JPH0677068B2 - Treatment method of radioactive ion exchange resin - Google Patents
Treatment method of radioactive ion exchange resinInfo
- Publication number
- JPH0677068B2 JPH0677068B2 JP60095634A JP9563485A JPH0677068B2 JP H0677068 B2 JPH0677068 B2 JP H0677068B2 JP 60095634 A JP60095634 A JP 60095634A JP 9563485 A JP9563485 A JP 9563485A JP H0677068 B2 JPH0677068 B2 JP H0677068B2
- Authority
- JP
- Japan
- Prior art keywords
- acid
- radioactive
- resin
- exchange resin
- ion exchange
- 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 12
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 title claims description 11
- 239000003456 ion exchange resin Substances 0.000 title claims description 8
- 229920003303 ion-exchange polymer Polymers 0.000 title claims description 8
- 230000002285 radioactive effect Effects 0.000 title claims description 8
- 239000002253 acid Substances 0.000 claims description 30
- 238000009792 diffusion process Methods 0.000 claims description 21
- 239000011347 resin Substances 0.000 claims description 21
- 229920005989 resin Polymers 0.000 claims description 21
- 238000000502 dialysis Methods 0.000 claims description 16
- 239000007788 liquid Substances 0.000 claims description 15
- 239000000941 radioactive substance Substances 0.000 claims description 15
- 239000012528 membrane Substances 0.000 claims description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 239000007864 aqueous solution Substances 0.000 claims description 8
- 239000002699 waste material Substances 0.000 claims description 8
- 238000011084 recovery Methods 0.000 claims description 4
- 239000000243 solution Substances 0.000 claims description 4
- 238000010828 elution Methods 0.000 claims description 3
- 239000011260 aqueous acid Substances 0.000 claims 1
- 238000007711 solidification Methods 0.000 claims 1
- 230000008023 solidification Effects 0.000 claims 1
- 230000007935 neutral effect Effects 0.000 description 5
- 150000003839 salts Chemical class 0.000 description 5
- 239000012153 distilled water Substances 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 description 3
- 239000003729 cation exchange resin Substances 0.000 description 3
- KRKNYBCHXYNGOX-UHFFFAOYSA-N citric acid Chemical compound OC(=O)CC(O)(C(O)=O)CC(O)=O KRKNYBCHXYNGOX-UHFFFAOYSA-N 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 150000002500 ions Chemical class 0.000 description 3
- 230000008929 regeneration Effects 0.000 description 3
- 238000011069 regeneration method Methods 0.000 description 3
- 210000005241 right ventricle Anatomy 0.000 description 3
- 101100149536 Caenorhabditis elegans skn-1 gene Proteins 0.000 description 2
- VEXZGXHMUGYJMC-UHFFFAOYSA-N Hydrochloric acid Chemical compound Cl VEXZGXHMUGYJMC-UHFFFAOYSA-N 0.000 description 2
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 2
- 101100083855 Rattus norvegicus Pou2f3 gene Proteins 0.000 description 2
- QAOWNCQODCNURD-UHFFFAOYSA-N Sulfuric acid Chemical compound OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 description 2
- 150000007513 acids Chemical class 0.000 description 2
- 239000003957 anion exchange resin Substances 0.000 description 2
- 210000005240 left ventricle Anatomy 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 150000007524 organic acids Chemical class 0.000 description 2
- 229920000642 polymer Polymers 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- CHRJZRDFSQHIFI-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;styrene Chemical compound C=CC1=CC=CC=C1.C=CC1=CC=CC=C1C=C CHRJZRDFSQHIFI-UHFFFAOYSA-N 0.000 description 1
- FEWJPZIEWOKRBE-JCYAYHJZSA-N Dextrotartaric acid Chemical compound OC(=O)[C@H](O)[C@@H](O)C(O)=O FEWJPZIEWOKRBE-JCYAYHJZSA-N 0.000 description 1
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- FEWJPZIEWOKRBE-UHFFFAOYSA-N Tartaric acid Natural products [H+].[H+].[O-]C(=O)C(O)C(O)C([O-])=O FEWJPZIEWOKRBE-UHFFFAOYSA-N 0.000 description 1
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 1
- 230000000903 blocking effect Effects 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
- 239000004568 cement Substances 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- 150000007522 mineralic acids Chemical class 0.000 description 1
- LNOPIUAQISRISI-UHFFFAOYSA-N n'-hydroxy-2-propan-2-ylsulfonylethanimidamide Chemical compound CC(C)S(=O)(=O)CC(N)=NO LNOPIUAQISRISI-UHFFFAOYSA-N 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 235000005985 organic acids Nutrition 0.000 description 1
- 235000006408 oxalic acid Nutrition 0.000 description 1
- 239000012466 permeate Substances 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 125000001453 quaternary ammonium group Chemical group 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 125000000542 sulfonic acid group Chemical group 0.000 description 1
- 235000002906 tartaric acid Nutrition 0.000 description 1
- 239000011975 tartaric acid Substances 0.000 description 1
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Description
【発明の詳細な説明】 （産業上の利用分野） 本発明は、原子力施設における使用済み放射性イオン交
換樹脂の処理方法に関する。TECHNICAL FIELD The present invention relates to a method for treating a used radioactive ion exchange resin in a nuclear facility.
（従来の技術） 使用済みの放射性イオン交換樹脂（以下、簡単のため単
に“樹脂”と記す）の有力な処理方法として焼却する方
法があるが、樹脂の含有放射能のレベルが高い場合は、
次の欠点を生ずる。(Prior Art) There is a method of incinerating used radioactive ion exchange resin (hereinafter, simply referred to as "resin" for simplicity) as a powerful treatment method, but when the level of radioactivity contained in the resin is high,
It causes the following drawbacks.
焼却炉が高汚染され線量率が高くなるので、メンテ
ナンスが困難になる。Maintenance is difficult because the incinerator is highly polluted and the dose rate is high.
焼却排ガスに含まれる放射能量が増大するので、こ
れに対する対策が必要になる。Since the amount of radioactivity contained in the incineration exhaust gas increases, it is necessary to take measures against this.
焼却灰の放射性物質濃度が高くなり、その取扱いが
容易でない。The incineration ash has a high concentration of radioactive substances and is not easy to handle.
（発明が解決しようとする問題点） 本発明は、原子力施設にて発生する使用済の樹脂を、上
記欠点のない方法で焼却する技術を提案するものであ
る。(Problems to be Solved by the Invention) The present invention proposes a technique for incinerating a used resin generated in a nuclear facility by a method that does not have the above-mentioned drawbacks.
（問題点を解決するための手段） 本発明は、放射性イオン交換樹脂の処理方法において、
酸水溶液にて放射性物質を溶離した前記樹脂を焼却炉に
て焼却し、該放射性物質を溶存する酸水溶液は拡散透析
膜で処理し、該処理により分離された酸水溶液は放射性
イオン交換樹脂からの放射性物質の溶離に再使用し、放
射性物質含有廃液は蒸発濃濃縮して蒸発水は拡散透析装
置に送り酸回収用水として使用し、濃縮液は固化処理す
ることを特徴とする放射性イオン交換樹脂の処理方法に
関する。(Means for Solving Problems) The present invention provides a method for treating a radioactive ion exchange resin,
The resin in which the radioactive substance is eluted with the acid aqueous solution is incinerated in an incinerator, the acid aqueous solution in which the radioactive substance is dissolved is treated with a diffusion dialysis membrane, and the acid aqueous solution separated by the treatment is extracted from the radioactive ion exchange resin. It is reused for elution of radioactive substances, the waste liquid containing radioactive substances is concentrated by evaporation, the evaporated water is sent to a diffusion dialysis device and used as acid recovery water, and the concentrated liquid is solidified. Regarding processing method.
本発明においては、次の点に特徴がある。The present invention is characterized by the following points.
樹脂が保有している放射性物質（例えば、Cs−137,
Sr−90,Co−60等）を酸の水溶液で処理し、溶離させる
（すなわち、樹脂の保有放射能を低減させる）。Radioactive substances held by the resin (for example, Cs-137,
Sr-90, Co-60, etc.) is treated with an aqueous solution of acid and eluted (ie, the radioactivity retained by the resin is reduced).
放射能の減少した樹脂は焼却炉で焼却する。 The resin with reduced radioactivity is incinerated in an incinerator.
放射性物質を溶解した酸又は中性塩水溶液は拡散透
析膜により、酸又は中性塩を回収し、この酸又は中性塩
を樹脂処理用の酸又は中性塩として再使用する。The acid or neutral salt aqueous solution in which the radioactive substance is dissolved is recovered by a diffusion dialysis membrane, and this acid or neutral salt is reused as the acid or neutral salt for resin treatment.
拡散透析膜で酸又は中性塩の大部分を除去された廃
液は、溶質分が大幅に減少しているので、必要に応じ、
蒸発装置で濃縮し、減容後、固化する。The waste solution from which most of the acid or neutral salt has been removed by the diffusion dialysis membrane has a significantly reduced solute content.
Concentrate with an evaporator, reduce the volume, and then solidify.
蒸発装置で得られた蒸留水は拡散透析膜への給水と
して利用することができる。The distilled water obtained by the evaporator can be used as water supply to the diffusion dialysis membrane.
すなわち、本発明は、（ｉ）樹脂の酸又は中性塩による
再生技術、（ii）樹脂の焼却技術、（iii）拡散透析膜
による酸回収技術、（iv）廃液蒸発装置（濃縮技術）を
効果的に組み合せたものである。That is, the present invention provides (i) regeneration technology of acid or neutral salt of resin, (ii) incineration technology of resin, (iii) acid recovery technology by diffusion dialysis membrane, and (iv) waste liquid evaporator (concentration technology). It is an effective combination.
第１図は本発明方法の一実施態様例を示すフローシート
である。FIG. 1 is a flow sheet showing an embodiment of the method of the present invention.
第１図において、処理すべき樹脂〔例えば、スチレン−
ジビニルベンゼン系高分子体に第４級アンモニウム基を
付加したもの（アニオン交換樹脂）や、この高分子体に
スルフオン酸基を付加したもの（カチオン交換樹脂）
で、具体的には、三菱化成（株）製商品名ダイヤイオン
SAN−１（アニオン交換樹脂）、SKN−１（カチオン交換
樹脂）、SKN−３（カチオン交換樹脂にリチウムを吸着
させたもの）、SMN−１（SKN−１とSAN−１の混合）、S
MN−３（SKN−３とSAN−１の混合）などの使用済みのも
のがある〕は樹脂充填塔１に入れられている。樹脂充填
塔１には、酸水溶液の入口ライン７、出口ライン２、及
び樹脂排出ライン13が接続している。In FIG. 1, the resin to be treated [eg styrene-
Divinylbenzene polymer with quaternary ammonium group added (anion exchange resin), or polymer with sulfonic acid group added (cation exchange resin)
Specifically, the product name Diaion manufactured by Mitsubishi Kasei Co., Ltd.
SAN-1 (anion exchange resin), SKN-1 (cation exchange resin), SKN-3 (cation exchange resin with lithium adsorbed), SMN-1 (mixture of SKN-1 and SAN-1), S
MN-3 (there is a mixture of SKN-3 and SAN-1) etc.] is put in the resin packed tower 1. The resin packed tower 1 is connected with an acid aqueous solution inlet line 7, an outlet line 2 and a resin discharge line 13.
本発明に使用できる酸としては、硫酸、硝酸、塩酸、リ
ン酸、ホウ酸等の無機酸、クエン酸、シユウ酸、スルフ
アミン酸、酒石酸等の有機酸が適している。有機酸は、
腐食性が弱く、イオン封鎖力をもつため、本発明におい
て好ましく使用できる。これらの酸の濃度は、余り低い
と酸と吸着イオン間の選択係数により再生（すなわちイ
オンの追出し）ができず、余り高くてもそれ程効果は向
上せず経済的でないので、５〜15wt％、好ましくは５〜
10wt％、酸総量は樹脂１当り３〜10当量（これは多い
ほど再生効率が高い）とすることが望ましい。Suitable acids usable in the present invention are inorganic acids such as sulfuric acid, nitric acid, hydrochloric acid, phosphoric acid and boric acid, and organic acids such as citric acid, oxalic acid, sulfamic acid and tartaric acid. The organic acid is
Since it is weakly corrosive and has an ion blocking power, it can be preferably used in the present invention. If the concentration of these acids is too low, regeneration (that is, ion ejection) cannot be performed due to the selectivity coefficient between the acid and the adsorbed ions, and even if the concentration is too high, the effect is not so improved and it is not economical, so 5-15 wt%, Preferably 5
It is desirable that the amount of the acid is 10 wt% and the total amount of the acid is 3 to 10 equivalents per resin (the higher the amount, the higher the regeneration efficiency).
これら酸水溶をライン７→塔１→ライン２と通液するこ
とにより、樹脂が保有していた放射性物質（例えば、Cs
−137,Sr−90,Co−90等）は、この液中に溶離する。By passing these acid water solutions through line 7 → tower 1 → line 2, the radioactive substances (eg Cs
(-137, Sr-90, Co-90, etc.) elutes in this liquid.
塔１において放射性物質を保有した液は、ライン２によ
り拡散透析装置３の左室に供給される。該拡散透析装置
３は、その拡大図である第２図に示すように、真中を拡
散透析膜（図中、点線で示す）で区切られており、左室
と右室に分かれている。左室には、樹脂処理液の供給ラ
イン２とそれを処理した後の拡散透析廃液ライン４が接
続している。また右室には、蒸留水の供給ライン６と酸
回収ライン７が接続している。ここで左室の流れ方向
と、右室の流れ方向が逆向き（カウンターフロー）であ
ることに留意する必要がある。拡散透析は半透膜を物質
が拡散により移動する際、拡散速度の大小の差を利用し
て物質の分離・回収を行なうのに用いられる。ここで
は、左室を流れる液から酸が透析膜を透過して右室へ移
行する。この際、放射性物質（Cs−137,Sr−90,Co−60
等）は半透膜内における拡散速度が小さいので、ほとん
ど右室へ移行しない。これにより酸と放射性物質の分離
が行なわれる。左右の液の流れ方向を逆にするのは拡散
透析を効果的に行なうために膜の左右に濃度差をつける
ためである。拡散透析の詳しい様子を第２図に示す。The liquid containing the radioactive substance in the tower 1 is supplied to the left chamber of the diffusion dialyzer 3 through the line 2. As shown in FIG. 2 which is an enlarged view of the diffusion dialysis device 3, the center is divided by a diffusion dialysis membrane (indicated by a dotted line in the figure), and is divided into a left chamber and a right chamber. To the left chamber, a resin treatment liquid supply line 2 and a diffusion dialysis waste liquid line 4 after treating the same are connected. A distilled water supply line 6 and an acid recovery line 7 are connected to the right chamber. Here, it should be noted that the flow direction of the left ventricle and the flow direction of the right ventricle are opposite (counterflow). Diffusion dialysis is used to separate and collect substances by utilizing the difference in diffusion rate when the substances move through the semipermeable membrane by diffusion. Here, acid permeates the dialysis membrane from the liquid flowing in the left ventricle and moves to the right ventricle. At this time, radioactive materials (Cs-137, Sr-90, Co-60
Etc., the diffusion rate in the semipermeable membrane is small, so that it hardly migrates to the right ventricle. Thereby, the acid and the radioactive substance are separated. The reason why the flow directions of the liquids on the left and right sides are reversed is to make a difference in concentration on the left and right sides of the membrane for effective diffusion dialysis. The detailed state of diffusion dialysis is shown in FIG.
さて、拡散透析装置３内で酸濃度が低下した液は、ライ
ン４から廃液蒸発装置５に送られ、そこで濃縮液と蒸留
水に分離される。濃縮液は、ライン10により固化装置11
に送られ、そこで固化される。蒸留水は、ライン６によ
り拡散透析装置３へ送られ、そこで酸を回収し、ライン
７を経由して樹脂充填塔１へ処理液として供給される。Now, the liquid whose acid concentration has decreased in the diffusion dialyzer 3 is sent from the line 4 to the waste liquid evaporator 5, where it is separated into a concentrated liquid and distilled water. Concentrated liquid is solidified by line 11
Sent to and solidified there. Distilled water is sent to the diffusion dialysis device 3 through the line 6, where the acid is recovered and supplied as a treatment liquid to the resin packed tower 1 through the line 7.
なお、酸の回収は100％行なわれる訳ではないので、ロ
ス分は酸補給ライン８から供給される。Since the acid is not recovered 100%, the loss is supplied from the acid supply line 8.
以上のようにして、保有していた放射能の大部分を除去
された樹脂は、樹脂排出ライン13を経由して、焼却炉14
へ送られ、そこで焼却される。As described above, the resin from which most of the stored radioactivity has been removed passes through the resin discharge line 13 and the incinerator 14
Sent to and incinerated there.
なお、上記の固化装置11としては種々のものが考えられ
るが（セメント固化、プラスチツク固化等）、ここで
は、その方式は限定しない。Various types of solidifying devices 11 are conceivable (cement solidifying, plastic solidifying, etc.), but the method is not limited here.
（発明の効果） 焼却炉では、大部分の放射能を除去した樹脂を焼却
するのであるから、次の効果を得ることができる。(Effects of the Invention) In an incinerator, most of the radioactivity-removed resin is incinerated, so the following effects can be obtained.
（ｉ） 焼却炉のメンテナンスが容易である。(I) Maintenance of the incinerator is easy.
（ii） 排ガス中の低射能が少ないので処理が容易であ
る。(Ii) Treatment is easy because there is little low radioactivity in the exhaust gas.
（iii） 焼却灰中の放射能濃度は低いので取扱いが容
易である。(Iii) It is easy to handle because the radioactivity concentration in the incineration ash is low.
放射性物質の溶離に用いた酸は、大部分が回収され
再使用されるので、酸の消費量が少ない。このことは換
言すれば、二次廃棄物の発生が少ないと言える。Most of the acid used for elution of the radioactive substance is recovered and reused, so that the acid consumption is small. In other words, it can be said that the generation of secondary waste is small.
拡散透析膜より出る廃液は溶質分が少ないので、充
分な減容が可能である。Since the waste solution discharged from the diffusion dialysis membrane has a small solute content, it is possible to sufficiently reduce the volume.
【図面の簡単な説明】 第１図は本発明方法の一実施態様例を示すフローシー
ト、第２図は第１図の一部拡大図である。BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a flow sheet showing an embodiment of the method of the present invention, and FIG. 2 is a partially enlarged view of FIG.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 稲垣 雄三 兵庫県神戸市兵庫区小松通５丁目１番16号 菱重環境流通エンジニアリング株式会社 内 (56)参考文献 特開 昭52−102884（ＪＰ，Ａ) 特開 昭59−116595（ＪＰ，Ａ) 特開 昭59−51399（ＪＰ，Ａ) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Yuzo Inagaki 5-1-16 Komatsudori, Hyogo-ku, Kobe-shi, Hyogo Ryoju Environmental Engineering Co., Ltd. (56) Reference JP-A-52-102884 (JP, A) JP-A-59-116595 (JP, A) JP-A-59-51399 (JP, A)
Claims (1)
て、酸水溶液にて放射性物質を溶離した前記樹脂を焼却
炉にて焼却し、該放射性物質を溶存する酸水溶液は拡散
透析膜で処理し、該処理により分離された酸水溶液は放
射性イオン交換樹脂からの放射性物質の溶離に再使用
し、放射性物質含有廃液は蒸発濃縮して蒸発水は拡散透
析装置に送り酸回収用水として使用し、濃縮液は固化処
理することを特徴とする放射性イオン交換樹脂の処理方
法。1. A method for treating a radioactive ion exchange resin, wherein the resin in which a radioactive substance is eluted with an acid aqueous solution is incinerated in an incinerator, and the acid aqueous solution in which the radioactive substance is dissolved is treated with a diffusion dialysis membrane, The aqueous acid solution separated by the treatment is reused for the elution of radioactive substances from the radioactive ion exchange resin, the radioactive substance-containing waste liquid is evaporated and concentrated, and the evaporated water is sent to the diffusion dialyzer for use as acid recovery water. A method for treating a radioactive ion exchange resin, which comprises performing a solidification treatment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60095634A JPH0677068B2 (en) | 1985-05-07 | 1985-05-07 | Treatment method of radioactive ion exchange resin |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60095634A JPH0677068B2 (en) | 1985-05-07 | 1985-05-07 | Treatment method of radioactive ion exchange resin |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61254899A JPS61254899A (en) | 1986-11-12 |
| JPH0677068B2 true JPH0677068B2 (en) | 1994-09-28 |
Family
ID=14142946
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60095634A Expired - Lifetime JPH0677068B2 (en) | 1985-05-07 | 1985-05-07 | Treatment method of radioactive ion exchange resin |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0677068B2 (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5489124B2 (en) * | 2011-08-23 | 2014-05-14 | 日立Ｇｅニュークリア・エナジー株式会社 | Waste resin treatment method and treatment system for nuclear power plant |
| JP2013217801A (en) * | 2012-04-10 | 2013-10-24 | Kurita Engineering Co Ltd | Decontamination method for radioactive waste resin |
| JP6221847B2 (en) * | 2013-10-24 | 2017-11-01 | 栗田工業株式会社 | Co and Fe electrodeposition method and apparatus |
| JP6439242B2 (en) * | 2013-10-24 | 2018-12-19 | 栗田工業株式会社 | Decontamination method and decontamination apparatus for radioactive waste ion exchange resin |
| WO2015060250A1 (en) * | 2013-10-24 | 2015-04-30 | 栗田工業株式会社 | Method and apparatus for treating liquid containing iron-group metal ions, method and apparatus for electrodeposition of co and fe, and method and apparatus for decontamination of radioactive waste ion exchange resin |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2607292C2 (en) * | 1976-02-23 | 1985-08-29 | Kraftwerk Union AG, 4330 Mülheim | Process for the removal of radioactive corrosion products from ion exchange resins used in nuclear reactor operation |
| JPS5951399A (en) * | 1982-09-17 | 1984-03-24 | 株式会社荏原製作所 | Method of heating and volume-decreasing ion exchanging resinhaving radioactivity material |
| JPS59116595A (en) * | 1982-12-24 | 1984-07-05 | 神鋼パンテック株式会社 | Method of removing radioactive material in electrolyte in electrolytic decontamination |
-
1985
- 1985-05-07 JP JP60095634A patent/JPH0677068B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61254899A (en) | 1986-11-12 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |