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Class Information
Number: 976/DIG.280
Name: Nuclear technology > Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor (e.g., within its pressure vessel) [g21c-19/00] > Reprocessing of irradiated fuel [g21c-19/42] > Of irradiated solid fuel [g21c-19/44] > Nonaqueous processes [g21c-19/48]
Description:










Patents under this class:

Patent Number Title Of Patent Date Issued
8506786 Method for recovery of residual actinide elements from chloride molten salt Aug. 13, 2013
6960326 Method of separating uranium from irradiated nuclear fuel Nov. 1, 2005
6793894 Pyrochemical reprocessing method for spent nuclear fuel and induction heating system to be used in pyrochemical reprocessing method Sep. 21, 2004
5531868 Advanced electrorefiner design Jul. 2, 1996
4880506 Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels Nov. 14, 1989
4814046 Process to separate transuranic elements from nuclear waste Mar. 21, 1989
4544531 Uranium hexafluoride purification process Oct. 1, 1985
4399108 Method for reprocessing and separating spent nuclear fuels Aug. 16, 1983
4392995 Molten tin reprocessing of spent nuclear fuel elements Jul. 12, 1983
4331618 Treatment of fuel pellets May. 25, 1982
4297174 Pyroelectrochemical process for reprocessing irradiated nuclear fuels Oct. 27, 1981
4285891 Method of removing fission gases from irradiated fuel Aug. 25, 1981
4279875 Method of releasing fission gases from irradiated fuel Jul. 21, 1981
4271126 Fluidized bed reactor for working up carbon coated particles Jun. 2, 1981
4228141 Process for a gasification of graphite Oct. 14, 1980
4225560 Nuclear fuel reprocessing apparatus Sep. 30, 1980
4202861 Method for dry reprocessing of irradiated nuclear fuels May. 13, 1980
4134941 Spherical fuel elements made of graphite for temperature reactors and process for reworking it after the irradiation Jan. 16, 1979
4092397 Pyrochemical separation of plutonium from irradiated nuclear fuels, by thermal decomposition in molten nitrates May. 30, 1978
3984519 Process to transport carbon from a zone to another one, by means of a carrier fluid acting inside a closed system, particularly for the reprocessing of nuclear fuel elements having a graphite Oct. 5, 1976
3982928 Separation of uranium from (Th,U)O.sub.2 solid solutions Sep. 28, 1976
3981960 Reprocessing method of caramic nuclear fuels in low-melting nitrate molten salts Sep. 21, 1976











 
 
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