Westinghouse Electrical Sweden AB

Västerås, Sweden

Westinghouse Electrical Sweden AB

Västerås, Sweden
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Patent
Westinghouse Electrical Sweden AB | Date: 2017-08-02

A fuel assembly for a boiling water reactor, comprises fuel rods (2), a tie plate (3), a handle device (4), and at least two water rods (7) attached to the tie plate and to the handle device. A plurality of spacers (8a, 8b), define first passages (8) for some of the fuel rods, and second passages (8) for the water rods. Each water rod comprises a tube part (7a) attached to the tie plate, and a solid part (7b) attached to the handle device. The tube part permits a flow of coolant. The spacers comprise primary spacers (8a) and a secondary spacer (8b). The primary spacers are attached to the tube parts. The tie plate, the water rods, the primary spacers and the handle device form a support structure carrying the weight of the fuel rods. The secondary spacer is positioned at the solid part of the respective water rod.


Patent
Westinghouse Electrical Sweden AB | Date: 2017-07-19

The present invention concerns a method of making a nuclear fuel pellet for a nuclear power reactor. The method comprising the following steps: providing a nuclear fuel material in powder form, pressing the powder such that a so-called green pellet is obtained, providing a liquid that comprises an additive which is to be added to the green pellet, contacting the green pellet with the liquid such that the liquid, with the additive, penetrates into the pellet, sintering the so treated green pellet, wherein the additive is such that larger grains in the nuclear fuel material are obtained with the additive.


Patent
Westinghouse Electrical Sweden AB | Date: 2017-07-19

The present invention concerns a method of making a nuclear fuel pellet for a nuclear power reactor. The method comprises the following steps: providing a nuclear fuel material in powder form, providing an additive, forming a so-called green pellet, wherein said additive is added either to said nuclear fuel mate- rial in powder form or to the green pellet, sintering the green pellet, wherein said additive is such that it causes larger grains in the nuclear fuel pellet, and wherein said additive is made of or includes a substance which causes the larger grains and which substantially leaves at least an outer portion of the pellet before and/or during the sintering step.


Patent
Westinghouse Electrical Sweden AB | Date: 2017-06-21

A fuel assembly (1) for a boiling water reactor comprising fuel rods (3), two or three water rods (30), a tie plate (4), spacers (6), a handle (10), and a joint arrangement (11, 12, 13, 20-25, 31, 32, 33) is provided. The joint arrangement is configured to transfer a vertical lifting force from the handle to the water rods. The joint arrangement comprises a balancing element (20) arranged between the water rods (30) and the handle (10). The joint arrangement comprises a first joint (13) arranged between the balancing element (20) and the handle (10) and a set of second joints (33) arranged between a respective one of said water rods (30) and said balancing element (20). The first joint (13) and the set of second joints (33) are configured to allow a rotational movement of said balancing element (20) in relation to said handle (10) as well as in relation to said water rods (30) in order to balance lifting forces in the water rods. The first joint (13) and each one of said second joints (33) comprise a pair of spherically rounded joint surfaces (11, 23; 25, 32).


Grant
Agency: European Commission | Branch: H2020 | Program: RIA | Phase: NFRP-16-2015 | Award Amount: 2.05M | Year: 2015

The overall aim of the project is to create greater security of energy supply and contribute to the security of supply of nuclear fuel for Russian designed pressurized water reactors (VVER) operating in the EU by diversification of fuel sources in the short / medium term and in full compliance with nuclear safety standards. By that, the project addresses the topic NFRP 16 2015. The scientific objectives of the proposed project include increased knowledge concerning the behaviour of the VVER-440 fuel during operation. State-of-the-art methods will be verified against an extensive database, including operating experience from several VVER-440 reactors as well as a number of other reactor designs and a wide range of operating conditions. The ability to accurately predict the fuel behaviour will be improved and thereby also the safety margins. New knowledge as well as identification of needs of technology development and improvements will be created in the fields of technologies for mechanical design, thermo-mechanical fuel rod design, and safety analysis for VVER fuel. In addition to the technological advances, the project will identify the variation in licensing requirements between the authorities in the different countries. Through such identification, it will become clear that standardization would be beneficial and will foster a dialogue between the authorities/regulatory bodies. The new knowledge will be exploited through innovation processes but will also be used for further research and recommendation to policy makers as well as for creating impact among the target groups of the project. Results will be presented to the members of the VVER community, i.e. the utilities, universities and other organizations with close links to the nuclear energy industry. Articles and papers presenting the work and the results of the project will be targeted for nuclear industry, magazines and conferences.


Grant
Agency: GTR | Branch: EPSRC | Program: | Phase: Research Grant | Award Amount: 4.98M | Year: 2013

We intend to make the UK the world leaders in the understanding, performance and application of hexagonal material systems used by the aero, energy and defence sectors. We wish to develop step-change technology by bringing to bear the extraordinary range of experimental, characterization and modelling techniques in which the UK holds many leaders but which have yet to be brought together to take full advantage of the synergy and multiplication possible. This simply remains un-achievable without clear UK unification of research effort. Hexagonal structural materials that are of industrial significance are all of close packed crystal structure (largely titanium, zirconium and magnesium alloys) and are strategic and profoundly important to the UK economy and find wide application. The implications of research success are profound in developing significant improvement in materials, material structure and processing conditions in optimizing manufacture, in optimizing component design with superior property-behaviour relationships, in improving operational efficiencies and in reducing production and running costs, thereby contributing to fuel efficiencies and very importantly, the UKs competitive advantage. Our ambition is to bring together the UKs experts in academia, supply chain and end-users, coupled with techniques to be brought to bear in four key themes in hexagonal metals which are fundamental mechanisms, micromechanics, performance in aero applications and performance in nuclear applications.


Patent
Westinghouse Electrical Sweden AB | Date: 2016-03-30

The present invention concerns a fuel assembly (4) for a nuclear power boiling water reactor, comprising:a fuel channel (6) defining a central fuel channel axis (8),fuel rods (10), each having a central fuel rod axis (12),at least 3 water channels (14) for non-boiling water, each water channel having a central water channel axis (16) and each water channel having a larger cross-sectional area than the cross-sectional area of (the average) fuel rod (10). The fuel rods (10) comprise a first group of full length fuel rods and a second group of shorter fuel rods. The fuel assembly (4) comprises at least 5 fuel rods which belong to said second group and which are positioned such that the central fuel rod axis (12) of each of these at least 5 fuel rods is closer to the central fuel channel axis (8) than any of the water channel axes (16) of the water channels (14).


Patent
Westinghouse Electrical Sweden AB | Date: 2016-08-24

The present invention concerns a fuel assembly (4) for a nuclear power boiling water reactor, comprising:a fuel channel (6) defining a central fuel channel axis (8),fuel rods (10), each having a central fuel rod axis (12),at least 3 water channels (14) for non-boiling water, each water channel having a central water channel axis (16) and each water channel having a larger cross-sectional area than the cross-sectional area of (the average) fuel rod (10). The fuel rods (10) comprise a first group of full length fuel rods and a second group of shorter fuel rods. The fuel assembly (4) comprises 3 or 4 fuel rods which belong to said second group and which are positioned such that the central fuel rod axis (12) of each of these 3 or 4 fuel rods is closer to the central fuel channel axis (8) than any of the water channel axes (16) of the water channels (14).


Patent
Westinghouse Electrical Sweden AB | Date: 2016-03-30

A fuel assembly for a boiling water reactor, comprises fuel rods (2), a tie plate (3), a handle device (4), and at least two water rods (7) attached to the tie plate and to the handle device. A plurality of spacers (8a, 8b), define first passages (8) for some of the fuel rods, and second passages (8) for the water rods. Each water rod comprises a tube part (7a) attached to the tie plate, and a solid part (7b) attached to the handle device. The tube part permits a flow of coolant. The spacers comprise primary spacers (8a) and a secondary spacer (8b). The primary spacers are attached to the tube parts. The tie plate, the water rods, the primary spacers and the handle device form a support structure carrying the weight of the fuel rods. The secondary spacer is positioned at the solid part of the respective water rod.


Patent
Westinghouse Electrical Sweden AB | Date: 2016-09-28

A method and a system (10) is provided for controlling and monitoring the gas pressure in a nuclear fuel rod (1) during filling of the fuel rod (1) with a gas, and subsequent sealing of the fuel rod (1). The system comprises a control unit (12) and a length measuring system (14), which control unit (12) is communicatively connected to the length measuring system (14). The length measuring system (14) is configured to monitor the length of the fuel rod (1), and the control unit (12) is configured to receive measurements from the length measuring system (14) and to determine the gas pressure inside the fuel rod (1) on the basis of variations of the length of the fuel rod (12). The method comprises positioning (101) an open first end (2) of the fuel rod (1) inside a pressure chamber (11), allowing gas to enter the fuel rod 1; pressurizing (103) the gas in the pressure chamber (11) at a first pressure level; closing (105) the fuel rod (1); and sealing (113) the fuel rod (1). Especially, the method comprises monitoring (107) the variation of the length of the fuel rod (1) between the step of closing (105) and the step of sealing (113), and using the length variation as a measure of the gas pressure variation inside the fuel rod (1).

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