March 1, 2007
Book Chapter

MECHANICAL PROPERTIES AND MICROSTRUCTURE OF THREE RUSSIAN Mechanical Properties And Microstructure Of Three Russian Ferritic/Martensitic Steels Irradiated In BN-350 Reactor To 50 dpa at 490C

Abstract

Ferritic/martensitic (F/M) steels are being considered for application in fusion reactors, intense neutron sources, and accelerator-driven systems. While EP-450 is traditionally used with sodium coolants in Russia, EP-823 and EI-852 steels with higher silicon levels have been developed for reactor facilities using lead-bismuth coolant. To determine the influence of silicon additions on short-term mechanical properties and microstructure, ring specimens cut from cladding tubes of these three steels were irradiated in sodium at 490?? in the BN-350 reactor to 50 dpa. Post-irradiation tensile testing and microstructural examination show that EI-852 steel (1.9 wt% Si) undergoes severe irradiation embrittlement. Microstructural investigation showed that the formation of near-continuous ?-phase precipitates on grain boundaries is the main cause of the embrittlement.

Revised: October 20, 2009 | Published: March 1, 2007

Citation

Dvoriashin A.M., S.I. Porollo, Y.V. Konobeev, N.I. Budylkin, E.G. Minonova, A.G. Loltukhovsky, and M.V. Leonteva-Smirnova, et al. 2007. MECHANICAL PROPERTIES AND MICROSTRUCTURE OF THREE RUSSIAN Mechanical Properties And Microstructure Of Three Russian Ferritic/Martensitic Steels Irradiated In BN-350 Reactor To 50 dpa at 490C. In Fusion Materials Semiannual Report for the period ending December 31, 2006, DOE/ER-313/41. 98-104. Oak Ridge, Tennessee:Oak Ridge National Laboratory. PNNL-SA-53768.