Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors

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In the development of nuclear power reactors, the use of metals able to withstand high temperatures and induced radiation is paramount. Molecular decomposition, embrittlement and swelling at the grain level of such materials are a consequence of intense neutron bombardment. Materials such as stainless steel T91 and oxide dispersed steel (ODS) are widely used in nuclear reactors. Mechanical and thermal properties at the grain level of these materials under irradiation have not been sufficiently demonstrated, for which the understanding and modeling of such parameters may lead to better maintenance of nuclear power plants, further development of newer materials and alloys, and material failure prediction. The purpose of this research is to further investigate the conduction of stainless steels at the grain level when subjected to intense radiation and high temperatures for efficient heat exchanger design and prediction of material failure.