G21C 19/42
Reprocessing of irradiated fuel
G21C19/42 (Reprocessing of irradiated fuel) appears on 368 US grants and 226 published applications in this corpus.
Search patents in G21C- Granted patents
- 368
- Published applications
- 226
- Assignees
- 177
- Inventors
- 973
- Latest grant
- 6 Oct 2026
Filings by year
| Year | Granted patents | Published applications |
|---|---|---|
| 1976 | 16 | 0 |
| 1977 | 7 | 0 |
| 1978 | 5 | 0 |
| 1979 | 6 | 0 |
| 1980 | 10 | 0 |
| 1981 | 12 | 0 |
| 1982 | 6 | 0 |
| 1983 | 5 | 0 |
| 1984 | 4 | 0 |
| 1985 | 6 | 0 |
| 1986 | 4 | 0 |
| 1987 | 6 | 0 |
| 1988 | 10 | 0 |
| 1989 | 5 | 0 |
| 1990 | 1 | 0 |
| 1991 | 4 | 0 |
| 1992 | 9 | 0 |
| 1993 | 6 | 0 |
| 1994 | 6 | 0 |
| 1995 | 10 | 0 |
| 1996 | 6 | 0 |
| 1997 | 14 | 0 |
| 1998 | 5 | 0 |
| 1999 | 2 | 0 |
| 2000 | 7 | 0 |
| 2001 | 8 | 2 |
| 2002 | 10 | 5 |
| 2003 | 4 | 6 |
| 2004 | 6 | 2 |
| 2005 | 3 | 3 |
| 2006 | 5 | 7 |
| 2007 | 2 | 3 |
| 2008 | 4 | 7 |
| 2009 | 4 | 11 |
| 2010 | 6 | 17 |
| 2011 | 7 | 12 |
| 2012 | 4 | 17 |
| 2013 | 17 | 14 |
| 2014 | 18 | 9 |
| 2015 | 11 | 8 |
| 2016 | 9 | 17 |
| 2017 | 9 | 6 |
| 2018 | 11 | 11 |
| 2019 | 15 | 5 |
| 2020 | 8 | 11 |
| 2021 | 5 | 11 |
| 2022 | 3 | 7 |
| 2023 | 9 | 9 |
| 2024 | 6 | 13 |
| 2025 | 8 | 8 |
| 2026 | 4 | 5 |
By publication year. Applications have been published since 2001. 2026 runs to 8 Oct.
Subgroups
Granted patents
Recent patents
- Real-time change detection monitoring using isotopic ratio signatures6 Oct 2026US 12,754,332 B2UT-Battelle, LLC
- Continuous removal of fission products from molten-salt fueled nuclear reactors23 Jun 2026US 12,665,099 B2Muons, Inc.
- Process for the repeated irradiation of a radium target9 Jun 2026US 12,651,677 B2TerraPower Isotopes, LLC
- Fission product trap for salt pipe and pump shaft seals and methods of use thereof24 Feb 2026US 12,562,289 B2
- Method for concentrating liquid radioactive waste28 Oct 2025US 12,456,558 B2State Atomic Energy Corporation "Rosatom" On Behalf of the Russian Federation
- Two-step chloride volatility process for separating uranium and transuranic elements from radioactive waste6 Aug 2026US 2026/0229378 A1Brigham Young University
- Conversion of spent nuclear fuel to fluoride salt fuel for molten salt reactors11 Jun 2026US 2026/0162841 A1Board of Regents, The University of Texas System
- Fission product trap for salt pipe and pump shaft seals and methods of use thereof21 May 2026US 2026/0142046 A1
- A method of adjusting oxoacidity14 May 2026US 2026/0135007 A1Seaborg Aps
- Installation and method for converting uranium hexafluoride to uranium dioxide8 Jan 2026US 2026/0008689 A1Framatome
Most cited
By later US patents
- Process and apparatus for oxidizing or reducing dissolved substance64US 4,774,026 AHitachi, Ltd. · 1988
- Method and apparatus for ionizing all the elements in a complex substance such as radioactive waste and separating some of the elements from the other elements59US 5,681,434 A1997
- Supported liquid membrane separation52US 6,086,769 ACommodore Separation Technologies, Inc. · 2000
- Electrorefining process and apparatus for recovery of uranium and a mixture of uranium and plutonium from spent fuels46US 4,880,506 AThe United States of America as represented by the Department of Energy · 1989
- Method for extracting lanthanides and actinides from acid solutions45US 4,548,790 AThe United States of America as represented by the United States Department of Energy · 1985