| Patent application number | Description | Published |
|---|
| 20080232536 | Spacer and a Fuel Unit for a Nuclear Plant - The invention refers to a spacer for holding a number of elongated fuel rods intended to be located in a nuclear plant, and a fuel unit with such spacers. The spacer encloses a number of cells for receiving a respective fuel rod extending in parallel to a longitudinal axis of the respective cell. Each cell is formed by a sleeve-like member having an upper edge and a lower edge. The sleeve-like member includes a number of abutment surfaces projecting inwardly towards and extending substantially in parallel with the longitudinal axis for abutment to the fuel rod the cell. The lower edge and the upper edge have, seen transversely to the longitudinal axis, a wave-like shape with wave peaks, aligned with a respective one of said abutment surfaces, and wave valleys located between two adjacent ones of said abutment surfaces. | 09-25-2008 |
| 20080267339 | Spacer and a Fuel Unit for a Nuclear Plant - The invention refers to a spacer for holding a number if elongated fuel rods intended to be located in a nuclear plant and to a fuel unit having such spacers. The spacer encloses a number of cells, which each has a longitudinal axis and is arranged to receive a fuel rod in such a way that the fuel rod extends in parallel with the longitudinal axis. Each cell is formed by a sleeve-like member. Each sleeve-like member is manufactured in a sheet-shaped material that is bent to the sleeve-like shape. | 10-30-2008 |
| 20100111242 | METHOD FOR OPERATING A REACTOR OF A NUCLEAR PLANT - A method of operating a nuclear reactor is disclosed. The reactor ( | 05-06-2010 |
| 20100111800 | PRODUCTION OF NUCLEAR GRADE ENRICHED GADOLINIUM AND ERBIUM USING VOLATILE Gd OR Er SPECIES USING AN AERODYNAMIC PROCESS - A method of making Gd or Er isotopes from gaseous compounds containing —BH | 05-06-2010 |
| 20100142667 | DEVICE FOR HANDLING A FUEL ASSEMBLY - The invention refers to a device and a method for handling a fuel assembly ( | 06-10-2010 |
| 20100158185 | METHOD AND APPARATUS OF ESTIMATING DRYOUT PROPERTIES IN A NUCLEAR LIGHT WATER REACTOR - The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product ( | 06-24-2010 |
