Abstract

Owing to its exceptional properties at high temperature, graphite is used in several applications such as structural material and fuel block in high temperature nuclear reactors. Air ingress is one of the serious safety concerns in these reactors. Oxidation of graphite leading to increased porosity affects its mechanical strength and may lead to core collapse resulting in a severe accident. During such a scenario, generation of graphite particles could be the main hazard. Once generated, these particles often in fine and ultrafine sizes, may carry radioactivity to large distances and/or for long times. These particles owing to their higher surface to volume ratio possess an additional inhalation hazard. Ultrafine particles have the potential to enter into respiratory tract and cause damage to body organs. Coating of graphite components is preferred to reduce the oxidation induced damages at high temperatures. In the present work, effect of alumina (Al2O3) coating on the emission characteristics of particles from graphite under high temperature conditions has been investigated. Bare and Al2O3 coated graphite specimens were heated within a closed chamber at varying temperatures during these experiments. Temporal evolution of concentrations of gases (CO and CO2) and particles were measured. The results reveal that Al2O3 coating on the graphite delayed the oxidation behavior and the structure of graphite remained largely intact at high temperatures. A significant reduction in aerosol formation and CO emission was also noticed for the coated specimens.

Highlights

  • Owing to its exceptional properties at high temperature, graphite is used in several applications such as structural material and fuel block in high temperature nuclear reactors

  • Graphite is used as a structural material in high temperature reactors (HTRs) owing to its excellent properties at high ­temperatures[1,2]

  • Loss of mechanical strength of fuel block and core collapse leading to severe accident is a part of ‘Probabilistic Safety Assessment’ for HTRs

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Summary

Introduction

Owing to its exceptional properties at high temperature, graphite is used in several applications such as structural material and fuel block in high temperature nuclear reactors. Oxidation of graphite leading to increased porosity affects its mechanical strength and may lead to core collapse resulting in a severe accident During such a scenario, generation of graphite particles could be the main hazard. Ingress of foreign media, i.e., air and water into the primary circuit during normal and off-normal conditions has been highlighted as a safety issue for ­HTRs8 Such ingress affects surface characteristics and properties of graphite components, at high temperatures. On the graphite surface has been explored in order to cut diffusion channel for oxygen to attack the s­ ubstrate[33,34,35,36,37,38,39,40] Out of these coating options, ­MoSi2 and ­B4C coatings are expected to severely affect the neutronic behavior of the reactor. The effect of neutron irradiation on thermal diffusivity could be detrimental for large volume fraction of c­ oating[45]

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