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Title: BOUNDING SURFACE FLAW CONFIGURATION SUSCEPTIBLE TO STRESS CORROSION CRACKING UNDER WELDING RESIDUAL STRESS IN A MULTIPLE-PURPOSE CANISTER

Authors:
; ; ;
Publication Date:
Research Org.:
SRS
Sponsoring Org.:
USDOE
OSTI Identifier:
1374405
Report Number(s):
SRNL-STI-2017-00224
DOE Contract Number:
DE-AC09-08SR22470
Resource Type:
Conference
Resource Relation:
Conference: ASME 2017 Pressure Vessels and Piping Conference
Country of Publication:
United States
Language:
English

Citation Formats

Lam, P., Sindelar, R., Duncan, A., and Carter, J. BOUNDING SURFACE FLAW CONFIGURATION SUSCEPTIBLE TO STRESS CORROSION CRACKING UNDER WELDING RESIDUAL STRESS IN A MULTIPLE-PURPOSE CANISTER. United States: N. p., 2017. Web.
Lam, P., Sindelar, R., Duncan, A., & Carter, J. BOUNDING SURFACE FLAW CONFIGURATION SUSCEPTIBLE TO STRESS CORROSION CRACKING UNDER WELDING RESIDUAL STRESS IN A MULTIPLE-PURPOSE CANISTER. United States.
Lam, P., Sindelar, R., Duncan, A., and Carter, J. Fri . "BOUNDING SURFACE FLAW CONFIGURATION SUSCEPTIBLE TO STRESS CORROSION CRACKING UNDER WELDING RESIDUAL STRESS IN A MULTIPLE-PURPOSE CANISTER". United States. doi:. https://www.osti.gov/servlets/purl/1374405.
@article{osti_1374405,
title = {BOUNDING SURFACE FLAW CONFIGURATION SUSCEPTIBLE TO STRESS CORROSION CRACKING UNDER WELDING RESIDUAL STRESS IN A MULTIPLE-PURPOSE CANISTER},
author = {Lam, P. and Sindelar, R. and Duncan, A. and Carter, J.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Apr 21 00:00:00 EDT 2017},
month = {Fri Apr 21 00:00:00 EDT 2017}
}

Conference:
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  • A typical multipurpose canister (MPC) is made of austenitic stainless steel and is loaded with spent nuclear fuel assemblies. Because heat treatment for stress relief is not required for the construction of the MPC, the canister is susceptible to stress corrosion cracking in the weld or heat affected zone regions under long-term storage conditions. Logic for flaw acceptance is developed should crack-like flaws be detected by Inservice Inspection. The procedure recommended by API 579-1/ASME FFS-1, Fitness-for-Service, is used to calculate the instability crack length or depth by failure assessment diagram. It is demonstrated that the welding residual stress has amore » strong influence on the results.« less
  • At a number of locations in the U.S., spent nuclear fuel (SNF) is maintained at independent spent fuel storage installations (ISFSIs). These ISFSIs, which include operating and decommissioned reactor sites, Department of Energy facilities in Idaho, and others, are licensed by the U.S. Nuclear Regulatory Commission (NRC) under Title 10 of the Code of Federal Regulations, Part 72. The SNF is stored in dry cask storage systems, which most commonly consist of a welded austenitic stainless steel canister within a larger concrete vault or overpack vented to the external atmosphere to allow airflow for cooling. Some ISFSIs are located inmore » marine environments where there may be high concentrations of airborne chloride salts. If salts were to deposit on the canisters via the external vents, a chloride-rich brine could form by deliquescence. Austenitic stainless steels are susceptible to chloride-induced stress corrosion cracking (SCC), particularly in the presence of residual tensile stresses from welding or other fabrication processes. SCC could allow helium to leak out of a canister if the wall is breached or otherwise compromise its structural integrity. There is currently limited understanding of the conditions that will affect the SCC susceptibility of austenitic stainless steel exposed to marine salts. NRC previously conducted a scoping study of this phenomenon, reported in NUREG/CR-7030 in 2010. Given apparent conservatisms and limitations in this study, NRC has sponsored a follow-on research program to more systematically investigate various factors that may affect SCC including temperature, humidity, salt concentration, and stress level. The activities within this research program include: (1) measurement of relative humidity (RH) for deliquescence of sea salt, (2) SCC testing within the range of natural absolute humidity, (3) SCC testing at elevated temperatures, (4) SCC testing at high humidity conditions, and (5) SCC testing with various applied stresses. Results to date indicate that the deliquescence RH for sea salt is close to that of MgCl{sub 2} pure salt. SCC is observed between 35 and 80 deg. C when the ambient (RH) is close to or higher than this level, even for a low surface salt concentration. (authors)« less
  • The effect of transient heat treatment on throughwall residual stress distribution of cold worked Alloy 600 tubes has been investigated, using electrochemical machining coupled with Sachs analyses for residual stress calculations. Heating for 60 to 150 seconds at 775 to 850 C is used. Specimens are made from one highly cold worked and one lightly cold worked tube. In both cases significant reduction of the magnitude of the stress, and modification of the stress distribution are achieved as a result of the heat treatment. The percentage reduction of the magnitude of the stress caused by the same heat treatment ismore » generally greater in the lightly cold worked tube than in the highly cold worked one. The implications of the stress relieving heat treatments to mitigating stress corrosion cracking in a specific case are discussed. 14 references, 17 figures, 1 table.« less