Short-term mechanical properties and microstructure of ferritic/martensitic steel EP-823 were investigated following irradiation as fuel pin cladding in BOR-60 to 63 dpa at 365-680?. Ring specimens cut from the cladding were used for ring-pull tests and electron microscopy. Up to ~460? irradiated EP-823 was found to fracture in a brittle mode at low strength levels. With increasing temperature the total elongation increased to 27.5 %. The irradiated strength in the temperature range 460-670? was found to be close to its unirradiated value. Void formation in EP-823 was suppressed with isolated voids observed only at 375? to 50.5 dpa. After irradiation at 375 and 500? finely dispersed ?6? precipitates formed. At 500 and 630? equiaxed -phase formed in ferritic grains and plate-like ?2? precipitates, which were present in the starting microstructure, dissolved completely.
Revised: November 10, 2005 |
Published: August 1, 2004
Citation
Porollo S.I., A.M. Dvoriashin, Y.V. Konobeev, and F.A. Garner. 2004.Microstructure and Mechanical Properties of Ferritic/Martensitic Steel EP-823 after Neutron Irradiation to High Doses in BOR-60. In 11th International Conference on Fusion Reactor Materials in JOURNAL OF NUCLEAR MATERIALS, edited by Kohyama, A., 329-33 PT. A AND B, 314-318. Amsterdam:Elsevier Science.PNNL-SA-40770.