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Title: Deformation mechanisms in a proton-irradiated austenitic stainless steel

Book ·
OSTI ID:100200
; ;  [1];  [2]
  1. Univ. of Michigan, Ann Arbor, MI (United States)
  2. Pacific Northwest Lab., Richland, WA (United States)

Samples of austenitic 304 L stainless steal have been irradiated with 3.4 MeV protons to a total dose of 1 dpa. The microstructure of the irradiated stainless steel has been quantified by transmission electron microscopy and shown to be similar to that found in neutron-irradiated core components. Constant extension rate tensile tests have been performed at strain rates of 3 {times} 10{sup {minus}7} s{sup {minus}1} and 3 {times} 10{sup {minus}8} s{sup {minus}1} to strains of up to 27% at 23 C and 288 C. The resulting microstructures were characterized using electron and optical microscopy. Deformation of the unirradiated material is similar to that reported by others in previous work on austenitic steels, consisting of dislocation source activation and formation of dense dislocation networks with increasing strain. In the irradiated samples tested at 288 C, deformation consists of dislocation source activation at grain boundaries punching dislocations through the grain interior to the opposing grain boundaries. The dislocations create channels that are free of radiation-produced defects and on which dislocation motion is concentrated. Dislocations in the channels pile-up at the boundaries, creating regions of highly localized stress concentration at the grain boundary. The mechanism by which this stress relieved is still unknown. Deformation at 23 C consists of the nucleation and propagation of microtwins across the width of the grains.

DOE Contract Number:
FG06-89ER75522; FG07-88ER12825; AC06-76RL01830
OSTI ID:
100200
Report Number(s):
CONF-941144-; ISBN 1-55899-275-8; TRN: IM9539%%229
Resource Relation:
Conference: Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 28 Nov - 9 Dec 1994; Other Information: PBD: 1995; Related Information: Is Part Of Microstructure of irradiated materials; Robertson, I.M. [ed.] [Univ. of Illinois, Urbana, IL (United States). Dept. of Materials Science and Engineering]; Rehn, L.E. [ed.] [Argonne National Lab., IL (United States). Materials Science Div.]; Zinkle, S.J. [ed.] [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.]; Phythian, W.J. [ed.] [AEA Technology-Harwell, Oxon (United Kingdom)]; PB: 588 p.; Materials Research Society symposium proceedings, Volume 373
Country of Publication:
United States
Language:
English