JPS63188693A - Purification of tributyl phosphate - Google Patents
Purification of tributyl phosphateInfo
- Publication number
- JPS63188693A JPS63188693A JP62020581A JP2058187A JPS63188693A JP S63188693 A JPS63188693 A JP S63188693A JP 62020581 A JP62020581 A JP 62020581A JP 2058187 A JP2058187 A JP 2058187A JP S63188693 A JPS63188693 A JP S63188693A
- Authority
- JP
- Japan
- Prior art keywords
- phosphate
- tributyl phosphate
- dibutyl
- tributyl
- adsorbent
- 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
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 title claims abstract description 31
- 238000000746 purification Methods 0.000 title 1
- JYFHYPJRHGVZDY-UHFFFAOYSA-N Dibutyl phosphate Chemical compound CCCCOP(O)(=O)OCCCC JYFHYPJRHGVZDY-UHFFFAOYSA-N 0.000 claims abstract description 19
- 239000003463 adsorbent Substances 0.000 claims abstract description 16
- GWEVSGVZZGPLCZ-UHFFFAOYSA-N Titan oxide Chemical compound O=[Ti]=O GWEVSGVZZGPLCZ-UHFFFAOYSA-N 0.000 claims abstract description 9
- OGIDPMRJRNCKJF-UHFFFAOYSA-N titanium oxide Inorganic materials [Ti]=O OGIDPMRJRNCKJF-UHFFFAOYSA-N 0.000 claims abstract description 9
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 claims abstract description 8
- 229910001928 zirconium oxide Inorganic materials 0.000 claims abstract description 8
- 238000000034 method Methods 0.000 claims description 18
- 239000003758 nuclear fuel Substances 0.000 abstract description 7
- 238000012958 reprocessing Methods 0.000 abstract description 7
- 229910052778 Plutonium Inorganic materials 0.000 abstract description 3
- 229910052770 Uranium Inorganic materials 0.000 abstract description 3
- 239000002904 solvent Substances 0.000 abstract description 3
- 239000002699 waste material Substances 0.000 abstract description 2
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 6
- 238000001179 sorption measurement Methods 0.000 description 6
- 238000004821 distillation Methods 0.000 description 4
- 229910019142 PO4 Inorganic materials 0.000 description 3
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 3
- 239000003085 diluting agent Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- NBIIXXVUZAFLBC-UHFFFAOYSA-K phosphate Chemical compound [O-]P([O-])([O-])=O NBIIXXVUZAFLBC-UHFFFAOYSA-K 0.000 description 3
- 239000010452 phosphate Substances 0.000 description 3
- 239000010887 waste solvent Substances 0.000 description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 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 description 1
- 239000004215 Carbon black (E152) Substances 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 150000007513 acids Chemical class 0.000 description 1
- 239000008346 aqueous phase Substances 0.000 description 1
- 239000003729 cation exchange resin Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 230000005865 ionizing radiation Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000011824 nuclear material Substances 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000001172 regenerating effect Effects 0.000 description 1
- 238000000638 solvent extraction Methods 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
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は核燃料再処理工程において使用されるリン酸ト
リブチルの精製方法に関し、更に詳しくはリン酸トリブ
チル中に劣化して存在するリン酸ブチｐをリン酸トリブ
チルから除去してリン酸トリブチルを精製する方法に関
する。Detailed Description of the Invention [Field of Industrial Application] The present invention relates to a method for purifying tributyl phosphate used in a nuclear fuel reprocessing process, and more specifically, it relates to a method for purifying tributyl phosphate that is used in a nuclear fuel reprocessing process. The present invention relates to a method for purifying tributyl phosphate by removing tributyl phosphate from tributyl phosphate.
リン酸トリブチルはウラン、プルトニウムの回収溶媒と
して優れた性能を有しているため、炭化水素系溶剤で希
釈されて主に核燃料再処理施設に利用されている。Tributyl phosphate has excellent performance as a recovery solvent for uranium and plutonium, so it is diluted with a hydrocarbon solvent and used primarily in nuclear fuel reprocessing facilities.
しかし、核燃料再処理施設においては、核物質、核分裂
生成物よシ放出される電離放射線及び溶媒抽出時に水相
として使用される強酸により、リン酸トリブチルは次第
に損傷し、各種の劣化物を生成する。However, in nuclear fuel reprocessing facilities, tributyl phosphate is gradually damaged by ionizing radiation emitted by nuclear materials and fission products, and by strong acids used as the aqueous phase during solvent extraction, resulting in the production of various degraded products. .
生成された劣化物の中でも生成量も多く、製品ウラン、
プルトニウムの純度を極度に低下させるのがリン酸ジプ
チｙである。リン酸ジブチ〃は、リン酸トリブチルの１
次加水分解物であシ、その反応式は下式で示される。Among the degraded products produced, the amount produced is large, and product uranium,
Dipty-y phosphate drastically reduces the purity of plutonium. Dibutyl phosphate is one of tributyl phosphate.
It is a secondary hydrolyzate, and its reaction formula is shown by the following formula.
（Ｃ４Ｈ＊０）ｓＰｏ ＋ Ｈ２０→（０４馬０）２・
ＨＰＯ，＋Ｃ４ＨｏＯＨ従って、現在の核燃料再処理施
設では、リン酸ジプチｐの蓄積したリン酸トリブチルは
プロセス外へ抜き出され、廃溶媒と呼ばれる放射性廃棄
物として貯蔵され、処理、処分に苦慮している。(C4H*0) sPo + H20 → (04 horse 0) 2・
HPO, +C4HoOH Therefore, in current nuclear fuel reprocessing facilities, the tributyl phosphate that has accumulated in dibutyl p phosphate is extracted from the process and stored as radioactive waste called waste solvent, making it difficult to process and dispose of it. .
現在まで廃溶媒となったリン酸トリブチルの再利用方法
として、蒸留法、リン酸付加体性と呼ばれる手法が考え
られている。蒸留法は蒸留によりリン酸トリブチルと希
釈剤を分離するとともにリン酸ジプチμを除去しようと
する方法であシ、リン酸付加体性はリン酸を添加するこ
とＫよシ２相となるリン酸トリブチルと希釈剤を分離す
るとともにリン酸ジプチμを除去しようとするものであ
る。Distillation and a method called phosphoric acid addition have been considered as methods for reusing tributyl phosphate, which has become a waste solvent. The distillation method is a method in which tributyl phosphate and diluent are separated by distillation and dibutyl phosphate is removed.The phosphoric acid adduct property is a method in which tributyl phosphate is separated from the diluent by distillation, and dibutyl phosphate is removed by adding phosphoric acid. The purpose is to separate tributyl and diluent and remove dibutyl phosphate μ.
ところが、上記２手法ではリン酸ジブチルの除去が不完
全であシ、そのためリン酸トリブチルの再利用に至って
いないのが現状である。However, in the above two methods, removal of dibutyl phosphate is incomplete, and therefore tributyl phosphate cannot be reused at present.
本発明は上記従来の技術水準に鑑み、極めて簡単な手法
で廃溶媒となったリン酸トリブチｐを再生精製する方法
を提供しようとするものである。In view of the above-mentioned prior art level, the present invention seeks to provide a method for regenerating and purifying tributyl phosphate, which has become a waste solvent, using an extremely simple method.
本発明者らは、リン酸トリブチルからリン酸ジプチμを
完全に除去するのに吸着剤を使用する方法につき鋭意研
究し、各種吸着剤を製作し、これら吸着剤のリン酸ジブ
チルに対する吸着性能試験を繰返した結果、酸化チタン
を４０〜６０重量％、酸化ジルコニウムを６０〜４０重
量％の割合で含有する吸着剤が、リン酸ジブチμの吸着
に非常に良好な性能を有しているとの知見を得た。The present inventors have conducted extensive research on the method of using adsorbents to completely remove dibutyl phosphate μ from tributyl phosphate, produced various adsorbents, and tested the adsorption performance of these adsorbents for dibutyl phosphate. As a result of repeated experiments, it was found that an adsorbent containing 40 to 60% by weight of titanium oxide and 60 to 40% by weight of zirconium oxide had very good performance in adsorbing dibutymuth phosphate. I gained knowledge.
本発明は上記知見に基づいて完成されたものであって、
・リン酸ジプチ〃を含有するリン酸トリブチルを、酸化
チタン４０〜６０重量％、酸化ジルコニウム６０〜４０
重量％よシなる吸着剤に接触させてリン酸ジプチｐを該
吸着剤上に吸着させることを特徴とするリン酸トリブチ
ルの精製方法である。The present invention was completed based on the above findings, and
・Tributyl phosphate containing dibutyl phosphate is mixed with 40-60% by weight of titanium oxide and 60-40% by weight of zirconium oxide.
This is a method for purifying tributyl phosphate, which comprises contacting with an adsorbent of varying weight % and adsorbing dibutyl phosphate onto the adsorbent.
本発明の一実施例を第１図に沿って説明する。 An embodiment of the present invention will be described with reference to FIG.
先ず、リン酸ジプチｐを８５ ｐｐｍを含む、リン酸ト
リブチｙを第１受液槽１に貯液し、貯液したリン酸トリ
ブチｐをボンデ２を介して吸着塔３へ供給する。吸着塔
３は内径１１ｍ、吸着剤ベッド高さ４６０ｍの空塔で約
４５ｇの吸着剤が充填されている。また吸着塔は２５±
１℃に温度調整されている。First, tributyl phosphate y containing 85 ppm of dibutyl phosphate p is stored in the first liquid receiving tank 1 , and the stored tributyl phosphate p is supplied to the adsorption tower 3 via the bonder 2 . The adsorption tower 3 is an empty tower with an inner diameter of 11 m and an adsorbent bed height of 460 m, and is filled with about 45 g of adsorbent. Also, the adsorption tower is 25±
The temperature is adjusted to 1°C.
この吸着塔に１時間に約（Ｌｌ ９１の速度で、前記リ
ン酸トリブチルを塔頂よシ供給し、塔底より留出した液
をポンプ４を介して第２受液槽５へ導く。ここで、留出
したリン酸トリブチル中に含有するリン酸ジブチル濃度
を経時的に測定し、供給リン酸トリブチル中に含有する
リン酸ジブチル濃度の１０％に相当するリン酸ジブチ／
Ｌ／（こ＼ではａ ３ ｐｐｍ ）が留出液に出現した
時点を破過時間と称する。The tributyl phosphate is supplied from the top of the adsorption tower at a rate of approximately (Ll 91 per hour), and the liquid distilled from the bottom of the tower is guided to the second liquid receiving tank 5 via the pump 4. The concentration of dibutyl phosphate contained in the distilled tributyl phosphate was measured over time, and the dibutyl phosphate concentration corresponding to 10% of the dibutyl phosphate concentration contained in the supplied tributyl phosphate was measured.
The time point at which L/(a 3 ppm in this case) appears in the distillate is called breakthrough time.
第１表に本実施例で得られた劣化生成物の除去効果を示
す。第１表に示されるように従来吸着に頻繁に使用され
ている陽イオン交換樹脂、シリカゲμに比較して格段に
長い破過時間を有していることがわかシ、このことはま
た本発明の吸着剤が、リン酸トリブチルの精製に優れた
特性を有していることを明らかにしている。Table 1 shows the effects of removing degraded products obtained in this example. As shown in Table 1, it has been found that it has a much longer breakthrough time than silicage μ, a cation exchange resin frequently used for adsorption in the past, and this also indicates that the present invention It has been revealed that this adsorbent has excellent properties for purifying tributyl phosphate.
さらに、この実施例の装置を用い、て、酸化チタン及び
酸化ジルコニウムの重量比と破過時間の相関を測定した
ところ第２図に示す結果を得た。この結果、酸化チタン
を４０〜６０重量先酸化ジルコニウムを６０〜４０重量
％含む吸着剤が優れていることが立証された。Furthermore, using the apparatus of this example, the correlation between the weight ratio of titanium oxide and zirconium oxide and the breakthrough time was measured, and the results shown in FIG. 2 were obtained. As a result, it was proved that an adsorbent containing 40 to 60% by weight of titanium oxide and 60 to 40% by weight of zirconium oxide is superior.
第２表に１例として酸化チタンを５０重量％、酸化ジル
コニウム５０重量％を含有した吸着剤の物性を示す。Table 2 shows, as an example, the physical properties of an adsorbent containing 50% by weight of titanium oxide and 50% by weight of zirconium oxide.
第 １ 表
〔発明の効果〕
本発明によればリン酸トリブチル中のリン酸ジブ千ルが
容易に吸着除去され、簡単にリン酸トリブチルを精製す
ることが可能となり、核燃料再処理施設の廃棄物処理量
が減少するという工業的に顕著な効果を奏する。Table 1 [Effects of the Invention] According to the present invention, dibutyl phosphate in tributyl phosphate can be easily adsorbed and removed, making it possible to easily purify tributyl phosphate, thereby reducing waste from nuclear fuel reprocessing facilities. This has an industrially significant effect of reducing the throughput.
第１図は本発明の一実施例を説明するための図、第２図
は本発明で使用する吸着剤の酸化チタンの重量比と破過
時間の関係を示す図表である。FIG. 1 is a diagram for explaining one embodiment of the present invention, and FIG. 2 is a chart showing the relationship between the weight ratio of titanium oxide in the adsorbent used in the present invention and breakthrough time.
Claims (1)
タン４０〜６０重量％、酸化ジルコニウム６０〜４０重
量％よりなる吸着剤に接触させてリン酸ジブチルを該吸
着剤上に吸着させることを特徴とするリン酸トリブチル
の精製方法。It is characterized in that tributyl phosphate containing dibutyl phosphate is brought into contact with an adsorbent comprising 40 to 60% by weight of titanium oxide and 60 to 40% by weight of zirconium oxide, and dibutyl phosphate is adsorbed onto the adsorbent. Method for purifying tributyl phosphate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62020581A JPS63188693A (en) | 1987-02-02 | 1987-02-02 | Purification of tributyl phosphate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62020581A JPS63188693A (en) | 1987-02-02 | 1987-02-02 | Purification of tributyl phosphate |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63188693A true JPS63188693A (en) | 1988-08-04 |
Family
ID=12031181
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62020581A Pending JPS63188693A (en) | 1987-02-02 | 1987-02-02 | Purification of tributyl phosphate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63188693A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2667327A1 (en) * | 1990-09-29 | 1992-04-03 | British Nuclear Fuels Plc | PROCESS FOR PURIFYING ALKYL PHOSPHATE SOLUTIONS IN A HYDROPHOBIC ORGANIC SOLVENT |
-
1987
- 1987-02-02 JP JP62020581A patent/JPS63188693A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2667327A1 (en) * | 1990-09-29 | 1992-04-03 | British Nuclear Fuels Plc | PROCESS FOR PURIFYING ALKYL PHOSPHATE SOLUTIONS IN A HYDROPHOBIC ORGANIC SOLVENT |
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