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Title: Intergranular fracture during high temperature, slow-strain-rate tensile testing of modified HP9-4-20 high strength steel.

Abstract

Abstract not provided.

Authors:
; ; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1320974
Report Number(s):
SAND2007-3996C
463523
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the 18th AeroMat Conference and Exposition held June 25-28, 2007 in Baltimore, MD.
Country of Publication:
United States
Language:
English

Citation Formats

Susan, Donald Francis, Duran, Peter S., Robino, Charles V, and Paules, John R. Intergranular fracture during high temperature, slow-strain-rate tensile testing of modified HP9-4-20 high strength steel.. United States: N. p., 2007. Web.
Susan, Donald Francis, Duran, Peter S., Robino, Charles V, & Paules, John R. Intergranular fracture during high temperature, slow-strain-rate tensile testing of modified HP9-4-20 high strength steel.. United States.
Susan, Donald Francis, Duran, Peter S., Robino, Charles V, and Paules, John R. Fri . "Intergranular fracture during high temperature, slow-strain-rate tensile testing of modified HP9-4-20 high strength steel.". United States. doi:. https://www.osti.gov/servlets/purl/1320974.
@article{osti_1320974,
title = {Intergranular fracture during high temperature, slow-strain-rate tensile testing of modified HP9-4-20 high strength steel.},
author = {Susan, Donald Francis and Duran, Peter S. and Robino, Charles V and Paules, John R.},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 2007},
month = {Fri Jun 01 00:00:00 EDT 2007}
}

Conference:
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  • Slow strain rate testing has been undertaken to determine the effects of individual chemical species on the fracture process of high-strength 4340 steel. Test environments included potassium chloride, ammonium nitrate, and ammonium chloride at concentrations from 0.001 to 1.0 mole por liter at ambient temperature. Tests were performed at cathodic and anodic controlled potentials, as well as at the open-circuit potential, to delineate the stress corrosion cracking range.
  • Slow strain rate testing has been undertaken to determine the effects of individual chemical species on the fracture process of high-strength 4340 steel. Test environments included potassium chloride, ammonium nitrate, and ammonium chloride at concentrations from 0.001 to 1.0 mole por liter at ambient temperature. Tests were performed at cathodic and anodic controlled potentials, as well as at the open-circuit potential, to delineate the stress corrosion cracking range.
  • Tapered cylindrical specimens have been used to evaluate the crack initiation strain for both annealed and sensitized 316 stainless steel in 5 ppm chloride containing water at temperatures from 150{degrees}C to 300{degrees}C. Parallel gauge length specimens were used to determine the potential ranges for cracking of annealed and of sensitized material and reference data for each temperature was obtained by testing at very negative applied potentials. The latter data were used in conjunction with the tapered specimen results to evaluate the minimum strain require to initiate cracks.
  • Tensile tests were conducted on 50 wt% Mo-50 wt% Re alloys, in fully-recrystallized and recovery heat-treated conditions respectively, at a very low strain rate of 10 -6 s -1 and room temperature in air. It was found that both these alloys exhibited predominantly cleavage fracture with significant intergranular secondary cracking, compared to the predominantly ductile fracture found in the alloys at a higher strain rate. Cracks were often initiated at grain boundary triple junctions at the low strain rate. Electron back scatter diffraction (EBSD) measurements revealed significantly high misorientation gradients at grain boundaries, especially in the vicinity of some grainmore » boundary triple junctions in the deformed alloys. Transmission electron microscopic (TEM) results verified the existence of significant misorientation taking place at grain boundaries in these alloys. Furthermore, wtress-assisted dynamic embrittlement, possibly due to trace interstitials, was the possible cause for the occurrence of brittle fracture in the 50Mo-50Re alloys at the low strain rate.« less
  • The susceptibility of neutron irradiated type 316 stainless to stress corrosion cracking in oxygenated pure water was investigated by Slow Strain Rate Technique (SSRT). The specimens had been irradiated to 8 dpa in the Oak Ridge Research Reactor (ORR) under fusion spectrally tailored condition to simulate radiation environment expected in the near-term water-cooled fusion reactor at temperatures of 60, 200, 330 and 400{degrees}C. SSRT tests were conducted at the same temperatures with irradiation for specimens irradiated at 60 and 200{degrees}C and at 300{degrees}C for specimens irradiated at 330 and 400{degrees}C. Intergranular cracks was observed on the specimens irradiated at highermore » two temperatures, while the specimens irradiated at lower two techniques showed completely ductile fracture. Crack initiation by transgranular type fracture was observed. On fractured grain facets apparent slip steps formed. Results of the SSRT were compared with those from specimens irradiated under LWR conditions and discussed.« less