0.000 description 1
- OKTJSMMVPCPJKN-NJFSPNSNSA-N Carbon-14 Chemical compound [14C] OKTJSMMVPCPJKN-NJFSPNSNSA-N 0.000 description 1
- 239000011398 Portland cement Substances 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 150000001298 alcohols Chemical class 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- 229910001430 chromium ion Inorganic materials 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 125000001495 ethyl group Chemical group [H]C([H])([H])C([H])([H])* 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 239000002808 molecular sieve Substances 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- BDERNNFJNOPAEC-UHFFFAOYSA-N propan-1-ol Chemical compound CCCO BDERNNFJNOPAEC-UHFFFAOYSA-N 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- URGAHOPLAPQHLN-UHFFFAOYSA-N sodium aluminosilicate Chemical compound [Na+].[Al+3].[O-][Si]([O-])=O.[O-][Si]([O-])=O URGAHOPLAPQHLN-UHFFFAOYSA-N 0.000 description 1
- QAOWNCQODCNURD-UHFFFAOYSA-N sulfuric acid Substances OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Separation, Recovery Or Treatment Of Waste Materials Containing Plastics (AREA)
Description
本発明は、放射性廃棄物中の放射性炭素、とくに14Cを
分離固定する処理方法に関する。The present invention relates to a treatment method for separating and fixing radioactive carbon, particularly 14 C, in radioactive waste.
原子力発電所から出る放射性廃棄物中の14Cは、微量で
はあるが半減期が長い放射性同位元素であるから、固定
化処理をする必要がある。 ガス状の化合物（主としてCOやCO2のような無機物また
はCH4のような低級の有機物）の形をとっている14Cに関
しては、酸化してすべてを14CO2の形にし、吸収または
吸着により固定して廃ガスから除去することが提案され
た（特開昭56−84597）。 CO2の固定には、アルカリ性物質との反応やモレキュラ
ーシーブへの吸着など多くの方法があるが、最も除去率
が高く、かつ生成物も安全で安定なのが、水酸化バリウ
ムBa(OH)2・8H2Oとの化学反応によるものである。 一方、使用ずみイオン交換樹脂（とくに原子力発電所で
発生する「一次系廃樹脂」とよばれるもの）や種々の放
射性廃液（通常は濃縮して固化処理する）中では、放射
性炭素14Cが有機物の形態をとっている可能性がある。
このような廃棄物中の放射性炭素の化学的質量それ自体
は、ごく微量である。 上記の（一次系）廃樹脂を減容する技術は種々提案され
ているが、処理法それ自体が最も安全なものは湿式酸化
分解、とくに過酸化水素による酸化であって、触媒とし
ての鉄イオンおよび（または）クロムイオンの存在下
に、温度約100℃、圧力は常圧で、H2O2を作用させる技
術が確立されている（特開昭57−1446）。 一方、濃縮廃液については、たとえばセメント固化、ア
スファルト固化等が実用化されている。 つまり、いままでは放射性炭素14Cは廃ガス処理の対象
核種でしかなかった。Since 14 C in radioactive waste from nuclear power plants is a radioisotope with a small amount but a long half-life, it needs to be immobilized. For 14 C in the form of gaseous compounds (mainly inorganics like CO and CO 2 or lower organics like CH 4 ), oxidize everything into 14 CO 2 and absorb or adsorb it. It has been proposed to fix it and remove it from waste gas (JP-A-56-84597). There are many methods for fixing CO 2 , such as reaction with alkaline substances and adsorption on molecular sieves, but the highest removal rate and safe and stable product are barium hydroxide Ba (OH) 2・ This is due to a chemical reaction with 8H 2 O. On the other hand, in used ion-exchange resins (particularly called "primary waste resin" generated in nuclear power plants) and various radioactive waste liquids (usually concentrated and solidified), radioactive carbon 14 C is an organic matter. May take the form of.
The chemical mass of radiocarbon in such waste itself is very small. Various techniques for reducing the volume of the above (primary) waste resin have been proposed, but the safest treatment method itself is wet oxidative decomposition, particularly oxidation with hydrogen peroxide, and iron ion as a catalyst. A technique has been established in which H 2 O 2 is allowed to act in the presence of and / or chromium ions at a temperature of about 100 ° C. and normal pressure (Japanese Patent Laid-Open No. 57-1446). On the other hand, for the concentrated waste liquid, solidification of cement, solidification of asphalt and the like have been put into practical use. In other words, until now, radiocarbon 14 C was the only target nuclide for waste gas treatment.
本発明の目的は、上記したような技術を利用し、放射性
廃棄物中の放射性炭素をすべて無機物CO2の形に変えて
分離固定することにより、固化体中に有機形態で残存す
ることのないようにした放射性炭素の処理方法を提供す
ることにある。The object of the present invention is to prevent all the radioactive carbon in radioactive waste from being converted into the form of inorganic matter CO 2 and separated and fixed by using the above-mentioned technique, so that it does not remain in the solidified form in the organic form. Another object of the present invention is to provide a method for treating radioactive carbon.
上記の目的を達成する本発明の放射性炭素の処理方法
は、放射性炭素を有機物の形態で含有する放射性廃棄物
に対し、水性媒体中で、水溶性の低級アルコールの共存
と、触媒としての銅イオンおよび（または）鉄イオンの
存在の下に過酸化水素を作用させ、上記放射性炭素含有
有機物および低級アルコールをともに酸化分解すること
により放射性炭素をCO2ガスとして分離し、分離されたC
O2ガスを水酸化バリウムと接触させて炭酸バリウムとし
て固定することからなる。The method for treating radioactive carbon of the present invention which achieves the above-mentioned object, is a radioactive waste containing radioactive carbon in the form of an organic substance, in an aqueous medium, the coexistence of a water-soluble lower alcohol, and copper ion as a catalyst. Hydrogen peroxide is allowed to act in the presence of and / or iron ions to oxidize and decompose both the above-mentioned radioactive carbon-containing organic matter and lower alcohol to separate radioactive carbon as CO 2 gas, and the separated C
It consists of contacting O 2 gas with barium hydroxide to fix it as barium carbonate.
第１図を参照して説明すれば、酸化分解はジャケットつ
きの反応器（１）において行なうのが適当である。処理
の対象とする放射性廃棄物は、前述の一次系廃樹脂、濃
縮廃液のほか、液体用フィルターに捕捉されたクラッド
を再溶解したときに生じた廃液などがある。 低級アルコールは、メタノール、エタノール、プロパノ
ールなど、低分子量で水溶性のアルコールを意味する。
この種のアルコールは、炭化水素がいわば低度に酸化さ
れた状態にあって、H2O2により容易に酸化されたH2OとC
O2になる。これが放射性炭素を含有する有機物をH2O2で
酸化して最終的にH2OとCO2とにする反応に対して、どの
ような機構か明らかでないが、促進作用をもつようであ
る。従ってその使用量は、酸化分解を行なう系に対して
数十〜数百ppmの少量で足りる。 触媒としてのCu2+やFe2+の使用を含め、H2O2による湿式
酸化分解の反応条件は、一次系廃樹脂や濃縮廃液の処理
に関して見出されている好適条件を採用すればよい。代
表的には、触媒の濃度はCu2+:5〜50mmol/lまたはFe2+:5
〜50mmol/l、併用の場合はCu2+＋Fe2+:5〜50mmol/lであ
り、pHは酸を加えて１〜５に調節する。温度は50℃以上
ほぼ100℃とし、発生した水蒸気はコンデンサー（２）
に導いて凝縮させる。 コンデンサーを通過したガスは、好ましくは予熱器
（３）を通して50〜100℃程度に温度を高め、吸着塔
（４）に送ってBa(OH)2・8H2Oと接触させ、炭酸バリウ
ムBaCO3として固定する。 なお、水酸化バリウム吸着塔出口の廃ガス組成は、放射
能の拡散を防ぐ目的で若干の負圧操作をしているため、
ほとんど空気組成に近く、過酸化水素が分解して生じた
未反応酸素が少量加わっている。 廃ガスは、さらにHEPAフィルター等で処理し、放射能濃
度の基準をみたしていることを確認した上で大気中に放
出する。 酸化分解反応は、一般に系に処理すべき放射性廃棄物を
連続的または断続的に供給し、過酸化水素水を連続的ま
たは断続的に供給し、発生した水蒸気を上記のように凝
縮により除去して濃縮しつつ行なう、半回分式が適当で
ある。ある程度まで濃縮された液は、たとえばセメント
固化法により、すなわちミキサー（５）でポルトランド
セメントと混練してドラム缶（６）に注入し固化させる
方法で固化処理する。アスファルト固化法によって固化
してもよいことはもちろんである。Referring to FIG. 1, oxidative decomposition is suitably carried out in a jacketed reactor (1). The radioactive wastes to be treated include the above-mentioned primary waste resin, concentrated waste liquid, and waste liquid generated when the clad captured by the liquid filter is redissolved. The lower alcohol means a low molecular weight, water-soluble alcohol such as methanol, ethanol, and propanol.
Alcohols of this kind, in a state in which the hydrocarbon is oxidized as it were in a low degree, H 2 O 2 by easily oxidized between H 2 O and C
It becomes O 2 . It is not clear what mechanism this is for the reaction of radiocarbon-containing organic matter with H 2 O 2 to finally form H 2 O and CO 2 , but it seems to have a promoting action. Therefore, the amount used is as small as several tens to several hundreds of ppm with respect to the system for oxidative decomposition. The reaction conditions for wet oxidative decomposition with H 2 O 2 , including the use of Cu 2+ and Fe 2+ as catalysts, may be the suitable conditions found for the treatment of primary waste resin and concentrated waste liquid. . Typically, the concentration of the catalyst is Cu 2+: 5~50mmol / l or Fe 2+: 5
˜50 mmol / l, Cu 2+ + Fe 2+ : 5 to 50 mmol / l when used in combination, and pH is adjusted to 1 to 5 by adding acid. The temperature is 50 ℃ or more and almost 100 ℃, and the generated water vapor is stored in the condenser (2).
Lead to and condense. The gas passed through the condenser is preferably heated through a preheater (3) to a temperature of about 50 to 100 ° C., sent to the adsorption tower (4) and brought into contact with Ba (OH) 2 .8H 2 O, and barium carbonate BaCO 3 To fix as. The composition of the waste gas at the outlet of the barium hydroxide adsorption tower is slightly negative pressure operation for the purpose of preventing the diffusion of radioactivity,
Almost close to the air composition, a small amount of unreacted oxygen generated by decomposition of hydrogen peroxide is added. Waste gas will be further processed with a HEPA filter, etc., and it will be released into the atmosphere after confirming that it meets the radioactive concentration standards. In the oxidative decomposition reaction, generally, radioactive waste to be treated is continuously or intermittently supplied, hydrogen peroxide solution is continuously or intermittently supplied, and the generated water vapor is removed by condensation as described above. The semi-batch method, which is carried out while concentrating the solution, is suitable. The liquid concentrated to a certain extent is solidified by, for example, a cement solidification method, that is, a method in which it is kneaded with Portland cement in a mixer (5), poured into a drum can (6) and solidified. Of course, it may be solidified by the asphalt solidification method.
処理の対象として、原子力発電所から発生したホウ酸３
％濃縮廃液をとりあげた。この濃縮廃液中の放射性炭素
濃度は10-2μCi/mlである。 ジャケット付きで攪拌機をそなえた容積120lの反応容器
を用意し、上記の濃縮廃液100lを入れ、触媒としてFeSO
4・7H2Oを400g投入し、濃硫酸5Kgを添加してpHを３にし
た。 ジャケット加熱により液の温度を100℃に高め、その温
度を維持しながら、あらかじめエチルアルコールを加え
てその濃度を100ppmにした濃縮廃液と、35％過酸化水素
水とを連続的に供給した。供給速度と時間は、エチルア
ルコール添加濃縮廃液が40l/hr×12.5時間、35％過酸化
水素水が3l/hr×15時間である。 反応容器から発生する水蒸気は、コンデンサーで全量を
凝縮させ、分離した。コンデンサーを出たガスは、小塊
状の水酸化バリウムを充填した塔を通してから放出し
た。 この操作により600lの濃縮廃液が酸化分解処理を受け、
100lに濃縮された。濃縮された液中の放射性炭素の濃度
は10-5μCi/mlに低下しており、TOCは1ppm未満であっ
た。水酸化バリウム吸着塔出口のCO2濃度は1ppm未満で
あって、炭素のほぼ完全な固定が行なわれたことが確認
できた。また、凝縮水は放射性物質を実質上含有してい
なかった。Boric acid generated from a nuclear power plant as a target of treatment 3
% Concentrated waste liquid was taken up. The concentration of radiocarbon in this concentrated waste liquid is 10 -2 μCi / ml. Prepare a reaction vessel with a jacket and a stirrer and a volume of 120 liters.
4 · 7H 2 O was 400g charged and the pH 3 by addition of concentrated sulfuric acid 5Kg. The temperature of the liquid was raised to 100 ° C. by heating the jacket, and while maintaining the temperature, a concentrated waste liquid in which ethyl alcohol had been added to make the concentration 100 ppm and 35% hydrogen peroxide solution were continuously supplied. The supply rate and time are 40 l / hr × 12.5 hours for ethyl alcohol-added concentrated waste liquid and 3 l / hr × 15 hours for 35% hydrogen peroxide solution. The water vapor generated from the reaction vessel was condensed by a condenser and separated. The gas leaving the condenser was discharged through a column packed with barium hydroxide in the form of small pieces. By this operation, 600 l of concentrated waste liquid undergoes oxidative decomposition treatment,
It was concentrated to 100 l. The concentration of radiocarbon in the concentrated liquid decreased to 10 -5 μCi / ml, and TOC was less than 1 ppm. The CO 2 concentration at the outlet of the barium hydroxide adsorption tower was less than 1 ppm, confirming that carbon was almost completely fixed. The condensed water contained substantially no radioactive substance.
本発明により、原子力発電所から発生する放射性廃棄物
とくに一次系廃樹脂や濃縮廃液に含まれている放射性炭
素（主に14C）を、有機物の形態からCO2の形に変えて分
離し、安定なBaCO3の形で固定することにより、減容固
化された廃棄物中に有機物形態の放射性炭素を残存させ
ることなく処理するトータルシステムが完成した。According to the present invention, radioactive waste generated from a nuclear power plant, particularly radioactive carbon (mainly 14 C) contained in primary waste resin and concentrated waste liquid is separated from the form of organic matter in the form of CO 2 , and separated. By fixing it in the form of stable BaCO 3 , a total system has been completed that treats radioactive carbon in the form of organic matter without remaining in the volume-solidified waste.
第１図は、本発明の放射性炭素の処理方法を説明するた
めの、反応容器を中心とする装置構成とフローを示した
概念的な図である。 １…反応容器、２…コンデンサー ３…予熱器、４…吸着塔 ５…ミキサー、６…ドラム缶FIG. 1 is a conceptual diagram showing an apparatus configuration centering on a reaction vessel and a flow for explaining a method for treating radioactive carbon according to the present invention. DESCRIPTION OF SYMBOLS 1 ... Reaction container, 2 ... Condenser 3 ... Preheater, 4 ... Adsorption tower 5 ... Mixer, 6 ... Drum can
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 昭63−158497（ＪＰ，Ａ) 特開 昭61−104299（ＪＰ，Ａ) 特開 昭60−61698（ＪＰ，Ａ) ─────────────────────────────────────────────────── ─── Continuation of front page (56) Reference JP-A-63-158497 (JP, A) JP-A-61-104299 (JP, A) JP-A-60-61698 (JP, A)
Claims (4)
性廃棄物に対し、水性媒体中で、水溶性の低級アルコー
ルの共存と、触媒としての銅イオンおよび（または）鉄
イオンの存在の下に過酸化水素を作用させ、上記の放射
性炭素を含有する有機物および低級アルコールをともに
酸化分解することにより放射性炭素をCO2ガスとして分
離し、分離されたCO2ガスを水酸化バリウムと接触させ
炭酸バリウムとして固定することからなる放射性炭素の
処理方法。1. A radioactive waste containing radiocarbon in the form of an organic substance in the presence of a water-soluble lower alcohol in the presence of copper ion and / or iron ion as a catalyst in an aqueous medium. By reacting hydrogen peroxide to oxidize and decompose both the above-mentioned organic substance containing radiocarbon and lower alcohol, the radiocarbon is separated as CO 2 gas, and the separated CO 2 gas is contacted with barium hydroxide to form barium carbonate. A method of treating radiocarbon comprising fixing as.
廃棄物が、原子力発電所から発生する一次系廃樹脂また
は各種放射性廃液である請求項１の処理方法。2. The treatment method according to claim 1, wherein the radioactive waste containing radioactive carbon in the form of an organic substance is primary waste resin or various radioactive waste liquid generated from a nuclear power plant.
〜50mmol/lの存在下、pH:1〜５、温度:50〜100℃の条件
下に実施する請求項１の処理方法。3. Cu 2+ : 5 to 50 mmol / l and / or Fe 2+ : 5
The treatment method according to claim 1, which is carried out under the conditions of pH: 1 to 5 and temperature: 50 to 100 ° C. in the presence of ˜50 mmol / l.
後の液を、必要によりさらに濃縮して、セメント固化ま
たはアスファルト固化により処理する工程を付加した請
求項１の処理方法。4. The treatment method according to claim 1, further comprising a step of further concentrating the liquid after separating and removing radioactive carbon as CO 2 gas and treating by cement solidification or asphalt solidification.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1110883A JPH0752238B2 (en) | 1989-04-28 | 1989-04-28 | Radiocarbon treatment method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1110883A JPH0752238B2 (en) | 1989-04-28 | 1989-04-28 | Radiocarbon treatment method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02287299A JPH02287299A (en) | 1990-11-27 |
| JPH0752238B2 true JPH0752238B2 (en) | 1995-06-05 |
Family
ID=14547109
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1110883A Expired - Lifetime JPH0752238B2 (en) | 1989-04-28 | 1989-04-28 | Radiocarbon treatment method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0752238B2 (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2746207B1 (en) * | 1996-03-14 | 1998-05-29 | PROCESS AND PLANT FOR THE TREATMENT OF AN AQUEOUS EFFLUENT FROM DECONTAMINATION OR CHEMICAL CLEANING OF A NUCLEAR POWER PLANT | |
| JP4040854B2 (en) * | 2001-09-28 | 2008-01-30 | 株式会社神戸製鋼所 | Radioactive waste disposal container, disposal facility and disposal method |
| FR2874120B1 (en) | 2004-08-09 | 2006-11-24 | Cogema Logistics Sa | METHOD AND DEVICE FOR REMOVING FLAMMABLE GASES IN A CLOSED ENCLOSURE AND ENCLOSURE EQUIPPED WITH SUCH A DEVICE |
| CA3128848A1 (en) | 2020-08-25 | 2022-02-25 | Korea Atomic Energy Research Institute | A method of treating radioactive waste resin and an equipment therefor |
| KR102567969B1 (en) * | 2021-07-09 | 2023-08-17 | 한국원자력연구원 | Radioactive waste treatment system and method thereof |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6061698A (en) * | 1983-09-16 | 1985-04-09 | 株式会社東芝 | Method of solidifying and treating radioactive liquid organic waste |
| JPS61104299A (en) * | 1984-10-26 | 1986-05-22 | 日揮株式会社 | Method of disposing radioactive decontaminated waste liquor |
| JPS63158497A (en) * | 1986-08-20 | 1988-07-01 | 富士電機株式会社 | Decomposing processing method of radioactive ion exchange resin |
-
1989
- 1989-04-28 JP JP1110883A patent/JPH0752238B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH02287299A (en) | 1990-11-27 |
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