Process for the treatment of a phosphite-containing waste stream
US-2020354304-A1 · Nov 12, 2020 · US
US2017337998A1 · US · A1
| Field | Value |
|---|---|
| Publication number | US-2017337998-A1 |
| Application number | US-201715598918-A |
| Country | US |
| Kind code | A1 |
| Filing date | May 18, 2017 |
| Priority date | May 18, 2016 |
| Publication date | Nov 23, 2017 |
| Grant date | — |
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Methods and systems are provided for continuous-flow production of radioisotopes with high specific activity. Radioisotopes with high specific activity produced according to the methods described are also provided. The methods can include causing a liquid capture matrix to contact a target containing a target nuclide; irradiating the target with radiation, ionizing radiation, particles, or a combination thereof to produce the radionuclides that are ejected from the target and into the capture matrix; and causing the liquid capture matrix containing the radionuclides to flow from the target to recover the capture matrix containing the radionuclides with high specific activity. The methods are suitable for the production of a variety of radionuclides. For example, in some aspects the target nuclide is 237 Np, and the radionuclide is 238 Np that decays to produce 238 Pu. In other aspects, the target nuclide is 98 Mo, and the radionuclide is 99 Mo that decays to produce 99m Tc.
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We claim: 1 . A method of producing radionuclides with high specific activity, the method comprising causing a liquid capture matrix to flow in contact with a target comprising a target nuclide, irradiating the target with radiation, ionizing radiation, particles, or a combination thereof to produce the radionuclides that are ejected from the target and into the capture matrix in contact with the target, and causing the liquid capture matrix containing the radionuclides to flow from the target to recover the capture matrix comprising the radionuclides with high specific activity. 2 . The method of claim 1 , wherein the radionuclides are produced from the target nuclide via a reaction selected from the group consisting of a (n, γ) reaction, a (γ, n) reaction, and a (n, 2n) reaction. 3 . The method of claim 1 , wherein the radiation is selected from the group consisting of neutron radiation, gamma radiation, and a combination thereof. 4 . The method of claim 1 , wherein the radiation comprises thermal neutron radiation, epithermal neutron radiation, or a neutron radiation having a neutron energy above 0.4 eV. 5 . The method of claim 1 , wherein the liquid capture matrix is water. 6 . The method claim 1 , wherein the liquid capture matrix has a pH of about 3 to 5. 7 . The method of claim 1 , wherein the target nuclide has one or more organic ligands attached thereto, and the radionuclides are ejected from the target by breaking one or more bonds with the ligands. 8 . The method of claim 1 , wherein the target nuclide is selected from the group consisting of elements having atomic number from 21 to 102. 9 . The method of claim 1 , wherein the target nuclide is selected from the group consisting of 23 Na, 31 P, 37 Cl, 50 Cr, 55 Mn, 75 As, 81 Br, 89 Y, 98 Mo, 104 Ru, 127 I, 152 Sm, 165 Ho, 174 Yb, 175/176 Lu, 185 Re, 187 Re, 194 Pt, 197 Au and 237 Np. 10 . The method claim 1 , wherein the target nuclide is selected from the group consisting of the lanthanides and the actinides. 11 . The method of claim 1 , wherein the target comprises one or more organic ligands selected from the group consisting of small molecules comprising one or more donor atoms selected from the group consisting of oxygen, nitrogen, and a combination thereof. 12 . The method of claim 1 , wherein the target comprises one or more organic ligands selected from the group consisting of acetylacetonate, picolinate, 8-hydroxyquinolinate, dimethylglyoximate, oxalate, 4-aminobenzoate, glycinate, and derivatives thereof. 13 . The method of claim 1 , wherein the target comprises a support structure having a large surface area, and wherein the target nuclide is in a thin polymer coating on the support structure. 14 . The method of claim 13 , wherein the support structure is a mesoporous resin. 15 . The method of claim 13 , wherein the support structure is a copolymer of styrene and divinylbenzene. 16 . The method of claim 13 , wherein the thin polymer coating on the support structure has a thickness that is less than a recoil range of the target nuclide. 17 . The method of claim 1 , wherein the target has a solubility in the capture matrix of about 0.001 M or less at room temperature. 18 . The method of claim 1 , wherein the enrichment factor is about 3 to 30. 19 . The method of claim 13 , wherein the target nuclide is 237 Np, and wherein the radionuclide is 238 Np that decays to produce 238 Pu. 20 . The method of claim 13 , wherein the target nuclide is 98 Mo, and wherein the radionuclide is 99 Mo that decays to produce 99m Tc.
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