skip to main content


Title: Short communication on " In-situ TEM ion irradiation investigations on U 3Si 2 at LWR temperatures"

Here, the radiation-induced amorphization of U 3Si 2 was investigated by in-situ transmission electron microscopy using 1 MeV Kr ion irradiation. Both arc-melted and sintered U3Si2 specimens were irradiated at room temperature to confirm the similarity in their responses to radiation. The sintered specimens were then irradiated at 350 °C and 550 °C up to 7.2 × 10 15 ions/cm 2 to examine their amorphization behavior under light water reactor (LWR) conditions. U 3Si 2 remains crystalline under irradiation at LWR temperatures. Oxidation of the material was observed at high irradiation doses.
 [1] ; ORCiD logo [2] ;  [1] ;  [3] ;  [1] ;  [1]
  1. Argonne National Lab. (ANL), Lemont, IL (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Northwestern Univ., Evanston, IL (United States)
Publication Date:
Grant/Contract Number:
AC02-06CH11357; NSFDMR-1121262; NSFEEC-0647560
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 484; Journal Issue: C; Journal ID: ISSN 0022-3115
Research Org:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy, Nuclear Energy Advanced Modeling and Simulation (NEAMS); University of Chicago, Materials Research Science & Engineering Center (MRSEC); USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; accident tolerant fuel; in-situ TEM; ion irradiation; nuclear fuel; uranium silicide
OSTI Identifier:
Alternate Identifier(s):
OSTI ID: 1460120