CN103451428A - Ruthenium purifying technology in plutonium purification cycle of Purex process - Google Patents
Ruthenium purifying technology in plutonium purification cycle of Purex process Download PDFInfo
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- CN103451428A CN103451428A CN2012101669216A CN201210166921A CN103451428A CN 103451428 A CN103451428 A CN 103451428A CN 2012101669216 A CN2012101669216 A CN 2012101669216A CN 201210166921 A CN201210166921 A CN 201210166921A CN 103451428 A CN103451428 A CN 103451428A
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Abstract
The invention belongs to the technical field of nuclear fuel postprocessing, and discloses a ruthenium purifying technology in a plutonium purification cycle of a Purex process; according to the ruthenium purifying technology, extraction agent 2AX and detergent 2AS are added in 2A tank for removing a small amount of ruthenium element in 2AF material liquid, the used extraction agent 2AX comprises 30%TBP (Tri-Butyl-Phosphate)/kerosene, the detergent 2AS is an aqueous solution with C(HNO3) being 0.5-1.5 mol/L, the flow ratio of 2AF:2AX is 3.5-6, the extraction count is 8-10 grades and the washing grade is more than 6 grades. The ruthenium purifying technology can further purify the ruthenium, and can improve the quality of a final plutonium product of the Purex process.
Description
Technical field
The invention belongs to the nuclear fuel reprocessing technical field, be specifically related to the purification process of ruthenium in Purex flow process plutonium purification cycle.
Background technology
The Purex flow process comprises codecontamination partitioning cycle, plutonium purification cycle and uranium decontamination cycle.One of main purpose of codecontamination partitioning cycle is will realize separating to greatest extent between uranium, plutonium and fission element, and uranium decontamination cycle and plutonium purification cycle are in order to obtain highly purified uranium, plutonium product.Ruthenium is one of the fission product that will remove in aftertreatment, is strong gamma activity nucleic, and its amount in uranium, plutonium product is directly determining the personnel protection standard of post-processing operation, so the content of ruthenium is an important test item of uranium, plutonium product.
In the codecontamination partitioning cycle, by adding extraction agent, make uranium, plutonium enter organic phase, the fission elements such as ruthenium enter raffinate, but still have a small amount of ruthenium to enter the plutonium purification cycle with its extraction form.The main task of plutonium purification cycle is that the thick product liquid of plutonium containing sliver and uranium that the codecontamination partitioning cycle is obtained carries out purifying and concentrated, to obtain qualified plutonium product liquid, and meets the requirement of subsequent technique, and its process diagram is as Fig. 1.Ruthenium in the plutonium purification cycle from purification in the codecontamination partitioning cycle have 2 important different: (1) ruthenium concentration in power reactor spent fuel aftertreatment codecontamination partitioning cycle is 0.22g/gPu, far above the ruthenium concentration 22.5 μ g/gPu in the plutonium purification cycle, concentration differs approximately 10000 times; (2) organic phase uranium in codecontamination cycle, the plutonium saturation ratio is higher is 75%, is beneficial to the purification of ruthenium, and in the plutonium purification cycle organic phase uranium, plutonium saturation ratio to hang down be 15% left and right, be unfavorable for the purification of ruthenium.Therefore, significant to the research of micro-ruthenium behavior and trend in the plutonium purification cycle.Have no the report of the purification of ruthenium in relevant plutonium purification cycle both at home and abroad in open source literature.
Summary of the invention
(1) goal of the invention
According to the existing problem of prior art, the invention provides and a kind ofly can purify the technique of ruthenium in the plutonium purification cycle, this technique can further purify ruthenium, at the plutonium yield, is greater than under 99.9% prerequisite, the df of ruthenium is greater than 1000, has improved the quality of the final plutonium product of Purex flow process.
(2) technical scheme
In order to address the above problem, the present invention is achieved by the following technical solutions: in the 2A groove, add extraction agent 2AX and washing composition 2AS that a small amount of ruthenium element in the 2AF feed liquid is removed, key is, extraction agent 2AX used consists of 30%TBP/ kerosene, and washing composition 2AS is c (HNO
3the aqueous solution of)=0.5 ~ 1.5mol/L, stream is than 2AF:2AX=3.5 ~ 6, and extraction progression is 8 ~ 10 grades, and washing progression is greater than 6 grades.
(3) beneficial effect
The purification process of ruthenium in Purex flow process plutonium purification cycle provided by the invention, propose first to carry out the purification of micro-ruthenium in the plutonium purification cycle, its beneficial effect is: (1) purifies micro-ruthenium in the plutonium purification cycle can further reduce ruthenium content, improve the plutonium product purity, reduce operator's protection level.(2) the plutonium yield is high, the ruthenium df is large.Propose stream than 2AF:2AX=3.5 ~ 6, extraction progression is 8 ~ 10 grades, and the processing condition that washing progression is greater than 6 grades are greater than at the plutonium yield under 99.9% prerequisite, and the df of ruthenium is greater than 1000.
The accompanying drawing explanation
Fig. 1. plutonium purification cycle process diagram
embodiment
Below in conjunction with specification drawings and specific embodiments, the present invention is further elaborated.
embodiment 1
Be under 20 ℃ of conditions in temperature, in the 2A groove, add extraction agent 2AX and washing composition 2AS that the fission elements such as a small amount of uranium in the 2AF feed liquid and ruthenium are removed, key is, extraction agent 2AX used is 30%TBP/ kerosene, and washing composition 2AS is c (HNO
3the aqueous solution of)=0.5mol/L, stream is than 2AF:2AX:2AS=3.5:1:0.45, the consisting of of 2AF feed liquid used: c (Pu
4+)=6.8g/L, c (UO
2 2+)=0.74g/L, c (HNO
3)=3.5mol/L, the aqueous solution of c (Ru)=0.3108mg/L, the extraction progression of selecting is 8 grades, and washing progression is 6 grades, and organic phase and water are in a ratio of 2:1.
During experiment, first with not uranium-bearing and plutonium feed liquid, filled groove two hours, then add the feed liquid of uranium-bearing and plutonium, after operation 5.0h, each gets up-to-date style at a flash in 2 hours, after operation 16h, stops the groove analysis.
Experimental result: the yield of uranium is greater than 99.9%, and the material balance of uranium is 97%, and the material balance of acid is 98%, the df DF that the yield of plutonium is 99.95%, Ru
ru=2653, show the experimentation operational excellence, experimental result is reliable.
The step used with embodiment 1 is identical, and different is that washing composition 2AS is c (HNO
3the aqueous solution of)=1mol/L, the stream of selecting is than 2AF:2AX:2AS=5:1:0.45, and 2AF consists of c (Pu
4+)=2.75g/L, c (UO
2 2+)=1.2g/L, c (HNO
3)=3.5mol/L, the aqueous solution of c (Ru)=0.054mg/L, extraction progression is 9 grades, and washing progression is 8 grades, and temperature is 30 ℃, and experimental results is: the df DF that the plutonium yield is 99.97%, Ru
ru=3590.
embodiment 3
The step used with embodiment 1 is identical, and different is that washing composition 2AS is c (HNO
3the aqueous solution of)=1.5mol/L, the stream of selecting is than 2AF:2AX:2AS=6:1:0.45, and 2AF consists of c (Pu
4+)=2.75g/L, c (UO
2 2+)=1.2g/L, c (HNO
3)=3.5mol/L, the aqueous solution of c (Ru)=0.054mg/L, extraction progression is 10 grades, and washing progression is 10 grades, and temperature is 30 ℃, and experimental results is: the df DF that the plutonium yield is 99.98%, Ru
ru=3120.
Claims (4)
1.Purex the purification process of ruthenium in flow process plutonium purification cycle, this technique is as extraction agent 2AX with 30%TBP/ kerosene, it is characterized in that, this technique is in the 2A groove, to add extraction agent 2AX and washing composition 2AS that the ruthenium in the 2AF feed liquid is removed, and washing composition 2AS used is c (HNO
3the aqueous solution of)=0.5 ~ 1.5mol/L.
2. the purification process of ruthenium in Purex flow process plutonium purification cycle according to claim 1, is characterized in that, described 2AF is with 2AX stream than 2AF:2AX=3.5 ~ 6, and extraction progression is 8 ~ 10 grades, and washing progression is greater than 6 grades.
3. the purification process of ruthenium in Purex flow process plutonium purification cycle according to claim 1, is characterized in that, best washing composition 2AS is that concentration is c (HNO
3the aqueous solution of)=1mol/L.
4. the purification process of ruthenium in Purex flow process plutonium purification cycle according to claim 1, is characterized in that, the temperature condition of this technique is 20 ℃ ~ 30 ℃.
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| CN201210166921.6A CN103451428B (en) | 2012-05-28 | 2012-05-28 | Ruthenium purifying technology in plutonium purification cycle of Purex process |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105913887A (en) * | 2016-04-14 | 2016-08-31 | 中国原子能科学研究院 | Plutonium purification cycle process using formaldoxime as back extraction reagent |
| CN110308262A (en) * | 2019-07-08 | 2019-10-08 | 中国工程物理研究院材料研究所 | It is a kind of based on TOA extraction soil in238Pu/239+240Pu analysis method |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0143749A1 (en) * | 1983-11-29 | 1985-06-05 | GebràDer Sulzer Aktiengesellschaft | Liquid-liquid extraction process of gallium from aqueous basic solutions using an organic extractant |
| US4656011A (en) * | 1984-02-13 | 1987-04-07 | British Nuclear Fuel Plc | Process of treating nuclear fuel |
-
2012
- 2012-05-28 CN CN201210166921.6A patent/CN103451428B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0143749A1 (en) * | 1983-11-29 | 1985-06-05 | GebràDer Sulzer Aktiengesellschaft | Liquid-liquid extraction process of gallium from aqueous basic solutions using an organic extractant |
| US4656011A (en) * | 1984-02-13 | 1987-04-07 | British Nuclear Fuel Plc | Process of treating nuclear fuel |
Non-Patent Citations (1)
| Title |
|---|
| 张宇等: ""单甲基肼改善铀纯化循环中钌的净化"", 《原子能科学技术》 * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105913887A (en) * | 2016-04-14 | 2016-08-31 | 中国原子能科学研究院 | Plutonium purification cycle process using formaldoxime as back extraction reagent |
| CN105913887B (en) * | 2016-04-14 | 2018-01-19 | 中国原子能科学研究院 | It is a kind of to use formaldoxime to be stripped the plutonium purification cycle technique of reagent |
| CN110308262A (en) * | 2019-07-08 | 2019-10-08 | 中国工程物理研究院材料研究所 | It is a kind of based on TOA extraction soil in238Pu/239+240Pu analysis method |
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| CN103451428B (en) | 2015-03-11 |
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