Patent Number: 
Section: claims

1. A method for producing and extracting a radioisotope fission product, the method including:(a) providing a target including solid phase uranium oxide;(b) irradiating, by a nuclear reactor, the target with neutrons so as to convert a first portion of the solid phase uranium oxide into oxides of radioisotope fission products;(c) gaseously extracting at least one of the oxides from the irradiated target of step (b), said extracting comprising halogenating the at least one of the oxides using an extraction gas including Cl2 gas so as to produce at least one gas phase oxidized and halogenated radioisotope fission product, wherein the at least one gas phase oxidized and halogenated radioisotope fission product includes molybdenum-99, and so as to produce a first residual target including a remainder of the irradiated target of step (b) less the at least one of the oxides extracted;(d) irradiating, by the nuclear reactor, the first residual target of step (c) with neutrons so as to convert a second portion of the solid phase uranium oxide into oxides of the radioisotope fission products; and(e) gaseously extracting the at least one of the oxides from the irradiated first residual target of step (d), said extracting comprising halogenating the at least one of the oxides using the extraction gas so as to additionally produce at least one gas phase oxidized and halogenated radioisotope fission product. 2. The method of claim 1, wherein the solid phase uranium oxide provided in step (a) has a U-235 enrichment above about 20%. 3. The method of claim 1, wherein the solid phase uranium oxide provided in step (a) has a U-235 enrichment less than about 20%. 4. The method of claim 1, wherein the solid phase uranium oxide provided in step (a) includes UO3 or U3O8. 5. The method of claim 1, wherein step (b) comprises irradiating the target in the nuclear reactor. 6. The method of claim 5, wherein step (c) comprises removing the target is from within the reactor for the extracting of step (c). 7. The method of claim 1, wherein step (b) comprises substituting the target for a nuclear reactor fuel element. 8. The method of claim 1, wherein the target provided in step (a) includes a primary containment. 9. The method of claim 1, wherein the target provided in step (a) comprises:a length of cladding having upper and lower ends and defining an interior space;upper and lower endcaps sealed to the upper and lower ends; andat least one gas port in fluid communication with the interior space; andwherein the uranium oxide is disposed within the interior space and has a form selected from the group consisting of powder, granules, or porous annular pellets. 10. The method of claim 9, wherein the target provided in step (a) further comprises a barrier layer disposed on an interior surface of the cladding. 11. The method of claim 9, wherein the cladding of the target provided in step (a) includes silicon carbide or quartz. 12. The method of claim 1, wherein the extracting of step (c) comprises converting the molybdenum-99 to molybdenum oxychloride (MoO2Cl2), a gaseous species. 13. The method of claim 1, the extraction gas of step (c) further including an oxygen-containing species selected from the group consisting of Ox, H2O, NOx, COx and ClOx, where x can take on any chemically permissible value. 14. The method of claim 1, wherein the extracting of step (c) comprises extracting a plurality of gaseous species. 15. The method of claim 1, wherein step (c) further comprises:using a gas inflow system coupled to the target to introduce the extraction gas into the target;heating the target to promote halogenating the at least one of the oxides using the extraction gas;using a gas outflow system coupled to the target to transfer the at least one gas phase oxidized and halogenated radioisotope fission product from the target; andcollecting the transferred at least one gas phase oxidized and halogenated radioisotope fission product in a recovery chamber. 16. The method of claim 15, wherein the transferred at least one gas phase oxidized and halogenated radioisotope fission product of step (c) includes molybdenum oxychloride (MoO2Cl2). 17. The method of claim 15, wherein the target is heated during step (c) to a temperature in a range from about 200 C to about 1500 C. 18. The method of claim 15, wherein during step (c) the at least one gas phase oxidized and halogenated radioisotope fission product is transferred out of the target to the recovery chamber at a temperature sufficiently high to inhibit solidification of the at least one gas phase oxidized and halogenated radioisotope fission product during the transfer. 19. The method of claim 15, wherein during step (c), introducing the extraction gas into the target comprises continuously flowing the extraction gas into the target during the steps of converting, transferring, and collecting. 20. The method of claim 15, wherein during step (c), introducing the extraction gas into the target comprises initial introduction of the extraction gas, a period of no flow of the extraction gas during formation of the at least one gas phase oxidized and halogenated radioisotope fission product, and a resumed flow of the extraction gas to extract and transfer the at least one gas phase oxidized and halogenated radioisotope fission product. 21. The method of claim 15, step (c) further comprising, after transferring the at least one gas phase oxidized and halogenated radioisotope fission product out of the target, filling the target with a fill gas, and returning the target to the nuclear reactor for the irradiating of step (d). 22. The method of claim 1, wherein step (b) comprises irradiating the target adjacent to the nuclear reactor. 23. The method of claim 22, wherein step (c) comprises the target remaining adjacent to the nuclear reactor during the extracting of step (c). 24. The method of claim 22, wherein step (c) comprises removing the target from adjacent to the nuclear reactor for the extracting of step (c).