Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 10(1); 2012
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2012;10(1):21-26. Published online: Mar, 30, 2012

Evaluation of Microstructural and Mechanical Property of Medium-sized HT9 Cladding Forged Material for Sodium-cooled Fast Reactor

  • Jun-Hwan Kim ; Kang-Soo Lee ; Sung-Ho Kim ; Chan-Bock Lee
Abstract

Microstructural and mechanical property were evaluated at the medium-sized HT9 (12Cr-1MoWV) forged steel which was considered as primary candidate for the fuel cladding in sodium-cooled fast reactor (SFR). Material was forged at 1170 C after the induction melting to make round bar as 160mm diameter, 7000mm length then the radial distribution of microstructure as well as microhardness was evaluated. The results showed that overall microstructure exhibited as ferrite-martensite structure, where small amount (2 3%) of delta ferrite was formed throughout the specimen and maximum 15% of transformed ferrite was formed at the center, where it gradually decreased toward the radial direction. Sensitivity analysis of the cooling curve and Time-Temperature-Transformation (TTT) diagram revealed that formation of transformed ferrite could be avoided when the diameter was decreased down to 120mm.

Keywords

Sodium-cooled Fast Reactor (SFR),Fuel,Cladding,HT9,Metallurgy