Speaker
Description
The harsh neutron irradiation environments in the core region of fast breeder reactors (FBRs) pose a unique challenge for cladding materials. Microchemistry and Microstructural changes resulting from displacement damage and creep rupture are anticipated for structural materials after extended neutron irradiation. Various irradiation effects on the service performance of cladding materials need to be understood. Because of their excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels (FMS) with 9-12%Cr are considered the candidate cladding materials for the new generation FBRs. T91 with the nominal chemistry of 9%Cr-1%Mo-0.2%V-0.08%Nb-0.05%N-0.1%C has been used extensively for fossil power plants because of its excellent creep resistance up to approximately 600℃. As a candidate material for cladding, the fundamental of irradiation damage and its effects on T91 are reviewed in this paper. The objective is to provide a insight of neutron irradiation damage, microstructural and microchemical changes, mechanical properties and facture behavior of T91. The chemistry modification of T91 are also discussed for the improvement of fracture toughness before and after irradiation. This review also provide some suggestions of additional investigations for the application of T91 in FBRs.
| Speaker's title | Mr |
|---|---|
| Country/Int. organization | China |
| Affiliation/Organization | China Institute of Atomic Energy |
| Speaker's email address | lijunhong@ciae.ac.cn |
