Abstract: A zirconium-based alloy, suitable for use in a corrosive environment, where it is subjected to increased radiation and comprises 0.5-1.6 percentage by weight Nb and 0.3-0.6 percentage by weight Fe. The alloy is characterised in that it comprises 0.5-0.85 percentage by weight Sn.

Abstract: The present invention relates to a component (1) comprising an element (2), which contains zirconium or a zirconium alloy and which has a surface (3) on which a corrosion protective layer (4) is formed, the oxide layer (4) comprising zirconium oxide. The component (1) is intended to be in an oxidising environment (6) and said oxide layer (4) has an outer surface (5) towards said oxidising environment (6). The element (2) comprises a layer (10), that borders said surface (3) and comprises hydrogen and at least one metal from the group of lanthanum elements and/or from the group platinum metals and/or yttrium which in its elemental form or as an oxide have the ability to effectively dissociate oxygen and H2O. The invention also relates to a method for manufacturing the component (1) and a nuclear facility comprising the component (1).

Abstract: A method for producing a component intended to be subjected to an increased radiation in a corrosive environment, wherein the component includes an alloy which at a first, high temperature has a BCC-structure and which at a second, lower temperature has an HCP-structure, wherein the alloy includes at least one alloying element which has a low solubility in the HCP-structure and wherein the alloy is rapidly cooled from the first to the second temperature while secondary phase particles, which include said alloying element and which contribute to improve corrosion properties are separated in the HCP-structure. The rapid cooling is performed in two stages, wherein the first stage includes a rapid cooling at a relatively lower intensity and the second, subsequent stage includes a rapid cooling at a relatively higher intensity.

Abstract: The present invention relates to a component (1) comprising an element (2), which contains zirconium or a zirconium alloy and which has a surface (3) on which a corrosion protective layer (4) is formed, the oxide layer (4) comprising zirconium oxide. The component (1) is intended to be in an oxidising environment (6) and said oxide layer (4) has an outer surface (5) towards said oxidising environment (6). The element (2) comprises a layer (10), that borders said surface (3) and comprises hydrogen and at least one metal from the group of lanthanum elements and/or from the group platinum metals and/or yttrium which in its elemental form or as an oxide have the ability to effectively dissociate oxygen and H2O. The invention also relates to a method for manufacturing the component (1) and a nuclear facility comprising the component (1).

Abstract: For determining the content and the chemical composition of particulate compounds in a liquid flow (15), the particulate compounds are collected on a filter (20) in a container (19) of a material which is permeable to microwaves. When carrying out the determination, samples of a fixed size of the liquid in the flow are supplied batchwise to the container on one side of the filter via an openable and a closable connection (16, 17) between the liquid flow and the container. At the same time, liquid from each liquid sample supplied batchwise, which has passed through the filter, is discharged from the container via an openable and a closable outlet (30, 31) on the other side of the filter.