CN103451428B - 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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- CN103451428B CN103451428B CN201210166921.6A CN201210166921A CN103451428B CN 103451428 B CN103451428 B CN 103451428B CN 201210166921 A CN201210166921 A CN 201210166921A CN 103451428 B CN103451428 B CN 103451428B
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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 nuclear fuel reprocessing technical field, be specifically related to the purification process of ruthenium in Purex flow plutonium purification cycle.
Background technology
Purex flow comprises codecontamination partitioning cycle, plutonium purification cycle and uranium decontamination cycle.One of main purpose of codecontamination partitioning cycle will realize uranium, is separated to greatest extent between plutonium with fission element, and uranium decontamination cycle and plutonium purification cycle are to obtain highly purified uranium, plutonium product.Ruthenium is one of fission product will removed in aftertreatment, is strong gamma activity nucleic, and its amount in uranium, plutonium product directly decides the personnel protection standard of post-processing operation, and therefore the content of ruthenium is an important test item of uranium, plutonium product.
By adding extraction agent in codecontamination partitioning cycle, make uranium, plutonium enters organic phase, the fission elements such as ruthenium enter raffinate, but still have a small amount of ruthenium to enter 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 codecontamination partitioning cycle obtains is carried out to purifying and concentrates, and to obtain qualified plutonium product liquid, and meet the requirement of subsequent technique, its process diagram is as Fig. 1.Ruthenium have from the purification in codecontamination partitioning cycle in plutonium purification cycle 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 plutonium purification cycle, concentration difference about 10000 times; (2) organic phase uranium in codecontamination cycle, plutonium saturation ratio is higher is 75%, is beneficial to the purification of ruthenium, and organic phase uranium in plutonium purification cycle, plutonium saturation ratio is lower is about 15%, is unfavorable for the purification of ruthenium.Therefore, significant to the research of ruthenium behavior micro-in plutonium purification cycle and trend.The report about the purification of ruthenium in plutonium purification cycle is had no in domestic and international open source literature.
Summary of the invention
(1) goal of the invention
Problem existing for prior art, the invention provides a kind of technique that can purify ruthenium in plutonium purification cycle, this technique can purify ruthenium further, be greater than the prerequisite of 99.9% at plutonium yield under, the df of ruthenium is greater than 1000, improves the quality of the final plutonium product of Purex flow.
(2) technical scheme
In order to solve the problem, the present invention is achieved by the following technical solutions: in 2A groove, add extraction agent 2AX and washing composition 2AS by a small amount of ruthenium element removing in 2AF feed liquid, 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, flows 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 plutonium purification cycle provided by the invention, the purification carrying out micro-ruthenium in plutonium purification cycle is proposed first, its beneficial effect is: (1) purifies micro-ruthenium in plutonium purification cycle can reduce ruthenium content further, improve plutonium product purity, reduce the protection level of operator.(2) plutonium yield is high, ruthenium df is large.Propose stream than 2AF:2AX=3.5 ~ 6, extraction progression is 8 ~ 10 grades, the processing condition that washing progression is greater than 6 grades, and be greater than the prerequisite of 99.9% at plutonium yield under, the df of ruthenium is greater than 1000.
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
Under temperature is 20 DEG C of conditions, in 2A groove, add extraction agent 2AX and washing composition 2AS by fission element removings such as a small amount of uranium in 2AF feed liquid and rutheniums, key is, extraction agent 2AX used is 30%TBP/ kerosene, and washing composition 2AS is c (HNO
3the aqueous solution of)=0.5mol/L, flows than 2AF:2AX:2AS=3.5:1:0.45, consisting of of 2AF feed liquid used: c (Pu
4+)=6.8g/L, c (UO
2 2+)=0.74g/L, c (HNO
3the aqueous solution of)=3.5mol/L, c (Ru)=0.3108mg/L, the extraction progression selected is 8 grades, and washing progression is 6 grades, and organic phase and aqueous phase are in a ratio of 2:1.
During experiment, first carry out filling groove two hours with not uranium-bearing and plutonium feed liquid, then add the feed liquid of uranium-bearing and plutonium, after running 5.0h, within each 2 hours, get up-to-date style at a flash, after running 16h, stop groove analysis.
Experimental result: the yield of uranium is greater than 99.9%, the material balance of uranium is 97%, and the material balance of acid is 98%, and the yield of plutonium is the df DF of 99.95%, Ru
ru=2653, show experimentation operational excellence, experimental result is reliable.
embodiment 2
The step used with embodiment 1 is identical, is c (HNO unlike washing composition 2AS
3the aqueous solution of)=1mol/L, the stream selected consists of c (Pu than 2AF:2AX:2AS=5:1:0.45,2AF
4+)=2.75g/L, c (UO
2 2+)=1.2g/L, c (HNO
3the aqueous solution of)=3.5mol/L, c (Ru)=0.054mg/L, extraction progression is 9 grades, and washing progression is 8 grades, and temperature is 30 DEG C, and experimental results is: plutonium yield is the df DF of 99.97%, Ru
ru=3590.
embodiment 3
The step used with embodiment 1 is identical, is c (HNO unlike washing composition 2AS
3the aqueous solution of)=1.5mol/L, the stream selected consists of c (Pu than 2AF:2AX:2AS=6:1:0.45,2AF
4+)=2.75g/L, c (UO
2 2+)=1.2g/L, c (HNO
3the aqueous solution of)=3.5mol/L, c (Ru)=0.054mg/L, extraction progression is 10 grades, and washing progression is 10 grades, and temperature is 30 DEG C, and experimental results is: plutonium yield is the df DF of 99.98%, Ru
ru=3120.
Claims (3)
- The purification process of ruthenium in 1.Purex flow process plutonium purification cycle, this technique is as extraction agent 2AX with 30%TBP/ kerosene, it is characterized in that, this technique in 2A groove, adds extraction agent 2AX and washing composition 2AS by the ruthenium removing in 2AF feed liquid, and washing composition 2AS used is c (HNO 3the aqueous solution of)=1mol/L.
- 2. the purification process of ruthenium in Purex flow plutonium purification cycle according to claim 1, is characterized in that, described 2AF and 2AX stream is 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 plutonium purification cycle according to claim 1, it is characterized in that, the temperature condition of this technique is 20 DEG C ~ 30 DEG C.
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| 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 |
| CN110308262B (en) * | 2019-07-08 | 2022-04-29 | 中国工程物理研究院材料研究所 | In soil based on TOA extraction238Pu/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 |
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2012
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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 |
|---|
| "单甲基肼改善铀纯化循环中钌的净化";张宇等;《原子能科学技术》;20091231;第43卷(第12期);正文第1187页1.2、图1及表2 * |
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