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Title: Techniques for Testing 304L Stainless Steel over a Wide Range of Temperatures.

Abstract

Abstract not provided.

Authors:
; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-CA), Livermore, CA (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1137265
Report Number(s):
SAND2007-1910C
523753
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the 2007 SEM Annual Conferenceq held June 4-6, 2007 in Springfield, MA.
Country of Publication:
United States
Language:
English

Citation Formats

Antoun, Bonnie R., Korellis, John S., and Song, Bo. Techniques for Testing 304L Stainless Steel over a Wide Range of Temperatures.. United States: N. p., 2007. Web.
Antoun, Bonnie R., Korellis, John S., & Song, Bo. Techniques for Testing 304L Stainless Steel over a Wide Range of Temperatures.. United States.
Antoun, Bonnie R., Korellis, John S., and Song, Bo. Thu . "Techniques for Testing 304L Stainless Steel over a Wide Range of Temperatures.". United States. doi:. https://www.osti.gov/servlets/purl/1137265.
@article{osti_1137265,
title = {Techniques for Testing 304L Stainless Steel over a Wide Range of Temperatures.},
author = {Antoun, Bonnie R. and Korellis, John S. and Song, Bo},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 2007},
month = {Thu Mar 01 00:00:00 EST 2007}
}

Conference:
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  • New tanks for storage of low level radioactive wastes will be constructed at the Savannah River Site (SRS) of AISI Type 304L stainless steel (304L). The presence of chlorides and fluorides in the wastes may induce Stress Corrosion Cracking (SCC) in 304L. Constant Extension Rate Tests (CERT) were performed to determine the susceptibility of 304L to SCC in simulated wastes. In five of the six tests conducted thus far 304L was not susceptible to SCC in the simulated waste environments. Conflicting results were obtained in the final test and will be resolved by further tests. For comparison purposes the CERTmore » tests were also performed with A537 carbon steel, a material similar to that utilized for the existing nuclear waste storage tanks at SRS.« less
  • Hopkinson split-bar tests were performed on Type 21-6-9 austenitic stainless steel from ambient temperature to 1023 K. These high-strain-rate tests (10/sup 2/ to 10/sup 4/ s/sup -1/) were compared with lower-strain-rate tests (10/sup -4/ s/sup -1/). The results indicate that over this temperature range, the strain-rate sensitivity of 21-6-9 is not strongly dependent on the strain rate. This suggests that the mechanism(s) of plastic flow at the higher rates is similar to that at the lower rates. This contention was corroborated by transmission electron microscopy.
  • Abstract not provided.
  • In an effort to better characterize and classify austenitic stainless steel resistance upset welds, standard methods have been examined and alternative methods investigated. Optical microscopy yields subjective classification due to deformation obscured bond lines and individual perception. The use of specimen preparations that better reveal grain boundaries aids in substantiating optical information. Electron microscopy techniques produce quantitative information in relation to microstructural constituents. Orientation Imaging Microscopy (OIM) is a relatively new technique for obtaining objective, quantitative information pertaining to weld integrity, i.e., percent grain boundary growth across the interface.
  • Type 304L stainless steel (SS) is the nuclear waste package reference material by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. The stress-corrosion cracking (SCC) resistance of this material to elevated-temperature tuff groundwater environments was determined under irradiated and unirradiated conditions. The material was found to be susceptible to SCC (in both the solution-annealed and solution-annealed-and-sensitized conditions) when exposed to an irradiated (3 x 10{sup 5} rad/h) air/water vapor/crushed tuff rock environment at 90{sup 0}C. A similar exposure at 50{sup 0}C did not result in failure after a 25-month test duration. Specimens of sensitized Type 304 SS failed in bothmore » the 90{sup 0}C and 50{sup 0}C environments. U-bend specimens of Type 304L SS conditioned with a variety of sensitization heat treatments resisted failure during a test of 1-year duration in which an environment of tuff rock and groundwater held at 200{sup 0}C was allowed to boil to dryness on a cyclical (weekly) basis. All specimens of sensitized Type 304 SS exposed to this environment failed. Slow-strain-rate studies were performed on 304L, 304, and 316L SS specimens. The Type 304L steel was tested in J-13 well water at 150{sup 0}C; the Type 316L steel at 95{sup 0}C. Neither material showed evidence of SCC in these tests. Sensitized Type 304 SS, on the other hand, did exhibit SCC in J-13 well water in tests conducted at 150{sup 0}C.« less