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Arrangement rod bundle positioning structure for reactor thermal-hydraulic experiment

A thermal-hydraulic and positioning structure technology, applied in reactors, reactor fuel elements, nuclear engineering, etc., can solve the problems of high cost and difficult positioning, and achieve the effect of low cost, reasonable overall structure and guaranteed reliability

Active Publication Date: 2016-08-24
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
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Problems solved by technology

[0004] The purpose of the present invention is to provide a positioning structure for arrayed rod bundles applied to a thermal hydraulic experiment of a reactor, to solve the problems of difficult positioning and high cost of the current rod bundle fuel assemblies in the test, and to simplify the structure while maintaining the experimental performance the goal of

Method used

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  • Arrangement rod bundle positioning structure for reactor thermal-hydraulic experiment
  • Arrangement rod bundle positioning structure for reactor thermal-hydraulic experiment

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Embodiment

[0021] Such as Figures 1 to 2 The schematic diagram shown is an arrangement rod bundle positioning structure for reactor thermal hydraulic experiments, including four jacket pieces 1, a total of 4 pieces, jacket piece 1 includes a pair of long pieces and a pair of short pieces, and the short pieces are vertically welded on a pair of Between the long pieces; a rectangular socket is set in the middle of the jacket piece 1, and its height H should take into account the support strength and the influence on the flow, and should not be too small or too large, preferably between 20~40mm; To reduce the obstruction to the flow field, the sheath piece 1 is welded to form a square cavity structure, an inner fixing ring 2 is arranged on the axis of the sheath piece 1, and four heating rod bundles 3 are arranged on the inner side of the sheath piece 1, and the heating rod bundle 3. The two adjacent sheath pieces 1 are fixed tangentially to the inner fixing ring 5; the outside of the shea...

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Abstract

The invention discloses an arrangement rod bundle positioning structure for a reactor thermal-hydraulic experiment. The arrangement rod bundle positioning structure comprises four outer sleeve pieces. The outer sleeve pieces are welded to form a square cavity structure, inner fixing rings are arranged at the axes of the outer sleeve pieces, the inner sides of the outer sleeve pieces are provided with four heating rod bundles, the heating rod bundles are tangent to and fixed to the inner fixing rings through two adjacent outer sleeve pieces, and the outer sides of the outer sleeve pieces are fixed to the side wall of a runner through equidistant pieces. The arrangement rod bundle positioning structure can rotate, so that reasonable disturbance is caused through heating, local burnout is avoided, and the whole arrangement rod bundle positioning structure is reasonable in structure, suitable for the thermal-hydraulic experiment of a rod bundle fuel assembly and high in substitutability. Besides, the arrangement rod bundle positioning structure is very low in cost; compared with a framework, cost of the arrangement rod bundle positioning structure is only 20%, and the positioning reliability is guaranteed.

Description

technical field [0001] The invention relates to the field of thermal-hydraulic experiments of reactors, in particular to a positioning structure for arranging rod bundles in thermal-hydraulic experiments of reactors. Background technique [0002] In water-cooled nuclear power reactors, zirconium alloys are used as cladding materials for nuclear fuel elements. When the reactor is running, the fuel of the element core will release radioactive fission gas, and the action of the fission product iodine (I) and the stress will lead to stress corrosion cracking (SCC) of the zirconium alloy cladding material, which is called iodine-induced stress corrosion cracking ( I-SCC), in the case of I-SCC, the zirconium alloy cladding will produce cracks to reduce its plasticity, which will cause brittle fracture of the zirconium cladding, leading to the leakage of radioactive substances, which may cause major safety hazards. [0003] The rod bundle fuel assembly has been widely used in nucl...

Claims

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Application Information

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IPC IPC(8): G21C3/336G21C3/08
CPCG21C3/08G21C3/336Y02E30/30
Inventor 周磊夹川昝元锋闫晓黄彦平陈炳德
Owner NUCLEAR POWER INSTITUTE OF CHINA
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