Study on the ageing behavior of carbon reactor internal materials under double end fracture accident of a heat transfer tube
The carbon reactor internals of the high-temperature gas-cooled reactor are made of graphite materials containing B4 C.When a double ends fracture accident occurs in the heat transfer tube of a steam generator,vapor of about 600 kg will leak into the primary circuit,causing oxidation of the carbon reactor internals,resulting in performance degradation and affecting the long-term safe and reli-able operation of the high temperature gas-cooled reactor.This article takes the carbon reactor internal materials as the research object,and studies the corrosion behavior and mechanical performance behavior under the simulated heat transfer tube double ends fracture ac-cident conditions.It was found that as time increases,the material density decreases and both the roughness and the degree of corrosion increases.The tensile strength,bending strength,compressive strength,and fracture toughness of materials all decrease with time.Analy-sis suggests that corrosion of surface pores in carbon reactor internal materials may promote crack initiation,while corrosion of internal pores may promote crack propagation.
High temperature gas-cooled reactorscarbon reactor internalsoxidationmechanical properties
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