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Title: Flowforming of Austenitic Stainless 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:
1372025
Report Number(s):
SAND2016-6683C
644993
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the International Metallographic Contest (IMC) held July 24, 2016 in Columbus, OH.
Country of Publication:
United States
Language:
English

Citation Formats

Susan, Donald F., Kilgo, Alice C., and Williams, Shelley. Flowforming of Austenitic Stainless Steel.. United States: N. p., 2016. Web.
Susan, Donald F., Kilgo, Alice C., & Williams, Shelley. Flowforming of Austenitic Stainless Steel.. United States.
Susan, Donald F., Kilgo, Alice C., and Williams, Shelley. 2016. "Flowforming of Austenitic Stainless Steel.". United States. doi:. https://www.osti.gov/servlets/purl/1372025.
@article{osti_1372025,
title = {Flowforming of Austenitic Stainless Steel.},
author = {Susan, Donald F. and Kilgo, Alice C. and Williams, Shelley},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2016,
month = 7
}

Conference:
Other availability
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  • There is now clear evidence that intergranular stress corrosion cracking (SCC) and hydrogen embrittlement (HE) of engineering materials depend on grain boundary composition. Two examples are used to illustrate this interrelationship: (1) SCC of austenitic stainless steel in high-temperature water and (2) HE of NiCrMoV rotor steels in acidic solutions. Grain boundary compositions are characterized by analytical electron microscopy and scanning Auger electron spectroscopy. Environmental cracking susceptibility is indicated by slow-strain-rate tests in appropriate aqueous environments. Direct correlations are documented between measured grain boundary compositions and environmental cracking. The ability to establish these types of correlations enables diagnosis of embrittlementmore » susceptibility and helps identify methods to control or eliminate embrittlement by bulk chemistry or processing modifications. 7 figs., 3 tabs.« less
  • This paper describes the current program to develop a high strength ferritic-martensitic steel. The alloy contains Fe-9% Cr-1% Mo with small additions of V and Nb and is known as modified 9 Cr-1 Mo. Its elevated-temperature properties and design allowable stresses match those of type 304 stainless steel for temperatures up to 600/sup 0/C and exceed other ferritic steels by factors of 2 to 3. The improved strength of this alloy will permit its use in place of stainless steels for many applications.
  • The USSR steel EP-838 is a high-manganese (13.5%), low-nickel (4.2%) steel that also has lower chromium and molybdenum than type 316 stainless steel. Tensile specimens of 20%-cold-worked EP-838 and type 316 stainless steel were irradiated in the High Flux Isotope Reactor (HFIR) at the coolant temperature (approx. 50/sup 0/C). A displacement damage level of 5.2 dpa was reached for the EP-838 and up to 9.5 dpa for the type 316 stainless steel. Tensile tests at room temperature and 300/sup 0/C on the two steels indicated that the irradiation led to increased strength and decreased ductility compared to the unirradiated steels.more » Although the 0.2% yield stress of the type 316 stainless steel in the unirradiated condition was greater than that for the EP-838, after irradiation there was essentially no difference between the strength or ductility of the two steels. The results indicate that the replacement of the majority of the nickel by manganese and a reduction of chromium and molybdenum in an austenitic stainless steel of composition near that for type 316 stainless steel has little effect on the irradiated and unirradiated tensile properties at low temperatures.« less
  • Transition weld joints between ferritic steels and austenitic stainless steels are required for fossil-fired power plants and proposed nuclear plants. The experience with these dissimilar-metal transition joints has been generally satisfactory, but an increasing number of failures of these joints is occurring prematurely in service. These concerns with transition joint service history prompted a program to develop more reliable joints for application in proposed nuclear power plants.