Framatome & Cie.
82Patents
0Active
82Granted
35Portfolio score
Filing activity: Apr 3, 1981 → Apr 16, 1987
Most-cited patents
| Patent | Title | Area | Cited by | Status |
|---|---|---|---|---|
| US4761748A | Method for validating the value of a parameter | Physics | 120 | Expired |
| US4684375A | Method for gasifying a material using a circulating fluidized bed | Emerging Cross-Sectional Technologies | 53 | Expired |
| US4590797A | Thermal system for measuring liquid levels | Emerging Cross-Sectional Technologies | 34 | Expired |
| US4652416A | Fuel assembly for a pressurized water nuclear reactor | Emerging Cross-Sectional Technologies | 27 | Expired |
| US4483205A | Apparatus for removing deposits from irradiated fuel elements | Emerging Cross-Sectional Technologies | 24 | Expired |
| US4452183A | Method and device for unclogging the top surface of the tube plate of a steam generator | Mechanical Engineering; Lighting; Heating | 24 | Expired |
| US4553889A | Expanding plug | Emerging Cross-Sectional Technologies | 21 | Expired |
| US4566310A | Method of inspecting the operation of a valve and mechanical test bench for performing the method | Mechanical Engineering; Lighting; Heating | 20 | Expired |
| US4585609A | Method of monitoring an electricity generating station equipped with a nuclear reactor | Emerging Cross-Sectional Technologies | 18 | Expired |
| US4681495A | Device and process for fixing two parts with a captive screw | Mechanical Engineering; Lighting; Heating | 18 | Expired |
| US4562038A | Device for guiding a control cluster in a nuclear reactor | Emerging Cross-Sectional Technologies | 17 | Expired |
| US4585613A | Process for the replacement of guide pins of a guiding tube forming part of the top internal equipment of a pressurized water nuclear reactor, and corresponding apparatus | Emerging Cross-Sectional Technologies | 16 | Expired |
| US5006305A | Device for guiding the control clusters of nuclear reactors | Emerging Cross-Sectional Technologies | 16 | Expired |
| US4624750A | Process for corrosion protection of a steam generator tube and device for making use of this process | Mechanical Engineering; Lighting; Heating | 15 | Expired |
| US4569365A | Device for detecting the operation of a valve | Emerging Cross-Sectional Technologies | 15 | Expired |
| US4544521A | Actuating device for two clusters of control rods movable vertically in one and the same fuel array of the core of a nuclear reactor | Emerging Cross-Sectional Technologies | 15 | Expired |
| US4784824A | Emergency cooling device for a pressurized water nuclear reactor | Emerging Cross-Sectional Technologies | 15 | Expired |
| US4770237A | Process for circulating solid particles within a fluidization chamber and fluidization chamber for carrying out the process | Emerging Cross-Sectional Technologies | 14 | Expired |
| US4646556A | Process and apparatus for testing a pilot-operated safety valve | Mechanical Engineering; Lighting; Heating | 14 | Expired |
| US4683106A | Wiring installation above the cover of a nuclear reactor vessel for connection of electric devices | Emerging Cross-Sectional Technologies | 13 | Expired |
| US4701299A | Modular lining for adapting the containment to the core of a pressurized water nuclear reactor | Emerging Cross-Sectional Technologies | 11 | Expired |
| US4687174A | Device for centering and guiding a roller supporting a heavy component | Emerging Cross-Sectional Technologies | 11 | Expired |
| US4587076A | Sealing device for the drive shaft of a high pressure fluid pump | Mechanical Engineering; Lighting; Heating | 10 | Expired |
| US4522782A | Fuel assembly for a nuclear reactor | Emerging Cross-Sectional Technologies | 10 | Expired |
| US4674560A | Process and apparatus for control of the heat transfer produced in a fluidized bed | Mechanical Engineering; Lighting; Heating | 9 | Expired |
Source: USPTO / EPO open patent data. Counts and citation impact are objective bibliographic measures.