JP4451966B2 - Cleaning method of organic solvent for spent nuclear fuel reprocessing - Google Patents
Cleaning method of organic solvent for spent nuclear fuel reprocessing Download PDFInfo
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- JP4451966B2 JP4451966B2 JP2000184780A JP2000184780A JP4451966B2 JP 4451966 B2 JP4451966 B2 JP 4451966B2 JP 2000184780 A JP2000184780 A JP 2000184780A JP 2000184780 A JP2000184780 A JP 2000184780A JP 4451966 B2 JP4451966 B2 JP 4451966B2
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- Prior art keywords
- organic solvent
- dissolved
- spent
- solvent
- carbon dioxide
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- 239000003960 organic solvent Substances 0.000 title claims description 59
- 238000004140 cleaning Methods 0.000 title claims description 24
- 238000012958 reprocessing Methods 0.000 title claims description 17
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims description 17
- 238000000034 method Methods 0.000 title claims description 14
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 claims description 56
- 239000001569 carbon dioxide Substances 0.000 claims description 28
- 229910002092 carbon dioxide Inorganic materials 0.000 claims description 28
- 239000007864 aqueous solution Substances 0.000 claims description 22
- 239000002904 solvent Substances 0.000 claims description 18
- 239000012530 fluid Substances 0.000 claims description 17
- 239000000243 solution Substances 0.000 claims description 8
- 239000002699 waste material Substances 0.000 claims description 8
- 230000006866 deterioration Effects 0.000 claims description 5
- 238000000605 extraction Methods 0.000 claims description 5
- 238000000926 separation method Methods 0.000 claims description 5
- 238000010586 diagram Methods 0.000 description 7
- 239000007788 liquid Substances 0.000 description 7
- 238000006243 chemical reaction Methods 0.000 description 5
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 238000000354 decomposition reaction Methods 0.000 description 3
- 239000000203 mixture Substances 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 2
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 2
- 230000015556 catabolic process Effects 0.000 description 2
- 238000006731 degradation reaction Methods 0.000 description 2
- 239000011259 mixed solution Substances 0.000 description 2
- 238000002156 mixing Methods 0.000 description 2
- 229910017604 nitric acid Inorganic materials 0.000 description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 2
- 238000011069 regeneration method Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000005406 washing Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 239000004215 Carbon black (E152) Substances 0.000 description 1
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- PTYMQUSHTAONGW-UHFFFAOYSA-N carbonic acid;hydrazine Chemical compound NN.OC(O)=O PTYMQUSHTAONGW-UHFFFAOYSA-N 0.000 description 1
- 239000003153 chemical reaction reagent Substances 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000839 emulsion Substances 0.000 description 1
- LOEUCBBZEHMJQN-UHFFFAOYSA-N hydrazine;oxalic acid Chemical compound NN.OC(=O)C(O)=O LOEUCBBZEHMJQN-UHFFFAOYSA-N 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 230000007062 hydrolysis Effects 0.000 description 1
- 238000006460 hydrolysis reaction Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 239000010808 liquid waste Substances 0.000 description 1
- 229940094933 n-dodecane Drugs 0.000 description 1
- 238000003608 radiolysis reaction Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000001172 regenerating effect Effects 0.000 description 1
- 229910000029 sodium carbonate Inorganic materials 0.000 description 1
Images
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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P20/00—Technologies relating to chemical industry
- Y02P20/50—Improvements relating to the production of bulk chemicals
- Y02P20/54—Improvements relating to the production of bulk chemicals using solvents, e.g. supercritical solvents or ionic liquids
-
- 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
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- Extraction Or Liquid Replacement (AREA)
Description
【0001】
【発明の属する技術分野】
本発明は、有機溶媒の洗浄再生方法に関し、特に使用済核燃料の再処理に使用される有機溶媒の洗浄方法に関する。
【0002】
【従来の技術】
軽水冷却型原子炉は現在広く使用されているが、その使用済燃料の再処理は、一般にピューレックス法で行われ、硝酸水溶液を用いて使用済燃料の細片を溶かす。硝酸水溶液に溶かされたウランやプルトニウムなどの有用物は、有機溶媒を用いて抽出され、再使用のため回収される。有機溶媒としては、例えばリン酸トリブチル(TBP)を溶かした炭化水素混合物が使用される。このような有機溶媒は一般に再生して循環使用されるが、前述のウランの抽出時等において、加水分解、放射線分解が生じ、これによる分解生成物を含んでいる。このような分解生成物は再処理工程において、ウラン、プルトニウムの回収率の低下、除染係数の低下、クラッド、エマルジョンの生成など、悪影響を及ぼすので例えば図5に示すように処理され、再生された有機溶媒が再使用される。即ち、図において、使用済燃料の再処理工程1から排出された使用済有機溶媒3に洗浄水溶液5a、5bを接触させ、分解生成物(以下劣化溶媒という。)を洗浄水溶液5a、5bに溶解させて廃液9a、9bとして分離する。再生有機溶媒11は、使用済燃料の再処理工程1へ戻されて使用される。洗浄水溶液5a、5bとしては、炭酸ナトリウム水溶液、水酸化ナトリウム水溶液などのアルカリ洗浄液ゃ、シュウ酸ヒドラジン水溶液、炭酸ヒドラジン水溶液などのソルトフリー試薬などが使用される。
【0003】
【発明が解決しようとする課題】
以上のように、使用済核燃料再処理工程において、有機溶媒中に生成される劣化溶媒は、種々あるためこれを洗浄水溶液を用いて除去しようとすると、そのための抽出操作が4回も必要となる。このため、処理操作が煩雑になると共に抽出器も4個必要となって装置も大型になるから、有機溶媒の洗浄処理コストも大きなものであった。
従って、本発明の課題は、処理操作も簡単で、シンプルな設備でも実施できる使用済核燃料再処理用有機溶媒の洗浄方法を提供することである。
【0004】
【課題を解決するための手段】
前述の課題を解決するため、本発明の使用済核燃料再処理用有機溶媒の洗浄方法によれば、使用済核燃料再処理工程の抽出に使用された劣化溶媒含有使用済有機溶媒から劣化溶媒を分離するため、有機溶媒を選択溶解する二酸化炭素などの超臨界流体を使用する。即ち、本発明の一態様において、劣化溶媒含有使用済有機溶媒に超臨界流体を接触させて該使用済有機溶媒を該超臨界流体に溶解させ、該使用済有機溶媒を溶解した該超臨界流体と洗浄水溶液とを向流接触させて劣化溶媒を洗浄水溶液に溶解させかつ有機溶媒を超臨界二酸化炭素に溶解された儘とし、劣化溶媒を含む前記水溶液を廃液として分離し、しかる後前記有機溶媒を溶解した前記超臨界流体に減圧分離操作を施して超臨界流体と有機溶媒とに分離する。分離された有機溶媒は再生されたもので、使用済核燃料再処理工程の抽出に再使用できる。
【0005】
【発明の実施の形態】
以下、添付の図面を参照して本発明の実施形態を説明する。尚、従来の技術に関する図面を含め、全図にわたり同一部分(物質、工程など)には、同一の符号を付している。
図1を参照するに、使用済燃料の再処理工程1から出た使用済有機溶媒3に、洗浄水溶液21を加えて混合23する。この混合により、使用済有機溶媒3中の劣化溶媒は洗浄水溶液に溶け、有機溶媒と劣化溶媒を溶解した水溶液との混合液25が得られる。次に、混合液25に超臨界状態(圧力12〜20MPa、温度40〜60℃)のCO2(以下超臨界二酸化炭素という。)27を作用させ、有機溶媒を超臨界二酸化炭素に溶解29させる。この有機溶媒の溶解29により、劣化溶媒を溶解した水溶液は廃液31として分離される。有機溶媒を溶解した超臨界二酸化炭素33は次いで減圧分離操作35により10MPa以下の圧力に減圧され、有機溶媒は析出し、二酸化炭素37と再生有機溶媒11とに分離される。再生有機溶媒11は、図示されるように使用済燃料の再処理工程1に戻されて再使用され、又図示されていないが二酸化炭素37は再圧縮され、超臨界流体状態の超臨界二酸化炭素27に戻される。尚、前記実施形態においては、超臨界流体として二酸化炭素を用いたが、これに限定されるものではなく他の超臨界流体を用いても良い。
【0006】
図2には、前述の工程を持つ有機溶媒洗浄再生方法を実施する設備の系統図が示されている。反応槽41は、使用済有機溶媒3と洗浄水溶液21を受け入れ、これらを混合すると共に超臨界二酸化炭素27を受け入れる。反応槽41は又、液体状態の廃液31をしかるべき設備に排出すると共に有機溶媒を溶解した超臨界二酸化炭素33を減圧弁47を介してブレークベッセル43へ送る。そして、低圧のブレークベッセル43内において、再生有機溶媒11と気体又は液体の二酸化炭素37とに分離される。二酸化炭素37は貯槽45に戻され、再使用される。
【0007】
次に、本発明の別の実施形態を図3を参照して説明する。図3を参照するに、使用済燃料の再処理工程1から前記実施形態と同様に出た使用済有機溶媒3に、超臨界状態(圧力12〜20MPa、温度40〜60℃)の超臨界二酸化炭素27を作用させ、使用済有機溶媒3を超臨界二酸化炭素に溶解51させる。使用済有機溶媒3を溶解した超臨界二酸化炭素53に更に洗浄水溶液21を混合55する。この混合55により、使用済有機溶媒3中の劣化溶媒は洗浄水溶液21に溶け、劣化溶媒を溶解した水溶液からなる廃液57が分離される。このようにして得られた、有機溶媒を溶解した超臨界二酸化炭素33は、次いで減圧分離操作35により10MPa以下の圧力に減圧され、有機溶媒は析出し、二酸化炭素37と再生有機溶媒11とに分離される。再生有機溶媒11と二酸化炭素37は、その後、前述の実施形態と同様に処理される。尚、本実施形態においても、二酸化炭素以外の超臨界流体が使用できる。
【0008】
図4には、前述の第2の実施形態として説明された有機溶媒洗浄再生方法を実施する設備の系統図が示されている。反応槽61は使用済有機溶媒(劣化溶媒含有)3を受け入れ、これに超臨界二酸化炭素27を作用させて溶解する。使用済有機溶媒3を溶解した超臨界二酸化炭素53は更に反応槽63に送られ、ここで超臨界二酸化炭素53と洗浄水溶液21とが向流接触される。この向流接触により、劣化溶媒は洗浄水溶液21に溶解し、有機溶媒は超臨界二酸化炭素に溶解された儘となる。劣化溶媒含有洗浄水溶液21は、廃液57として分離して取り出され、又有機溶媒を溶解した超臨界二酸化炭素33は減圧弁47を介してブレークベッセル43へ送られる。その後の処理は図2の場合と同様である。
【0009】
【発明の効果】
以上説明したように、本発明によれば、リン酸トリブチル、n−ドデカンなどの有機溶媒は溶解するが水溶液は溶解しないという選択溶解性を有する超臨界流体を使用するので、劣化溶媒の分離洗浄が単純になると共に超臨界流体は再使用が可能であるので、廃液処理量が減少し、コストが低減できる。
【図面の簡単な説明】
【図1】本発明の実施形態を示す工程図である。
【図2】前記実施形態に係る方法を実施するための設備の系統図である。
【図3】本発明の別の実施形態を示す工程図である。
【図4】前記別の実施形態に係る方法を実施するための設備の系統図である。
【図5】従来の方法を示す工程図である。
【符号の説明】
1 使用済燃料の再処理工程
3 使用済有機溶媒
11 再生有機溶媒
21 洗浄水溶液
23 混合
25 混合液
27 超臨界二酸化炭素
31 廃液
33 有機溶媒を溶解した超臨界二酸化炭素
35 減圧・分離操作
37 二酸化炭素
41 反応槽
43 ブレークベッセル
45 貯槽
47 減圧弁[0001]
BACKGROUND OF THE INVENTION
The present invention relates to a method for cleaning and regenerating an organic solvent, and more particularly to a method for cleaning an organic solvent used for reprocessing spent nuclear fuel.
[0002]
[Prior art]
Light water-cooled nuclear reactors are currently widely used, but reprocessing of spent fuel is generally performed by the Purex method, and nitric acid aqueous solution is used to dissolve spent fuel debris. Useful substances such as uranium and plutonium dissolved in an aqueous nitric acid solution are extracted using an organic solvent and recovered for reuse. As the organic solvent, for example, a hydrocarbon mixture in which tributyl phosphate (TBP) is dissolved is used. Such an organic solvent is generally regenerated and recycled, but hydrolysis and radiolysis occur at the time of extraction of uranium as described above, and contain decomposition products. Such decomposition products are adversely affected in the reprocessing step, such as a decrease in the recovery rate of uranium and plutonium, a decrease in the decontamination coefficient, cladding, and the formation of emulsions. Organic solvent is reused. That is, in the figure, cleaning
[0003]
[Problems to be solved by the invention]
As described above, in the spent nuclear fuel reprocessing step, there are various kinds of deteriorated solvents generated in the organic solvent. Therefore, if it is attempted to remove these using a cleaning aqueous solution, four extraction operations are required. . For this reason, the processing operation becomes complicated, and four extractors are required, which increases the size of the apparatus, resulting in a high cost for cleaning the organic solvent.
Accordingly, an object of the present invention is to provide a method for cleaning an organic solvent for spent nuclear fuel reprocessing which can be carried out with a simple facility and with a simple processing operation.
[0004]
[Means for Solving the Problems]
In order to solve the above-described problems, according to the cleaning method for spent nuclear fuel reprocessing organic solvent of the present invention, the degraded solvent is separated from the spent organic solvent-containing spent organic solvent used in the extraction of the spent nuclear fuel reprocessing step. Therefore, a supercritical fluid such as carbon dioxide that selectively dissolves an organic solvent is used. That is, in one embodiment of the present invention, the deterioration solvent-containing spent organic solvent by contacting the supercritical fluid dissolving the spent organic solvent for said use the supercritical fluid, the supercritical dissolving the spent organic solvent for said use and dissolved in fluid and cleaning solution to the cleaning solution deterioration solvent was countercurrent contact with the organic solvent and as one likes dissolved in supercritical carbon dioxide, separating the aqueous solution containing the deterioration solvent as waste, after which the organic The supercritical fluid in which the solvent is dissolved is subjected to a vacuum separation operation to separate it into a supercritical fluid and an organic solvent. The separated organic solvent has been regenerated and can be reused for extraction in the spent nuclear fuel reprocessing step.
[0005]
DETAILED DESCRIPTION OF THE INVENTION
Embodiments of the present invention will be described below with reference to the accompanying drawings. In addition, the same code | symbol is attached | subjected to the same part (substance, a process, etc.) over all drawings including drawing regarding a prior art.
Referring to FIG. 1, a cleaning
[0006]
FIG. 2 shows a system diagram of equipment for carrying out the organic solvent cleaning and regeneration method having the above-described steps. The
[0007]
Next, another embodiment of the present invention will be described with reference to FIG. Referring to FIG. 3, the spent
[0008]
FIG. 4 shows a system diagram of equipment for carrying out the organic solvent cleaning and regeneration method described as the second embodiment. The
[0009]
【The invention's effect】
As described above, according to the present invention, a supercritical fluid having selective solubility in which an organic solvent such as tributyl phosphate and n-dodecane is dissolved but an aqueous solution is not dissolved is used. However, since the supercritical fluid can be reused, the amount of waste liquid treated can be reduced and the cost can be reduced.
[Brief description of the drawings]
FIG. 1 is a process diagram showing an embodiment of the present invention.
FIG. 2 is a system diagram of equipment for carrying out the method according to the embodiment.
FIG. 3 is a process diagram showing another embodiment of the present invention.
FIG. 4 is a system diagram of equipment for carrying out the method according to another embodiment.
FIG. 5 is a process diagram showing a conventional method.
[Explanation of symbols]
DESCRIPTION OF SYMBOLS 1 Reprocessing process of spent
Claims (1)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2000184780A JP4451966B2 (en) | 2000-06-20 | 2000-06-20 | Cleaning method of organic solvent for spent nuclear fuel reprocessing |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2000184780A JP4451966B2 (en) | 2000-06-20 | 2000-06-20 | Cleaning method of organic solvent for spent nuclear fuel reprocessing |
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| Publication Number | Publication Date |
|---|---|
| JP2002006079A JP2002006079A (en) | 2002-01-09 |
| JP4451966B2 true JP4451966B2 (en) | 2010-04-14 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2000184780A Expired - Lifetime JP4451966B2 (en) | 2000-06-20 | 2000-06-20 | Cleaning method of organic solvent for spent nuclear fuel reprocessing |
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| JP (1) | JP4451966B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100821138B1 (en) | 2006-09-28 | 2008-04-14 | 경희대학교 산학협력단 | Method for Purifying Waste Oil Using Supercritical Solvent and its Purifier |
| KR101016348B1 (en) | 2008-08-14 | 2011-02-25 | 주식회사 대영기공 | Refining method and purification device for waste oil using supercritical solvent and separator |
-
2000
- 2000-06-20 JP JP2000184780A patent/JP4451966B2/en not_active Expired - Lifetime
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| Publication number | Publication date |
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| JP2002006079A (en) | 2002-01-09 |
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