JPS62180299A - Method of processing waste solvent - Google Patents
Method of processing waste solventInfo
- Publication number
- JPS62180299A JPS62180299A JP2199886A JP2199886A JPS62180299A JP S62180299 A JPS62180299 A JP S62180299A JP 2199886 A JP2199886 A JP 2199886A JP 2199886 A JP2199886 A JP 2199886A JP S62180299 A JPS62180299 A JP S62180299A
- Authority
- JP
- Japan
- Prior art keywords
- diluent
- tributyl phosphate
- waste solvent
- distillation
- rectification column
- 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.)
- Granted
Links
- 239000010887 waste solvent Substances 0.000 title claims description 17
- 238000000034 method Methods 0.000 title claims description 10
- 238000012545 processing Methods 0.000 title description 2
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims description 34
- 238000004821 distillation Methods 0.000 claims description 28
- 239000003085 diluting agent Substances 0.000 claims description 26
- 239000010409 thin film Substances 0.000 claims description 12
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 10
- 229910017604 nitric acid Inorganic materials 0.000 claims description 10
- 239000000243 solution Substances 0.000 claims description 10
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 7
- 239000007864 aqueous solution Substances 0.000 claims description 6
- 238000012958 reprocessing Methods 0.000 claims description 6
- 239000012857 radioactive material Substances 0.000 claims 1
- 239000000047 product Substances 0.000 description 14
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 description 12
- 230000006866 deterioration Effects 0.000 description 10
- 238000009835 boiling Methods 0.000 description 7
- 238000001704 evaporation Methods 0.000 description 7
- 229910052770 Uranium Inorganic materials 0.000 description 6
- 238000000354 decomposition reaction Methods 0.000 description 6
- 230000008020 evaporation Effects 0.000 description 6
- 239000000203 mixture Substances 0.000 description 5
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 239000000941 radioactive substance Substances 0.000 description 4
- 238000005979 thermal decomposition reaction Methods 0.000 description 4
- -1 CI4 hydrocarbons Chemical class 0.000 description 3
- JYFHYPJRHGVZDY-UHFFFAOYSA-N Dibutyl phosphate Chemical compound CCCCOP(O)(=O)OCCCC JYFHYPJRHGVZDY-UHFFFAOYSA-N 0.000 description 3
- 239000002904 solvent Substances 0.000 description 3
- 229910019142 PO4 Inorganic materials 0.000 description 2
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 2
- 239000007857 degradation product Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 229930195733 hydrocarbon Natural products 0.000 description 2
- 238000012856 packing Methods 0.000 description 2
- 239000010452 phosphate Substances 0.000 description 2
- 238000003672 processing method Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- MQEMKUTWMALMCC-UHFFFAOYSA-N 1-nitrododecane Chemical compound CCCCCCCCCCCC[N+]([O-])=O MQEMKUTWMALMCC-UHFFFAOYSA-N 0.000 description 1
- LSKONYYRONEBKA-UHFFFAOYSA-N 2-Dodecanone Natural products CCCCCCCCCCC(C)=O LSKONYYRONEBKA-UHFFFAOYSA-N 0.000 description 1
- 239000004215 Carbon black (E152) Substances 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- BNMJSBUIDQYHIN-UHFFFAOYSA-N butyl dihydrogen phosphate Chemical compound CCCCOP(O)(O)=O BNMJSBUIDQYHIN-UHFFFAOYSA-N 0.000 description 1
- 238000003889 chemical engineering Methods 0.000 description 1
- 230000000052 comparative effect Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 239000003350 kerosene Substances 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 150000003014 phosphoric acid esters Chemical class 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000010992 reflux Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
Landscapes
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (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】
〔産業上の利用分野〕
本発明は、原子力発電所等で発生する使用済み核燃料を
再処理工程において硝酸水溶液に溶解させ、その後燐酸
トリブチルと希釈剤からなる溶液によってＵ、 Ｐｕ等
の放射性物質を抽出した燐酸トリブチル、希釈剤を含む
廃溶媒から燐酸トリブチル及び希釈剤を回収するための
廃溶媒の処理方法に関するものである。Detailed Description of the Invention [Field of Industrial Application] The present invention involves dissolving spent nuclear fuel generated at nuclear power plants, etc. in a nitric acid aqueous solution in a reprocessing process, and then treating the spent nuclear fuel with a solution of tributyl phosphate and a diluent. This invention relates to a waste solvent processing method for recovering tributyl phosphate and a diluent from a waste solvent containing tributyl phosphate and a diluent from which radioactive substances such as Pu have been extracted.
更に詳しくは、原子力発電所等で発生する使用済み核燃
料を再処理工程において硝酸水溶液に溶解させ、その後
、燐酸トリブチルと希釈剤からなる溶液によってＵ、
Ｐｕ等の放射性物質を抽出した燐酸トリブチル、希釈剤
を含む廃溶媒から燐酸トリブチル及び希釈剤を回収する
に際し、先ず廃溶媒に含まれている高沸点の劣化生成物
を薄膜蒸発式蒸留装置により除去し、次いで精留塔によ
り燐酸トリブチルと希釈剤を分離、回収することにより
、留出率を低下することなく高い純度の燐酸トリブチル
及び希釈剤が回収でき、しかも蒸留操作が円滑に行える
ようにする廃溶媒の処理方法を提供するものである。More specifically, spent nuclear fuel generated at nuclear power plants, etc. is dissolved in an aqueous nitric acid solution in the reprocessing process, and then U, U,
When recovering tributyl phosphate and the diluent from the waste solvent containing the tributyl phosphate and diluent from which radioactive substances such as Pu have been extracted, first the high boiling point deterioration products contained in the waste solvent are removed using a thin film evaporation distillation device. Then, by separating and recovering tributyl phosphate and diluent using a rectification column, high purity tributyl phosphate and diluent can be recovered without reducing the distillation rate, and the distillation operation can be performed smoothly. A method for treating waste solvent is provided.
一般に原子力発電所等で発生する使用済み核燃料は、再
処理工程において硝酸水溶液に溶解させ、その後、燐酸
トリブチル（以下ｒＴＢＰＪと略記する）と希釈剤（ド
デカン、ケロセン、ＣＩＯ”ＣＩ４の炭化水素等）から
なる溶媒によってＵ 、 Ｐ ｕ １４が抽出されてい
る。上述の操作によりＴＢＰと希釈剤の溶媒は硝酸、放
射線及び熱等によるＴＢＰあるいは希釈剤の分解生成物
（燐酸ジブチル、燐酸モノブチル、燐酸、ニトロドデカ
ン、ドデカノン、Ｆデカノール、リン酸エステル、炭化
水素）、及び燐酸ジブチル（以下ｒＤＢＰＪと略記する
）あるいは燐酸エステル等との錯体が含有されると共に
、硝酸水溶液中の無機物（Ｚｒ、 Ｒｈ、 Ｎｂ、 Ｒ
ｕ、 Ｕ、Ｐｕ等）、水及び硝酸等（以下「劣化生成物
」という）を微量含有することになる。Generally, spent nuclear fuel generated at nuclear power plants, etc. is dissolved in a nitric acid aqueous solution in the reprocessing process, and then mixed with tributyl phosphate (rTBPJ) and diluents (dodecane, kerosene, CIO" CI4 hydrocarbons, etc.) U and P u 14 are extracted with a solvent consisting of nitric acid, radiation, heat, etc. (dibutyl phosphate, monobutyl phosphate, phosphoric acid, nitrododecane, dodecanone, F-decanol, phosphate ester, hydrocarbon), and complexes with dibutyl phosphate (hereinafter abbreviated as rDBPJ) or phosphate ester, etc., and inorganic substances (Zr, Rh, Nb) in the nitric acid aqueous solution. , R
(U, Pu, etc.), water, nitric acid, etc. (hereinafter referred to as "deterioration products").
上述のような熱分解を起こし易いＴＢＰ及び劣化生成物
を含む廃溶媒からＴＢＰ及び希釈剤を回収するには、４
〜５段の分離段数を有するｔｉ留塔が使用されている。To recover TBP and diluent from waste solvents containing TBP and degradation products that are prone to thermal decomposition as described above, 4.
A Ti distillation column with a number of separation stages of ˜5 is used.
しかし、精留操作において精留塔の缶残側は殆どＴＢＰ
になり、かつ塔圧損により塔内の圧力が高くなって、蒸
留温度が設定温度より高くなる。However, in the rectification operation, the bottom side of the rectification column is mostly TBP.
, and the pressure inside the column increases due to column pressure loss, making the distillation temperature higher than the set temperature.
また、ＤＢＰ等のＴＢＰを分解劣化させる劣化生成物は
殆ど高沸点であるため、缶残側に蓄積されることになる
。Moreover, since most of the decomposition products such as DBP that cause decomposition and deterioration of TBP have high boiling points, they will be accumulated on the left side of the can.
これらの結果、精留塔の缶残側においては４１時間、高
温度で加熱されることになり、ＴＢＰが熱分解されると
いう問題があった。As a result, the bottom side of the rectification column was heated at a high temperature for 41 hours, causing the problem that TBP was thermally decomposed.
本発明の目的は、上述のような問題点を解決し、留出率
を低下することなく高い純度の燐酸トリブチル及び希釈
剤が回収でき、しかも蒸留操作を円滑に行なうことがで
きる廃溶媒（燐酸トリブチルと希釈剤を含む）の処理方
法を提供するにある。The purpose of the present invention is to solve the above-mentioned problems, to recover high-purity tributyl phosphate and diluent without reducing the distillation rate, and to provide a waste solvent (phosphoric acid) that allows smooth distillation operations. tributyl and a diluent).
すなわち、本発明は、原子力発電所等で発生する使用済
み核燃料を再処理工程において硝酸水溶液に熔解させ、
その後、燐酸トリブチルと希釈剤からなる溶液によって
ＩＩ、Ｐｕ等の放射性物質を抽出した燐酸トリブチル、
希釈剤を含む廃溶媒から燐酸トリブチル及び希釈剤を回
収するに際し、先ず廃溶媒に含まれている高沸点の劣化
生成物を薄膜蒸発式蒸留装置により除去し、次いで精留
塔により燐酸トリブチルと希釈剤を分離し回収する廃溶
媒の処理方法を提供するものである。That is, the present invention melts spent nuclear fuel generated at nuclear power plants etc. into a nitric acid aqueous solution in a reprocessing process,
After that, radioactive substances such as II and Pu were extracted with a solution consisting of tributyl phosphate and a diluent.
When recovering tributyl phosphate and the diluent from the waste solvent containing the diluent, first the high boiling point deterioration products contained in the waste solvent are removed using a thin film evaporative distillation device, and then diluted with tributyl phosphate using a rectification column. The present invention provides a method for treating waste solvents that separates and recovers solvents.
ここで、燐酸トリブチルと希釈剤に含まれる被抽出材は
、ＴＢＰ、希釈剤の分解生成物、無機物、及び燐酸ジブ
チル、リン酸エステル等との錯体、並びに水、硝酸等の
劣化生成物を微量含有するものである。Here, the extractable materials contained in tributyl phosphate and the diluent include TBP, decomposition products of the diluent, inorganic substances, complexes with dibutyl phosphate, phosphate esters, etc., and trace amounts of deterioration products such as water and nitric acid. It contains.
薄膜蒸発式蒸留装置は、装置内での溶媒の滞留時間が短
く、しかも局部的な異常滞留が生じず、蒸発効率の高い
ものを使用する必要がある。この装置としては、生産装
置として実用化されている点及び使用実績からして化学
工学便覧（昭和５５年１２月２５日、丸善株式会社発行
）第４０６頁０図４・１１（Ｊ）に記載されているよう
な攪拌薄膜蒸発式蒸留装置を使用するのが好ましい。The thin-film evaporative distillation apparatus must have a short residence time of the solvent within the apparatus, prevent abnormal local retention, and have high evaporation efficiency. This device is listed in the Chemical Engineering Handbook (December 25, 1980, published by Maruzen Co., Ltd.), page 406, Figure 4, 11 (J), as it has been put into practical use as a production device and has been used. Preferably, a stirred thin film evaporative distillation apparatus, such as that described in US Pat.
精留塔は、薄膜蒸発式リボイラーを装着した構成のもの
を使用するのが好ましい。It is preferable to use a rectification column equipped with a thin film evaporation reboiler.
廃溶媒の処理に際しては、第１図に示すような回転ロー
タ１ａを内装したＦ＃膜蒸発式蒸留装置１に精留塔２を
連結すると共に、精留塔２の底部に回転ロータ３ａを、
頂部にコンデンサー４をそれぞれ連結し、蒸留装置１の
留出液を直接精留塔２に供給するように構成するのが好
ましい。しがし、薄膜蒸発式蒸留装置と精留塔を単独に
設置し、蒸〔実施例〕
蒸留、精留操作条件
蒸留装置の蒸発面寸法： ８０ｘ３００ ｍｍ楕留
塔の寸法： ２５Ｘ２００ ＋ｎ Ｘ ２段リボ
イラーの蒸発面寸法： ８０Ｘ３００ ＋ｎ精留塔の
圧力（塔頂） ： １ ｔｏｒｒ蒸留装置の加
熱温度：１５５℃
リボイラーの加熱温度＝１６０°Ｃ
ロータの回転数： ２８ＯＲ，Ｐ、Ｍ精留塔の還流
比＝０．３
供給液量： ０．２ ｋｒｒ／ｈｒ
上述のような条件で、第１図に示すような装置を使用し
、ドデカン７０．３容量％、Ｔ １３ Ｐ ２９．７容
量％、分解生成物及びＤＢＰ等０．１容量％以下（ドデ
カン６４．５重量％、ＴＢＰ３５．５重量％、分解生成
物及びＤＢＰ等０．１容量％以下）からなる溶液を蒸留
、精留処理を行なったところ、次のような結果を得るご
とができた。When processing waste solvent, a rectification column 2 is connected to an F# membrane evaporative distillation apparatus 1 equipped with a rotating rotor 1a as shown in FIG.
It is preferable that a condenser 4 is connected to the top of each of the distillation apparatuses, so that the distillate of the distillation apparatus 1 is directly supplied to the rectification column 2. However, a thin-film evaporative distillation device and a rectification column were installed independently, and the distillation was carried out.[Example] Distillation and rectification operation conditions Dimensions of the evaporation surface of the distillation device: 80 x 300 mm Dimensions of the elliptical distillation column: 25 x 200 +n x 2 stages Dimensions of evaporation surface of reboiler: 80X300 +N Pressure of rectification column (tower top): 1 torr Heating temperature of distillation equipment: 155℃ Reboiler heating temperature = 160℃ Rotor rotation speed: 28OR, P, M of rectification column Reflux ratio = 0.3 Supply liquid amount: 0.2 krr/hr Under the conditions described above, using the apparatus shown in Figure 1, dodecane was 70.3% by volume, T 13 P was 29.7% by volume. , a solution consisting of 0.1% by volume or less of decomposition products, DBP, etc. (64.5% by weight of dodecane, 35.5% by weight of TBP, 0.1% by volume or less of decomposition products, DBP, etc.) is subjected to distillation and rectification treatment. When I did this, I got the following results:
（１）蒸留、精留操作による溶液中の組成変化留出液の
組成は、ドデカンが９９．９重量％以上、ＴＢＰが２０
ＰＰＭ以下であり、また、精留塔缶残液の組成は、ドデ
カンが０．６重量％、ＴＢＰが９９．４重量％である。(1) Composition change in solution due to distillation and rectification The composition of the distillate is 99.9% by weight or more of dodecane and 20% of TBP.
PPM or less, and the composition of the rectification column bottom liquid is 0.6% by weight of dodecane and 99.4% by weight of TBP.
（２）溶液中に含まれていたＤ Ｂ Ｐ （５３ＰＰＭ
）は、蒸留、精留操作を行なったところ、薄膜蒸発式蒸
留装置の残液中にＤＢＰが１０２ ＰＰＭ含有されてい
たが、精留塔の留出液及び精留塔缶残液からはＤＢＰを
検出することができなかった。(2) D B P (53 PPM) contained in the solution
) was subjected to distillation and rectification operations, and found that the residual liquid from the thin-film evaporative distillation apparatus contained 102 PPM of DBP. could not be detected.
このことからも、分解生成物及びＤＢＰ等の高沸点劣化
生成物は、薄膜蒸発式蒸留装置により完全に除去される
と共に、精留塔内においてＴＢＰの熱分解によるＤＢＰ
の発生がなかったことがわかる。From this, decomposition products and high boiling point deterioration products such as DBP are completely removed by the thin film evaporative distillation apparatus, and DBP is produced by thermal decomposition of TBP in the rectification column.
It can be seen that there was no occurrence of
操作終了後に精留塔の充填物を点検したが着色した劣化
生成物の付着は見られなかった。After the operation was completed, the packing of the rectification column was inspected, but no colored deterioration products were observed.
上述の実施例と同一の組成の溶液を、第２図に示すよう
な予熱器１０を精留塔１１に連結すると共に、精留塔１
１の底部にリボイラー１２を、頂部にコンデンサー１３
をそれぞれ連結した構成の装置を使用した他は実施例と
同一条件で精留操作を行なったところ、精留操作による
溶液中の組成は上述の実施例と略同−であった。しかし
、溶液中に含まれていたＤ Ｂ Ｐ （５３ＰＰＭ）は
、精留操作を行なった結果、留出液からはＤＢＰを検出
することはできなかったが、缶残液ではＤＢＰが２０３
ＰＰＭに増加していた。A solution having the same composition as in the above-mentioned example was prepared by connecting a preheater 10 as shown in FIG.
Reboiler 12 at the bottom of 1, condenser 13 at the top
When the rectification operation was carried out under the same conditions as in the example except that an apparatus having a structure in which the two were connected together was used, the composition of the solution obtained by the rectification operation was approximately the same as in the above-mentioned example. However, as a result of rectification, DBP (53 PPM) contained in the solution could not be detected in the distillate, but DBP was 203 PPM in the bottom liquid.
It was increasing to PPM.
なお、操作終了後に精留塔の充填物を点検したところ、
褐色で粘着性のある劣化生成物が付着していた。In addition, when the packing of the rectification column was inspected after the operation was completed, it was found that
A brown and sticky deterioration product was attached.
上述のようにうに原子力発電所等で発生する使用済み核
燃料を再処理工程において硝酸水溶液に溶解させ、その
後、燐酸トリブチルと希釈剤からなる溶液によってＵ、
Ｐｕ等の放射性物質を抽出した燐酸トリブチルおよび
希釈剤を含む廃溶媒から、燐酸トリブチル及び希釈剤を
回収するに際し、先ず廃溶媒に含まれている高沸点の劣
化生成物を薄膜蒸発式蒸留装置により除去し、次いで精
留塔により燐酸トリブチルと希釈剤を分離し回収せしめ
ることにより次のような効果を奏する。As mentioned above, spent nuclear fuel generated at nuclear power plants, etc. is dissolved in a nitric acid aqueous solution in the reprocessing process, and then U, U,
When recovering tributyl phosphate and the diluent from the waste solvent containing the tributyl phosphate and diluent from which radioactive substances such as Pu have been extracted, first the high boiling point deterioration products contained in the waste solvent are removed using a thin film evaporation distillation device. The following effects can be achieved by removing the diluent and then separating and recovering the tributyl phosphate and the diluent using a rectification column.
（１） 燐酸トリブチルの熱分解を促進する高沸点の
劣化生成物を除去した後に、燐酸トリブチルと希釈剤を
分離するため、留出率を低下することなく、高い純度の
燐酸トリブチル及びドデカン等の希釈剤を安定して回収
することができる。(1) After removing high boiling point degradation products that promote the thermal decomposition of tributyl phosphate, the tributyl phosphate and diluent are separated, so high purity tributyl phosphate, dodecane, etc. Diluent can be recovered stably.
（２）高沸点の劣化生成物が除去された状態で籾留深作
するため、塔内圧力および温度を低く設定でき燐酸トリ
ブチルの熱分解を防止することができる。(2) Since the paddy distillation is carried out in a deep state in which deterioration products with high boiling points are removed, the pressure and temperature inside the column can be set low, and thermal decomposition of tributyl phosphate can be prevented.
第１図は本発明の処理方法を実施するための装置の概略
を示す系統図である。
第２図は従来の精留塔の１実施例を示す概略図である。
１：薄膜蒸発式蒸留装置、 ２：精留塔、３：薄膜蒸発
式リボイラー、
４：コンデンサー、 １０：予熱器、１１：精留塔
、 １２：リボイラー、１３：コンデンサ
ー。FIG. 1 is a system diagram schematically showing an apparatus for carrying out the processing method of the present invention. FIG. 2 is a schematic diagram showing one embodiment of a conventional rectification column. 1: thin film evaporative distillation apparatus, 2: rectifying column, 3: thin film evaporating reboiler, 4: condenser, 10: preheater, 11: rectifying column, 12: reboiler, 13: condenser.
Claims (1)
させ、その後、燐酸トリブチルと希釈剤からなる溶液に
よって放射性物質を抽出した燐酸トリブチル及び希釈剤
を含む廃溶媒から燐酸トリブチル及び希釈剤を回収する
に際し、先ず廃溶媒に含まれている高沸点の劣化生成物
を薄膜蒸発式蒸留装置により除去し、次いで精留塔によ
り燐酸トリブチルと希釈剤を分離し回収することを特徴
とする廃溶媒の処理方法。Spent nuclear fuel is dissolved in a nitric acid aqueous solution in the reprocessing process, and then radioactive materials are extracted with a solution consisting of tributyl phosphate and a diluent.When recovering tributyl phosphate and the diluent from the waste solvent containing the tributyl phosphate and the diluent, A method for treating waste solvent, which comprises first removing high-boiling-point degraded products contained in the waste solvent using a thin-film evaporative distillation device, and then separating and recovering tributyl phosphate and a diluent using a rectification column.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2199886A JPH0631847B2 (en) | 1986-02-05 | 1986-02-05 | Waste solvent treatment method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2199886A JPH0631847B2 (en) | 1986-02-05 | 1986-02-05 | Waste solvent treatment method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62180299A true JPS62180299A (en) | 1987-08-07 |
| JPH0631847B2 JPH0631847B2 (en) | 1994-04-27 |
Family
ID=12070687
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2199886A Expired - Lifetime JPH0631847B2 (en) | 1986-02-05 | 1986-02-05 | Waste solvent treatment method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0631847B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113571223A (en) * | 2021-07-07 | 2021-10-29 | 中国核电工程有限公司 | Method and device for treating radioactive organic extractant waste liquid |
| CN117198582A (en) * | 2023-09-26 | 2023-12-08 | 中国核电工程有限公司 | Method for recovering radioactive organic waste liquid and recovery device used by same |
-
1986
- 1986-02-05 JP JP2199886A patent/JPH0631847B2/en not_active Expired - Lifetime
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113571223A (en) * | 2021-07-07 | 2021-10-29 | 中国核电工程有限公司 | Method and device for treating radioactive organic extractant waste liquid |
| CN113571223B (en) * | 2021-07-07 | 2024-03-08 | 中国核电工程有限公司 | Method and device for treating radioactive organic extractant waste liquid |
| CN117198582A (en) * | 2023-09-26 | 2023-12-08 | 中国核电工程有限公司 | Method for recovering radioactive organic waste liquid and recovery device used by same |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0631847B2 (en) | 1994-04-27 |
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