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Nuclear fuel assembly grid with enhanced mixing blades

A technology for nuclear fuel assemblies and fuel assemblies, which is applied to reactor fuel elements, nuclear engineering, nuclear power generation, etc., can solve problems such as weakening the mixing performance of mixing blades, and achieve the effects of ensuring mechanical strength, increasing choke area, and improving mixing disturbance.

Active Publication Date: 2013-07-03
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Due to the existence of the welding window, part of the fluid flows sideways through the welding window, which weakens the mixing performance of the mixing blade to a certain extent

Method used

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  • Nuclear fuel assembly grid with enhanced mixing blades
  • Nuclear fuel assembly grid with enhanced mixing blades
  • Nuclear fuel assembly grid with enhanced mixing blades

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Embodiment Construction

[0016] A nuclear fuel assembly grid with enhanced mixing blades according to the present invention will be further described below in conjunction with the accompanying drawings and specific embodiments.

[0017] Such as Figure 3 to Figure 5 As shown, a nuclear fuel assembly grid with enhanced mixing blades according to the present invention, which forms a grid-like structure through cross-connection of several grid strips.

[0018] On the side wall of each grid strip, there are two upper and lower rigid projections 2 and a spring 1 between the two rigid projections 2 to clamp the fuel rods.

[0019] A groove 3 is opened below or above each grid strip, and adjacent grid strips are cross-connected up and down through the groove 3 to form a grid. The width of the groove 3 is between 0.2 mm and 0.8 mm, and the length is between 5 and 40 mm.

[0020] Two corresponding enhanced mixing blades 5 are fixedly connected above the crossing points of the grid strips to stir the passing ...

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Abstract

The invention provides a nuclear fuel assembly grid with enhanced mixing blades, wherein an upper rigid dimple and a lower rigid dimple and a spring between the upper rigid dimple and the lower rigid dimple are arranged on the side wall of each grid strip to clamp a fuel rod; a slot is formed below or above each grid strip, and the adjacent grid strips are connected in a vertical crossing manner through the slots; two corresponding enhanced mixing blades are arranged above a cross point of each two adjacent grid strips to mix fluid flowing by; each enhanced mixing blade is of a closed structure; a cavity is arranged on an axis wire which is within the range of 1-20 mm below the cross point of each two adjacent grid strips, and the grid strips are fixed through welding at the cavities. A closed area is formed at the cross part between each enhanced mixing blade and each strip, so that the mixing disturbance of the mixing blades on the fluid is remarkably improved. As the welding cavity is arranged below each mixing blade, the overall mechanical strength of the mixing grid is guaranteed.

Description

technical field [0001] The invention relates to fuel assembly technology, in particular to a nuclear fuel assembly grid with enhanced mixing blades. Background technique [0002] The fuel assembly is a key component of the pressurized water nuclear reactor core, which generates heat energy and transfers this heat energy to the coolant. The thermal energy of the fuel assembly is generated by the fuel rod, which is a slender rod-shaped structure, mainly composed of several cylindrical pellets covered by an outer tubular cladding. The fuel rods penetrate the fuel assembly in the axial direction, and are positioned axially and laterally by the positioning grid. Each fuel assembly is axially spaced with a number of spacer grids, and each spacer grid is composed of a plurality of thin strips intersecting, and the side walls of each grid are arranged with springs or rigid protrusions to support the fuel rods . The structure of the grid is reinforced by welding at the vertical in...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/352G21C3/322
CPCY02E30/30
Inventor 丁捷干富军周云清秦慧敏贾红轶童幸
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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