JPH0212095A - Method for cleaning solvent - Google Patents
Method for cleaning solventInfo
- Publication number
- JPH0212095A JPH0212095A JP63163252A JP16325288A JPH0212095A JP H0212095 A JPH0212095 A JP H0212095A JP 63163252 A JP63163252 A JP 63163252A JP 16325288 A JP16325288 A JP 16325288A JP H0212095 A JPH0212095 A JP H0212095A
- Authority
- JP
- Japan
- Prior art keywords
- nitric acid
- condensate
- tbp
- solvent
- butyl phosphate
- 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
- 239000002904 solvent Substances 0.000 title claims abstract description 32
- 238000000034 method Methods 0.000 title claims abstract description 26
- 238000004140 cleaning Methods 0.000 title claims description 16
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims abstract description 39
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims abstract description 33
- 229910017604 nitric acid Inorganic materials 0.000 claims abstract description 33
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 claims abstract description 21
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 18
- 239000000463 material Substances 0.000 claims abstract description 13
- 229940094933 n-dodecane Drugs 0.000 claims abstract description 13
- 230000004992 fission Effects 0.000 claims abstract description 12
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 12
- 239000008346 aqueous phase Substances 0.000 claims abstract description 7
- 239000012074 organic phase Substances 0.000 claims abstract description 7
- 238000001291 vacuum drying Methods 0.000 claims abstract description 4
- DOIRQSBPFJWKBE-UHFFFAOYSA-N dibutyl phthalate Chemical compound CCCCOC(=O)C1=CC=CC=C1C(=O)OCCCC DOIRQSBPFJWKBE-UHFFFAOYSA-N 0.000 claims description 8
- 238000000638 solvent extraction Methods 0.000 claims description 8
- 239000000446 fuel Substances 0.000 claims description 7
- 238000004519 manufacturing process Methods 0.000 claims description 7
- 238000012958 reprocessing Methods 0.000 claims description 7
- -1 etc. Substances 0.000 claims description 3
- 230000001172 regenerating effect Effects 0.000 claims 1
- 239000002699 waste material Substances 0.000 abstract description 19
- 239000012071 phase Substances 0.000 abstract description 5
- 230000005484 gravity Effects 0.000 abstract description 4
- 238000010438 heat treatment Methods 0.000 abstract description 4
- 238000005260 corrosion Methods 0.000 abstract description 2
- 230000007797 corrosion Effects 0.000 abstract description 2
- 238000004880 explosion Methods 0.000 abstract description 2
- 239000002351 wastewater Substances 0.000 abstract 3
- 239000002826 coolant Substances 0.000 abstract 2
- 238000001816 cooling Methods 0.000 abstract 1
- 238000001704 evaporation Methods 0.000 abstract 1
- 238000000859 sublimation Methods 0.000 abstract 1
- 230000008022 sublimation Effects 0.000 abstract 1
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 18
- 239000007788 liquid Substances 0.000 description 10
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 7
- 239000003507 refrigerant Substances 0.000 description 6
- 235000011121 sodium hydroxide Nutrition 0.000 description 6
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 6
- BVKZGUZCCUSVTD-UHFFFAOYSA-L Carbonate Chemical compound [O-]C([O-])=O BVKZGUZCCUSVTD-UHFFFAOYSA-L 0.000 description 5
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 229910052708 sodium Inorganic materials 0.000 description 4
- 239000011734 sodium Substances 0.000 description 4
- 238000005092 sublimation method Methods 0.000 description 4
- 239000000126 substance Substances 0.000 description 4
- 238000005406 washing Methods 0.000 description 4
- 230000008014 freezing Effects 0.000 description 3
- 238000007710 freezing Methods 0.000 description 3
- 235000010344 sodium nitrate Nutrition 0.000 description 3
- 239000004317 sodium nitrate Substances 0.000 description 3
- 239000010426 asphalt Substances 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000006386 neutralization reaction Methods 0.000 description 1
- 239000003960 organic solvent Substances 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 229910000029 sodium carbonate Inorganic materials 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- SRVJKTDHMYAMHA-WUXMJOGZSA-N thioacetazone Chemical compound CC(=O)NC1=CC=C(\C=N\NC(N)=S)C=C1 SRVJKTDHMYAMHA-WUXMJOGZSA-N 0.000 description 1
- VGBPIHVLVSGJGR-UHFFFAOYSA-N thorium(4+);tetranitrate Chemical compound [Th+4].[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O VGBPIHVLVSGJGR-UHFFFAOYSA-N 0.000 description 1
- 238000004017 vitrification Methods 0.000 description 1
- 239000010887 waste solvent Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は再処理工場、燃料製造工場等で用いる溶媒抽出
における溶媒洗浄工程の代替として利用する溶媒洗浄方
法に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a solvent cleaning method used as an alternative to the solvent cleaning step in solvent extraction used in reprocessing plants, fuel manufacturing plants, etc.
一般に、再処理工場や燃料製造工場等の溶媒抽出工程に
用いて劣化した溶媒は、炭酸ナトリウム、水酸化ナトリ
ウムによる溶媒洗浄工程に送られて炭酸ソーダ液、苛性
ソーダ液で洗浄し、不純物を除去して再生溶媒として再
利用している。Generally, degraded solvents used in solvent extraction processes at reprocessing plants and fuel manufacturing plants are sent to a solvent cleaning process using sodium carbonate and sodium hydroxide, where they are washed with soda carbonate and caustic soda solutions to remove impurities. and reused as recycled solvent.
しかしながらこのような方法によると、溶媒劣化が進ん
だものは、溶媒洗浄しても容易に再生できず炭酸ソーダ
液、苛性ソーダ液を含む洗浄廃液の発生量が多くなる欠
点がある。また、これらナトリウムを含む廃液は、硝酸
と結合して硝酸ナトリウムとなり、硝酸すトリウムを含
む廃液は蒸発缶等で濃縮しても硝酸ナトリウム含有量に
より一定程度以上には減容できない。However, this method has the disadvantage that if the solvent has deteriorated, it cannot be easily regenerated even by solvent washing, and a large amount of washing waste liquid containing soda carbonate solution and caustic soda solution is generated. In addition, these sodium-containing waste liquids combine with nitric acid to become sodium nitrate, and even if waste liquids containing thorium nitrate are concentrated in an evaporator or the like, the volume cannot be reduced beyond a certain level due to the sodium nitrate content.
本発明は上記問題点を解決するためのもので、廃棄物処
理、処分の観点からは可能な限り炭酸ソーダ、苛性ソー
ダのようなナトリウムを含む物質の利用をなくすため、
洗浄液の利用をやめ、廃液発生壇を減らして廃液処理の
負荷を軽くし、しかも装置の腐蝕・火災・爆発が起きな
い低温を利用して安全性の高い溶媒洗浄方法を提供する
。ことを目的とする。The present invention is intended to solve the above problems, and from the viewpoint of waste treatment and disposal, to eliminate the use of sodium-containing substances such as soda carbonate and caustic soda as much as possible.
To provide a highly safe solvent cleaning method that eliminates the use of cleaning liquid, reduces the waste liquid generation stage, reduces the load of waste liquid treatment, and uses low temperature that does not cause corrosion, fire, or explosion of equipment. The purpose is to
そのために本発明の溶媒洗浄方法は、再処理工場、燃料
製造工場等の溶媒抽出から発生する溶媒の再生のための
溶媒洗浄工程において、凍結真空乾燥法により水、硝酸
、昇華する核種、ｎ−ドデカン等よりなる凝１１液と、
リン酸トリ−ｎ−ブチル（以下ＴＢＰと言う）、フタル
酸ジブチル（以下ＤＢＰと言う）、リン酸ブチル（以下
ＭＢＰと言う）および昇華しない核燃料物質、核分裂生
成物よりなるＴＢＰ等残留物とに分離し、前記凝縮液は
、水、硝酸等よりなる水相とｎ−ドデカン等よりなる有
機相とに分離し、前記ＴＢＰ等残留物は、硝酸溶液によ
り洗浄し、ＴＢＰに同伴している核燃料物質、核分裂生
成物を分離し、ＴＢＰを再利用することを再利用する。For this purpose, the solvent cleaning method of the present invention uses a freeze-vacuum drying method to remove water, nitric acid, sublimated nuclides, n- A coagulated liquid 11 consisting of dodecane etc.,
To residues such as tri-n-butyl phosphate (hereinafter referred to as TBP), dibutyl phthalate (hereinafter referred to as DBP), butyl phosphate (hereinafter referred to as MBP), and TBP made of non-sublimed nuclear fuel materials and fission products. The condensate is separated into an aqueous phase consisting of water, nitric acid, etc. and an organic phase consisting of n-dodecane, etc. The TBP and other residues are washed with a nitric acid solution and the nuclear fuel accompanying the TBP is separated. Recycle the material, separate the fission products and reuse the TBP.
〔作用］
本発明は再処理工場、燃料製造工場等で利用している溶
媒抽出の溶媒洗浄工程において、ナトリウムを含む物質
（炭酸ソーダ、苛性ソーダ）の利用する溶媒洗浄工程の
代替法として、凍結真空乾燥法を用い、凝縮液とＴＢＰ
等残留物に分離し、凝縮液は、さらに比重差によりｎ−
ドデカン等の可燃性有機溶媒と水、硝酸等に分離し、Ｔ
ＢＰ等残留物は硝酸溶液で洗浄することによりＴＢＰを
再生させることができる。[Function] The present invention is an alternative method to the solvent cleaning process of solvent extraction used in reprocessing plants, fuel manufacturing plants, etc., which uses sodium-containing substances (soda carbonate, caustic soda). Using the drying method, condensate and TBP
The condensate is further divided into n-
Separate into flammable organic solvent such as dodecane, water, nitric acid, etc.
TBP can be regenerated by washing residual BP etc. with a nitric acid solution.
（実施例） 以下、実施例を図面を参照して説明する。(Example) Examples will be described below with reference to the drawings.
第１図は本発明の廃溶媒処理の全体構成を示す図である
。ｌは凍結乾燥器、２は溶媒、３は冷媒、４は加熱媒体
、５は凝縮器、６は真空ポンプ、７は冷媒、８は凝縮液
受槽、９は有機相、１０は水相、１１はｎ−ドデカン等
、１２は水・硝酸等、１３はＴＢＰ・核燃料物質・核分
裂生成物、１４は廃硝酸溶液である。FIG. 1 is a diagram showing the overall configuration of waste solvent treatment according to the present invention. 1 is a freeze dryer, 2 is a solvent, 3 is a refrigerant, 4 is a heating medium, 5 is a condenser, 6 is a vacuum pump, 7 is a refrigerant, 8 is a condensate receiver, 9 is an organic phase, 10 is an aqueous phase, 11 12 is water, nitric acid, etc., 13 is TBP, nuclear fuel material, nuclear fission product, and 14 is waste nitric acid solution.
図において、凍結乾燥器１へは溶媒供給系から溶媒２が
供給されるようになっている。凍結乾燥器ｌへは冷媒３
、加熱媒体４が供給排出され、溶媒２を冷却凍結、昇華
乾燥するようになっている。In the figure, a solvent 2 is supplied to a freeze dryer 1 from a solvent supply system. Refrigerant 3 to freeze dryer 1
, a heating medium 4 is supplied and discharged, and the solvent 2 is cooled, frozen, and sublimated to dry.
凍結乾燥器１で昇華した物質は凝縮器５に供給される。The substance sublimed in the freeze dryer 1 is supplied to the condenser 5.
凝縮器５には冷媒７が供給排出されると共に、真空ポン
プ６で排気されており、４ｉ縮液は凝縮液受槽゛８へ貯
留し、比重差により有機相９と水相１０とに分離し、そ
れぞれ有機相からはｎ−ドデカン等１１が抽出され、水
相１０からは水・硝酸等１２が抽出され再利用される。A refrigerant 7 is supplied to and discharged from the condenser 5, and is also exhausted by a vacuum pump 6, and the 4i condensate is stored in a condensate receiving tank 8 and separated into an organic phase 9 and an aqueous phase 10 due to the difference in specific gravity. , n-dodecane etc. 11 are extracted from the organic phase, and water, nitric acid etc. 12 are extracted from the aqueous phase 10 and reused.
また凍結乾燥器ｌで蒸発しないＴＢＰ１３と核燃料物質
・核分裂生成物を含む廃硝酸溶液１４は残留物として取
り出され、ＴＢＰ１３は分離されて再利用され、廃硝酸
溶液１４は廃棄系へ導かれることになる。In addition, the TBP 13 that does not evaporate in the freeze dryer 1 and the waste nitric acid solution 14 containing nuclear fuel materials and fission products are taken out as residue, the TBP 13 is separated and reused, and the waste nitric acid solution 14 is led to the disposal system. Become.
こうして、ＴＢＰ等、ｎ−ドデカン等、核燃料物質、核
分裂生成物、硝酸、水等が再処理工場９、燃料製造工場
等の溶媒抽出工程から排出され、再生もしくは廃棄され
る。In this way, nuclear fuel materials such as TBP, n-dodecane, nuclear fission products, nitric acid, water, etc. are discharged from the solvent extraction process of the reprocessing plant 9, fuel manufacturing plant, etc., and are recycled or disposed of.
第２図は第１図のプロセスフローを示す図で、■は溶媒
、■は凍結工程、■は昇華工程、■はＴＢＰ等残留物、
■は洗浄工程、■はＴＢＰ、■は廃硝酸溶液、■は調整
槽、■は廃液処理系、［相］は凝縮器、■は凝縮液、＠
はｎ−ドデカン等、■は水・硝酸等である。Figure 2 is a diagram showing the process flow of Figure 1, where ■ is the solvent, ■ is the freezing process, ■ is the sublimation process, ■ is the residue such as TBP, etc.
■ is the cleaning process, ■ is TBP, ■ is the waste nitric acid solution, ■ is the adjustment tank, ■ is the waste liquid treatment system, [phase] is the condenser, ■ is the condensate, @
is n-dodecane, etc., and ■ is water, nitric acid, etc.
ＴＢＰ等、ｎ−ドデカン等、核燃料物質、核分裂生成物
、水、硝酸等を含む再処理工場、燃料製造工場等の溶媒
抽出工程から発生する溶媒■は、凍結工程■において冷
却凍結される。凍結された溶媒凍結体は、昇華工程■に
おいて加熱、減圧、真空状態に置かれ、凍結体より溶媒
中に含まれている硝酸、水、ｎ−ドデカン等と昇華する
核種が昇華され、それらは凝縮器により凝縮され凝縮液
■になる。Solvent (1) generated from the solvent extraction process at a reprocessing factory, fuel manufacturing factory, etc., containing nuclear fuel materials such as TBP, n-dodecane, etc., nuclear fission products, water, nitric acid, etc., is cooled and frozen in the freezing process (2). The frozen solvent frozen body is heated, depressurized, and placed in a vacuum state in the sublimation process (2), and the nuclides that sublimate with nitric acid, water, n-dodecane, etc. contained in the solvent are sublimated from the frozen body, and they are It is condensed by the condenser and becomes condensate liquid■.
凝縮液■は、比重差により有機相のｎ−ドデカン等＠と
水相の水、硝酸等＠に分離され、可燃性のｎ−ドデカン
等＠は焼却され、水、硝酸等＠は再利用される。The condensate ■ is separated into an organic phase, n-dodecane, etc., and an aqueous phase, water, nitric acid, etc., due to the difference in specific gravity.The flammable n-dodecane, etc., are incinerated, and the water, nitric acid, etc., are recycled. Ru.
昇華工程■において、ＴＢＰ、ＤＢＰ、ＭＢＰおよび昇
華しない核燃ｔ４物質、核分裂生成物等は、ＴＢＰ等残
留物■となる。ＴＢＰ等残留物■は、洗浄工程において
硝酸溶液■で洗浄するとＴＢＰ■と核燃料物質、核分裂
生成物を含む廃硝酸溶液■に分けられる。In the sublimation process (2), TBP, DBP, MBP, nuclear fuel T4 materials, nuclear fission products, etc. that do not sublimate become TBP and other residues (2). When TBP and other residues (2) are washed with nitric acid solution (2) in the cleaning process, they are separated into TBP (2) and waste nitric acid solution (2) containing nuclear fuel materials and fission products.
ＴＢＰ■は、調整槽■においてｎ−ドデカン等と混合さ
れて再利用される。廃硝酸溶液■は、廃液処理系■へ送
られる。TBP (2) is mixed with n-dodecane etc. in the adjustment tank (2) and reused. The waste nitric acid solution (■) is sent to the waste liquid treatment system (■).
なお、以上の説明においてはＴＢＰを例にとって説明し
たが、本発明による溶媒の処理方法は、ＴＢＰのみでな
く、溶媒抽出で使用されている他の種類の溶媒の分離再
生にも適用可能であることは明らかである。Although TBP was used as an example in the above explanation, the solvent processing method according to the present invention is applicable not only to TBP but also to the separation and regeneration of other types of solvents used in solvent extraction. That is clear.
以上のように本発明によれば、再処理工場、燃料製造工
場等で利用している溶媒抽出の溶媒洗浄工程を凍結真空
乾燥法で代替することができ、凝縮液とＴＢＰ等残留物
に分離できる。そして凝縮液は、さらに比重差によりｎ
−ドデカン等の可燃性有ａ熔媒と水、硝酸等に分離でき
、ＴＢＰ等残留物は硝酸溶液で洗浄することによりＴＢ
Ｐを再生させることができる。As described above, according to the present invention, the solvent cleaning process of solvent extraction used in reprocessing plants, fuel manufacturing plants, etc. can be replaced by the freeze-vacuum drying method, and the condensate and residues such as TBP can be separated. can. The condensate is further divided into n due to the difference in specific gravity.
- Can be separated into flammable atomized solvent such as dodecane, water, nitric acid, etc., and TBP and other residues can be removed by washing with nitric acid solution.
P can be regenerated.
その結果、ナトリウムを含む物質（炭酸ソーダ、苛性ソ
ーダ）による溶媒洗浄が不要となり、アスファルト固化
、ガラス固化へ送られる硝酸ソーダ層を大幅に減らすこ
とが可能となる。As a result, solvent cleaning with sodium-containing substances (soda carbonate, caustic soda) becomes unnecessary, and the amount of sodium nitrate layer sent to asphalt solidification and vitrification can be significantly reduced.
第１図は本発明の溶媒処理の全体構成を説明する図、第
２図は第１図のプロセスフローを示す図である。
■・・・凍結乾燥器、２・・・溶媒、３・・・冷媒、４
・・・加熱媒体、５・・・凝縮器、６・・・真空ポンプ
、７・・・冷媒、８・・・凝縮液受槽、９・・・存機相
、１０・・・水相、１１・・・ｎ−ドデカン等、１２・
・・水・硝酸等、１３・・・ＴＢＰ−核燃料物質・核分
裂生成物、１４・・・廃硝酸溶液、■・・・溶媒、■・
・・凍結工程、■・・・昇華工程、■・・・ＴＢＰ等残
留物、■・・・中和洗浄工程、■・・・ＴＢ Ｉ）、■
・・・廃硝酸溶液、■・・・調整槽、■・・・廃液処理
系、［相］・・・凝縮器、■・・・凝縮液、■・・・ｎ
・ドデカン等、■・・・水・硝酸等。
第１図
出 願 人FIG. 1 is a diagram explaining the overall configuration of the solvent treatment of the present invention, and FIG. 2 is a diagram showing the process flow of FIG. 1. ■...Freeze dryer, 2...Solvent, 3...Refrigerant, 4
. . . Heating medium, 5. Condenser, 6. Vacuum pump, 7. Refrigerant, 8. Condensate receiver tank, 9. Existing phase, 10. Water phase, 11. ... n-dodecane etc., 12.
...Water, nitric acid, etc., 13...TBP-Nuclear fuel material/fission products, 14...Waste nitric acid solution, ■...Solvent, ■・
・・Freezing process, ■・Sublimation process, ■・Residues such as TBP, ■・Neutralization cleaning process, ■・TB I), ■
...waste nitric acid solution, ■...adjustment tank, ■...waste treatment system, [phase]...condenser, ■...condensate, ■...n
・Dodecane, etc., ■...Water, nitric acid, etc. Figure 1 Applicant
Claims (3)
する溶媒の再生のための溶媒洗浄工程において、凍結真
空乾燥法により水、硝酸、昇華する核種、ｎ−ドデカン
等よりなる凝縮液と、リン酸トリ−ｎ−ブチル、フタル
酸ジブチル、リン酸ブチルおよび昇華しない核燃料物質
、核分裂生成物よりなるリン酸トリ−ｎ−ブチル等残留
物とに分離することを特徴とする溶媒洗浄方法。(1) In the solvent cleaning process for regenerating the solvent generated from solvent extraction at reprocessing plants, fuel manufacturing plants, etc., a condensate consisting of water, nitric acid, sublimated nuclides, n-dodecane, etc. is removed by freeze-vacuum drying. , tri-n-butyl phosphate, dibutyl phthalate, butyl phosphate, and residues such as tri-n-butyl phosphate consisting of non-sublimated nuclear fuel materials and fission products.
デカン等よりなる有機相とに分離する請求項１記載の溶
媒洗浄方法。(2) The solvent cleaning method according to claim 1, wherein the condensate is separated into an aqueous phase consisting of water, nitric acid, etc., and an organic phase consisting of n-dodecane, etc.
液により洗浄し、リン酸トリ−ｎ−ブチルに同伴してい
るフタル酸ジブチル、リン酸ブチル核燃料物質、核分裂
生成物を分離し、リン酸トリ−ｎ−ブチルを再利用する
請求項１または２記載の溶媒洗浄方法。(3) The tri-n-butyl phosphate and other residues are washed with a nitric acid solution to separate the dibutyl phthalate, butyl phosphate nuclear fuel material, and fission products that accompany the tri-n-butyl phosphate. 3. The solvent cleaning method according to claim 1 or 2, wherein tri-n-butyl phosphate is reused.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63163252A JPH0212095A (en) | 1988-06-30 | 1988-06-30 | Method for cleaning solvent |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63163252A JPH0212095A (en) | 1988-06-30 | 1988-06-30 | Method for cleaning solvent |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0212095A true JPH0212095A (en) | 1990-01-17 |
Family
ID=15770257
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63163252A Pending JPH0212095A (en) | 1988-06-30 | 1988-06-30 | Method for cleaning solvent |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0212095A (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4980756A (en) * | 1972-11-15 | 1974-08-03 | ||
| JPS57117U (en) * | 1980-06-02 | 1982-01-05 |
-
1988
- 1988-06-30 JP JP63163252A patent/JPH0212095A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4980756A (en) * | 1972-11-15 | 1974-08-03 | ||
| JPS57117U (en) * | 1980-06-02 | 1982-01-05 |
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