Rod bundle test piece for simulating supercritical water-cooled reactor fuel element

Abstract

The invention discloses a rod bundle test piece for simulating a supercritical water-cooled reactor fuel element. The rod bundle test piece comprises a sealings insulation piece, a ceramic lining pipe and a heating pipe, wherein the heating pipe is electrified to be heated to simulate fission heat of the fuel element, so that the relevant thermotechnical-hydraulic characteristic research is carried out; the sealing insulation piece consists of a top high-pressure sealing flange, a sealing insulation pad, a middle stainless steel outer pipe and a bottom high-pressure sealing flange; the stainless steel pipe is welded with the flanges; the ceramic lining pipe is circular in outer part and square in inner part; four fillets are formed in an internal square structure; the middle part of the heating pipe consists of four stainless steel pipes; a stainless steel electrode and a copper electrode are respectively arranged on the top and at the bottom of the heating pipe and are communicated with an alternating current transformer to heat the heating pipe through alternating current; the heating pipe is inserted into the ceramic lining pipe; a clearance between the heating pipe and the ceramic lining pipe is a flowing channel; fluid flows in the channel to bring away heat of the heating pipe; the sealing insulation piece is arranged on the outer layer of the ceramic layer and serves as a pressure boundary, so that sealing and electric insulation effects under conditions of high temperature and high pressure are achieved.

Description

technical field [0001] The invention relates to the field of reactor thermal hydraulics, in particular to a rod bundle test piece for simulating supercritical water-cooled reactor fuel elements. Background technique [0002] The supercritical water-cooled reactor is one of the six fourth-generation new nuclear reactors selected by the Fourth Generation Nuclear Energy System International Forum. It has the advantages of high thermal efficiency, good safety, simple system structure and high fuel utilization rate. It has a very bright future development prospect. One of the heap types. In terms of reactor thermal hydraulics, the supercritical water-cooled reactor core structure is extremely complex, the core flow path is narrow, the fuel rods withstand megawatt-level high heat flux and strong thermonuclear coupling, making the supercritical water-cooled reactor core thermal-hydraulic characteristics Experimental research is extremely difficult. The objects of traditional expe...

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Problems solved by technology

Due to the above reasons, it is extremely difficult to study the flow characteristics of the fluid in the typical channel of the core under the condition of high temperature and high pressure.

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