US2758024A - Method of dissolving binary alloys - Google Patents
Method of dissolving binary alloys Download PDFInfo
- Publication number
- US2758024A US2758024A US477145A US47714554A US2758024A US 2758024 A US2758024 A US 2758024A US 477145 A US477145 A US 477145A US 47714554 A US47714554 A US 47714554A US 2758024 A US2758024 A US 2758024A
- Authority
- US
- United States
- Prior art keywords
- zirconium
- concentration
- dissolving
- uranium
- nitric acid
- 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.)
- Expired - Lifetime
Links
- 238000000034 method Methods 0.000 title claims description 13
- 229910002056 binary alloy Inorganic materials 0.000 title description 2
- KRHYYFGTRYWZRS-UHFFFAOYSA-N Fluorane Chemical compound F KRHYYFGTRYWZRS-UHFFFAOYSA-N 0.000 claims description 18
- 229910000711 U alloy Inorganic materials 0.000 claims description 12
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 9
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 9
- 229910017604 nitric acid Inorganic materials 0.000 claims description 9
- 229910052726 zirconium Inorganic materials 0.000 claims description 9
- BNGXYYYYKUGPPF-UHFFFAOYSA-M (3-methylphenyl)methyl-triphenylphosphanium;chloride Chemical compound [Cl-].CC1=CC=CC(C[P+](C=2C=CC=CC=2)(C=2C=CC=CC=2)C=2C=CC=CC=2)=C1 BNGXYYYYKUGPPF-UHFFFAOYSA-M 0.000 claims description 7
- HXPJIEMQFBIQMQ-UHFFFAOYSA-N [Zr].[U] Chemical compound [Zr].[U] HXPJIEMQFBIQMQ-UHFFFAOYSA-N 0.000 claims description 7
- 239000007864 aqueous solution Substances 0.000 claims description 5
- 229910045601 alloy Inorganic materials 0.000 description 4
- 239000000956 alloy Substances 0.000 description 4
- 239000000446 fuel Substances 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- 239000010935 stainless steel Substances 0.000 description 3
- 229910001220 stainless steel Inorganic materials 0.000 description 3
- 229910052770 Uranium Inorganic materials 0.000 description 2
- QGZKDVFQNNGYKY-UHFFFAOYSA-O ammonium group Chemical class [NH4+] QGZKDVFQNNGYKY-UHFFFAOYSA-O 0.000 description 2
- 239000004615 ingredient Substances 0.000 description 2
- 239000002904 solvent Substances 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- 229910002651 NO3 Inorganic materials 0.000 description 1
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 231100001261 hazardous Toxicity 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000007654 immersion Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
- C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
- C22B60/023—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors halogenated ion as active agent
Definitions
- Zirconium-uranium alloys are being used as fuel material in some types of neutronic reactors.
- the fuel elements have to be dissolved either after irradiation for recovery of the various ingredients and for analytical purposes, or sometimes after inspection when the fuel elements have been found flawy and the metals are to be recovered.
- Zirconium-containing binary uranium alloys have been dissolved heretofore in nitric acid.
- the nitric acid for instance, of a concentration between 7 and 15 M, was found to dissolve the uranium faster than the zirconium whereby a highly reactive zirconium surface was obtained on the alloy bodies. This reactive surface proved to be pyrophoric. If the surface, for instance, was struck with a pointed rod a vigorous reaction took place with evolution of heat and light and forceful ejection of the container contents. Violent shaking produced similar results. Sometimes serious explosions were caused by this phenomenon.
- the concentrations of the ingredients may vary widely.
- the nitric acid concentration may range between 7 and 15 M
- the hydrofluoric acid may be present in a concentration between 0.02 and 0.5 M and the Patented Aug. 7, 1956 aluminum nitrate in a concentration between 0.5 and 1.5 M.
- the quantity of the solvent is, of course, dependent upon these concentrations.
- a ratio of 4 moles hydrofluoric acid per mole of zirconium has given satisfactory results, and within the concentration ranges given above the use of 4 liters of solution per kilogram of alloy was found adequate. While the dissolution may be carried out at room temperature, heating of the solution, preferably to between and 0, proved advantageous.
- Example A SO-gram piece of a uranium alloy containing 2% by weight of zirconium and 98% by weight of uranium was immersed in an aqueous nitric acid-hydrofluoric acidaluminum nitrate solution; the concentrations were 11 M for the nitric acid, 0.3 M for the hydrofluoric acid and 0.75 M for the aluminum nitrate. The process was carried out in a stainless steel container. After about 10 hours practically all of the alloy had dissolved, with the exception of a small residue which weighed less than 6 mg. There was no explosion-like phenomenon and no corrosion of the stainless steel took place.
- the process of this invention was found to be applicable to binary uranium alloys which contain up to 20% by weight of zirconium.
- a process of dissolving binary zirconium-uranium alloys containing up to 20% by weight of zirconium consisting of immersing the alloy in an aqueous solution of nitric acid, hydrofluoric acid and aluminum nitrate.
- aqueous solution contains nitric acid in a concentration of 11M, hydrofluoric acid in a concentration of 0.3 M and aluminum nitrate in a concentration of 0.75 M.
Landscapes
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Geology (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacture And Refinement Of Metals (AREA)
Description
United States Patent li IETHOD OF DISSOLVING BINARY ALLOYS No Drawing. Application December 22, 1954, Serial No. 477,145
5 Claims. (Cl. 75-121) This application deals with a process of dissolving binary uranium alloys, and in particular binary uranium alloys which contain comparatively small quantities of zirconium.
Zirconium-uranium alloys are being used as fuel material in some types of neutronic reactors. The fuel elements have to be dissolved either after irradiation for recovery of the various ingredients and for analytical purposes, or sometimes after inspection when the fuel elements have been found flawy and the metals are to be recovered.
Zirconium-containing binary uranium alloys have been dissolved heretofore in nitric acid. However, the nitric acid, for instance, of a concentration between 7 and 15 M, was found to dissolve the uranium faster than the zirconium whereby a highly reactive zirconium surface was obtained on the alloy bodies. This reactive surface proved to be pyrophoric. If the surface, for instance, was struck with a pointed rod a vigorous reaction took place with evolution of heat and light and forceful ejection of the container contents. Violent shaking produced similar results. Sometimes serious explosions were caused by this phenomenon.
It is an object of this invention to provide a process for dissolving binary zirconium-uranium alloys by which the two components are dissolved at the same rate.
It is another object of this invention to provide a process for dissolving binary zirconium-uranium alloys which is not hazardous.
It is still another object of this invention to provide a process for dissolving binary zirconium-uranium alloys with a solvent that does not corrode stainless steel equipment. I
These objects are accomplished by immersing the zirconium-uranium alloy in an aqueous solution of a mixture consisting of nitric acid, hydrofluoric acid and aluminum nitrate.
The concentrations of the ingredients may vary widely. For instance, the nitric acid concentration may range between 7 and 15 M, the hydrofluoric acid may be present in a concentration between 0.02 and 0.5 M and the Patented Aug. 7, 1956 aluminum nitrate in a concentration between 0.5 and 1.5 M. The quantity of the solvent is, of course, dependent upon these concentrations. A ratio of 4 moles hydrofluoric acid per mole of zirconium has given satisfactory results, and within the concentration ranges given above the use of 4 liters of solution per kilogram of alloy was found adequate. While the dissolution may be carried out at room temperature, heating of the solution, preferably to between and 0, proved advantageous.
Substitution of ammonium silicofiuoride for the hydrofluoric acid gave also satisfactory results; the preferred concentration of the ammonium silicofiuoride was about 0.1 M.
Example A (SO-gram piece of a uranium alloy containing 2% by weight of zirconium and 98% by weight of uranium was immersed in an aqueous nitric acid-hydrofluoric acidaluminum nitrate solution; the concentrations were 11 M for the nitric acid, 0.3 M for the hydrofluoric acid and 0.75 M for the aluminum nitrate. The process was carried out in a stainless steel container. After about 10 hours practically all of the alloy had dissolved, with the exception of a small residue which weighed less than 6 mg. There was no explosion-like phenomenon and no corrosion of the stainless steel took place.
The process of this invention was found to be applicable to binary uranium alloys which contain up to 20% by weight of zirconium.
It will be understood that this invention is not to be limited to the details given herein but that it may be modified within the scope of the appended claims.
What is claimed is:
l. A process of dissolving binary zirconium-uranium alloys containing up to 20% by weight of zirconium consisting of immersing the alloy in an aqueous solution of nitric acid, hydrofluoric acid and aluminum nitrate.
2. The process of claim 1 in which immersion is carried out at elevated temperature.
3. The process of claim 2 in which the temperature ranges between 90 and 100 C.
4. The process of claim 1 in which the nitric acid is present in the aqueous solution in a concentration of from 7 to 15 M, the hydrofluoric acid in a concentration between 0.02 and 0.5 M and the aluminum nitrate in a concentration of between 0.5 and 1.5 M.
5. The process of claim 4 in which the aqueous solution contains nitric acid in a concentration of 11M, hydrofluoric acid in a concentration of 0.3 M and aluminum nitrate in a concentration of 0.75 M.
References Cited in the file of this patent Milner et al.: Analyst, vol. 79, pp. 475-482 (1954). (Copy in Scientific Library.)
Claims (1)
1. A PROCESS OF DISSOLVING BINARY ZIRCONIUM-URANIUM ALLOYS CONTAINING UP TO 20% BY WEIGHT OF ZIRCONIUM CONSISTING OF IMMERSING THE ALLOY IN AN AQUEOUS SOLUTION OF NITRIC ACID, HYDROFLUORIC ACID AND ALUMINUM NITRATE.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US477145A US2758024A (en) | 1954-12-22 | 1954-12-22 | Method of dissolving binary alloys |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US477145A US2758024A (en) | 1954-12-22 | 1954-12-22 | Method of dissolving binary alloys |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US2758024A true US2758024A (en) | 1956-08-07 |
Family
ID=23894709
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US477145A Expired - Lifetime US2758024A (en) | 1954-12-22 | 1954-12-22 | Method of dissolving binary alloys |
Country Status (1)
| Country | Link |
|---|---|
| US (1) | US2758024A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2927855A (en) * | 1957-12-31 | 1960-03-08 | Nat Res Corp | Separation of tantalum |
| US2927854A (en) * | 1957-12-31 | 1960-03-08 | Nat Res Corp | Separation of tantalum |
| US3012849A (en) * | 1959-04-06 | 1961-12-12 | Frederick L Horn | Dissolution of zirconium-containing fuel elements |
-
1954
- 1954-12-22 US US477145A patent/US2758024A/en not_active Expired - Lifetime
Non-Patent Citations (1)
| Title |
|---|
| None * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2927855A (en) * | 1957-12-31 | 1960-03-08 | Nat Res Corp | Separation of tantalum |
| US2927854A (en) * | 1957-12-31 | 1960-03-08 | Nat Res Corp | Separation of tantalum |
| US3012849A (en) * | 1959-04-06 | 1961-12-12 | Frederick L Horn | Dissolution of zirconium-containing fuel elements |
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