Abstract:
The invention relates to a nuclear fuel element for pressurized-water reactors comprising a fuel cladding of a zirconium alloy composed of two parts. The inner part constitutes a supporting part of a conventional zirconium and the outer part a corrosion-resistant layer of zirconium with 0.65 - 0.95 % Sn and 0.4 - 0.5 % Fe. The difference in Sn content between the inner and outer parts must not exceed 0.7 %.
Abstract:
A zirconium alloy for nuclear fuel components such as cladding tubes, spacers, boxes, etc., with improved properties with respect to the absorption of hydrogen released during the corrosion, in combination with good strength and creep properties. The alloy contains zirconium and tin, iron, nickel, chromium, and silicon with a total content of at least 0.54 per cent by weight and at most 2.15 per cent by weight, of which the content of tin is at least 0.03 %, the content of iron at least 0.07 %, the content of nickel at least 0.03 %, the content of chromium at least 0.05 %, and the content of silicon at least 0.005 % and 0.15-0.30 % vanadium and 0.015-0.30 % niobium.
Abstract:
A fuel assembly (1) comprising a plurality of elongated elements (3) filled with nuclear fuel and at least one component (5, 6, 7) for retaining the elongated elements (3), wherein the retaining component (5, 6, 7) is completely or partly made of a ceramic material.
Abstract:
A component (1) designed for use in a light water reactor and at least partly comprised by a metal and/or a metal alloy presents a coatings (4, 7) at its outer surface (3) and its inner surface (5). The coating (4 and 7 respectively) has as its task to protect the surface (3 and 5 respectively) against oxidation, corrosion, wear and hydration. The coating (4 and 7 respectively) suitably comprises at least one of zirconium dioxide (ZrO2) and zirconium nitride (ZrN).
Abstract:
The present invention relates to a nuclear fuel element for a pressurized-water reactor, PWR. The fuel element comprises cladding tubes or cladding tubes and guide tubes, whose composition and manufacture are so adapted that the cladding or the cladding and the guide tubes during reactor operation show a good resistance to general corrosion and a low hydrogen contents. This can be achieved by allowing the cladding or the cladding and the guide tubes, when being manufactured, to undergo heat treatments which are of such a nature that the cumulative annealing parameter SIGMA A = SIGMA ti exp (-Q/RTi) is at most 1.25 x 10 , at Q/R = 31726 K.
Abstract translation:本发明涉及一种用于加压水反应堆的核燃料元件,PWR。 燃料元件包括包层管或包覆管和导管,其组成和制造适于在反应器操作期间使包层或包层和导管显示出良好的抗一般腐蚀性和低氢含量。 这可以通过允许包层或包层和导管在制造时进行热处理来实现,这些热处理的性质使得累积退火参数SIGMA A = SIGMA ti exp(-Q / RTi)至多为 1.25×10 14,在Q / R = 31726K。
Abstract:
A fuel assembly (1) for a boiling water nuclear reactor comprising a plurality of vertical fuel rods (3) which are arranged in spaced relationship between a bottom tie plate (6) and a top tie plate (5). The bottom tie plate (6) is provided with through-holes (6a) for the passage of a coolant (F). Further, the fuel assembly (1) comprises a bottom support (10) which is formed substantially from a downstream and an upstream flat surface (12, 13) and four side surfaces (14). The flat surfaces (12, 13) and the side surfaces (14) form a parallelepiped which surrounds a cavity. A filtering member is arranged in the upstream flat surface (13) and comprises a plurality of through-holes (11).
Abstract:
The present invention relates to a fuel assembly for a pressurized-water nuclear reactor comprising a plurality of fuel units (3) stacked on top of each other, wherein each fuel unit (3) comprises fuel rods (4) extending between a bottom nozzle (5) and a top nozzle (6). A coolant is adapted, during operation, to flow upwards through the fuel assembly. The fuel assembly has a substantially square cross section and the fuel rods (4) are arranged in an orthogonal lattice. Further, support lugs (8) are adapted to support the fuel rods (4), in four directions, in the upper or lower end of a fuel unit (3) to ensure that a certain distance is maintained between the fuel rods (4).
Abstract:
A fuel assembly for a boiling water reactor comprising full-length fuel rods (3a, 3c) with a first length extending over the height of the entire fuel assembly, and part-length fuel rods (3b) with a second length extending only in the lower part (10) of the fuel assembly, the fuel rods which have positions immediately adjacent to the part-length fuel rods being adapted so as to be bent inwards, in their upper part, towards the open region (15) which is formed above the part-length fuel rods. At least half of the fuel rods in the fuel assembly are straight.
Abstract:
A device for weighing a material that is supplied to a container (1) during processing thereof presents a processing member (3) for processing the material, which processing member is driven by an outer driving member (4, 7) and arranged in the container (1). The driving member (4, 7) is connected to the processing member (3) by a connection (8) which, at least during operation, transmits axial forces. The processing member (3), in co-operation with the supplied material, gives rise to dynamic forces acting between the included components. The device presents a first weighing member (26) which is mechanically connected to the container (1) and arranged to determine a weight associated to the container. Furthermore, the device comprises a second weighing member (27) which is mechanically connected to the driving member (4, 7) and arranged to determine the weight associated to the driving member. With consideration taken to the weights determined by the first and second weighing members (26, 27), the weight of the supplied material is calculated in an evaluating member.
Abstract:
A zirconium alloy including tin (Sn) in a range of greater than 0.005 wt.% to less than 1.0 wt.%, preferably with a lower limit greater than 0.1 wt.% to an upper limit of less than 0.7 wt.%, and most preferably with a lower limit of greater than 0.3 wt.% to an upper limit of less than 0.5 wt.%; iron (Fe) in a range of greater than 0.05 wt.% to less than about 1.0 wt.%, preferably with a lower limit of greater than 0.2 wt.% to an upper limit of greater than 0.5 wt.%, and most preferably with a lower limit of greater than 0.3 wt.% to an upper limit of less than 0.4 wt.%; chromium (Cr) in a range of greater than 0.02 wt.% to less than 1.0 wt.%, preferably with a lower limit of greater than 0.05 wt.% to an upper limit of less than 0.5 wt.%, and most preferably with a lower limit of greater than 0.1 wt.% to an upper limit of less than 0.2 wt.%; silicon in a range of greater than 50 to less than 300 parts per million (ppm), preferably in a range of greater than 70 to about 200 ppm, and most preferably in a range of greater than 90 to about 150 ppm; tungsten (W) in a range of greater than 0.01 wt.% to less than 1.0 wt.%, preferably with a lower limit of greater than 0.1 wt.% to an upper limit of less than 0.7 wt.%, and most preferably with a lower limit of greater than 0.2 wt.% to an upper limit of about less than 0.5 wt.%; nickel (Ni) in a range of greater than 0.007 wt.% and less than about 0.3 wt.%, preferably with a lower limit of greater than 0.05 wt.% to an upper limit of less than about 0.2 wt.%, and most preferably with a lower limit of greater than 0.08 wt.% to an upper limit of less than about 0.1 wt.%, with the balance zirconium.