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Title: On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.

Abstract

Laser Engineered Net Shaping (LENS) is being evaluated for use as a metal component repair/modification process for the NWC. An aspect of the evaluation is to better understand the characteristics of the interface between LENS deposited material and the substrate on which it is deposited. A processing and metallurgical evaluation was made on LENS processed material fabricated for component qualification tests. A process parameter evaluation was used to determine optimum build parameters and these parameters were used in the fabrication of tensile test specimens to study the characteristics of the interface between LENS deposited material and several types of substrates. Analyses of the interface included mechanical properties, microstructure, and metallurgical integrity. Test samples were determined for a variety of geometric configurations associated with interfaces between LENS deposited material and both wrought base material and previously deposited LENS material. Thirteen different interface configurations were fabricated for evaluation representing a spectrum of deposition conditions from complete part build, to hybrid substrate-LENS builds, to repair builds for damaged or re-designed housings. Good mechanical properties and full density were observed for all configurations. When tested to failure, fracture occurred by ductile microvoid coalescence. The repair and hybrid interfaces showed the same metallurgical integrity as,more » and had properties similar to, monolithic LENS deposits.« less

Authors:
; ; ; ;
Publication Date:
Research Org.:
Sandia National Laboratories
Sponsoring Org.:
USDOE
OSTI Identifier:
919107
Report Number(s):
SAND2004-4035
TRN: US200825%%184
DOE Contract Number:
AC04-94AL85000
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; COALESCENCE; DEPOSITION; EVALUATION; FABRICATION; FRACTURES; GEOMETRY; LASERS; MECHANICAL PROPERTIES; MICROSTRUCTURE; PROCESSING; REPAIR; STAINLESS STEEL-304L; SUBSTRATES; Machine design.; LASER APPLICATIONS; Manufactured Materials.; Steel, Stainless.

Citation Formats

Smugeresky, John E., Harris, Marc F., Griffith, Michelle Lynn, Gill, David Dennis, and Robino, Charles Victor. On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.. United States: N. p., 2004. Web. doi:10.2172/919107.
Smugeresky, John E., Harris, Marc F., Griffith, Michelle Lynn, Gill, David Dennis, & Robino, Charles Victor. On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.. United States. doi:10.2172/919107.
Smugeresky, John E., Harris, Marc F., Griffith, Michelle Lynn, Gill, David Dennis, and Robino, Charles Victor. Wed . "On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.". United States. doi:10.2172/919107. https://www.osti.gov/servlets/purl/919107.
@article{osti_919107,
title = {On the interface between LENS deposited stainless steel 304L repair geometry and cast or machined components.},
author = {Smugeresky, John E. and Harris, Marc F. and Griffith, Michelle Lynn and Gill, David Dennis and Robino, Charles Victor},
abstractNote = {Laser Engineered Net Shaping (LENS) is being evaluated for use as a metal component repair/modification process for the NWC. An aspect of the evaluation is to better understand the characteristics of the interface between LENS deposited material and the substrate on which it is deposited. A processing and metallurgical evaluation was made on LENS processed material fabricated for component qualification tests. A process parameter evaluation was used to determine optimum build parameters and these parameters were used in the fabrication of tensile test specimens to study the characteristics of the interface between LENS deposited material and several types of substrates. Analyses of the interface included mechanical properties, microstructure, and metallurgical integrity. Test samples were determined for a variety of geometric configurations associated with interfaces between LENS deposited material and both wrought base material and previously deposited LENS material. Thirteen different interface configurations were fabricated for evaluation representing a spectrum of deposition conditions from complete part build, to hybrid substrate-LENS builds, to repair builds for damaged or re-designed housings. Good mechanical properties and full density were observed for all configurations. When tested to failure, fracture occurred by ductile microvoid coalescence. The repair and hybrid interfaces showed the same metallurgical integrity as, and had properties similar to, monolithic LENS deposits.},
doi = {10.2172/919107},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Dec 01 00:00:00 EST 2004},
month = {Wed Dec 01 00:00:00 EST 2004}
}

Technical Report:

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  • No abstract prepared.
  • The vessels (reactor tanks) of the Savannah River Site nuclear production reactors constructed in the 1950's are comprised of Type 304 stainless steel with Type 308 stainless steel weld filler. Irradiation exposure to the reactor tank sidewalls through reactor operation has caused a change in the mechanical properties of these materials. A database of as-irradiated mechanical properties for site-specific materials and irradiation conditions has been produced for reactor tank structural analyses and to quantify the effects of radiation-induced materials degradation for evaluating reactor service life. The data has been collected from the SRL Reactor Materials Program (RMP) irradiations and testingmore » of archival stainless steel weldment components and from previous SRL programs to measure properties of irradiated reactor Thermal Shield weldments and reactor tank (R-tank) sidewall material. Irradiation programs of the RMP are designed to quantify mechanical properties at tank operating temperatures following irradiation to present and future tank wall maximum exposure conditions. The exposure conditions are characterized in terms of fast neutron fluence (E{sub n} > 0.1 MeV) and displacements per atom (dpa){sup 3}. Tensile properties, Charpy-V notch toughness, and elastic-plastic fracture toughness were measured for base, weld, and weld heat-affected zone (HAZ) weldment components from archival piping specimens following a Screening Irradiation in the University of Buffalo Reactor (UBR) and following a Full-Term Irradiation in the High Flux Isotope Reactor (HFIR).« less
  • The vessels (reactor tanks) of the Savannah River Site nuclear production reactors constructed in the 1950`s are comprised of Type 304 stainless steel with Type 308 stainless steel weld filler. Irradiation exposure to the reactor tank sidewalls through reactor operation has caused a change in the mechanical properties of these materials. A database of as-irradiated mechanical properties for site-specific materials and irradiation conditions has been produced for reactor tank structural analyses and to quantify the effects of radiation-induced materials degradation for evaluating reactor service life. The data has been collected from the SRL Reactor Materials Program (RMP) irradiations and testingmore » of archival stainless steel weldment components and from previous SRL programs to measure properties of irradiated reactor Thermal Shield weldments and reactor tank (R-tank) sidewall material. Irradiation programs of the RMP are designed to quantify mechanical properties at tank operating temperatures following irradiation to present and future tank wall maximum exposure conditions. The exposure conditions are characterized in terms of fast neutron fluence (E{sub n} > 0.1 MeV) and displacements per atom (dpa){sup 3}. Tensile properties, Charpy-V notch toughness, and elastic-plastic fracture toughness were measured for base, weld, and weld heat-affected zone (HAZ) weldment components from archival piping specimens following a Screening Irradiation in the University of Buffalo Reactor (UBR) and following a Full-Term Irradiation in the High Flux Isotope Reactor (HFIR).« less
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  • This report addresses the state of knowledge in flaw detection within cast stainless steel and the mechanics of the long-term aging processes. The programs, both domestic and foreign, which address these issues have been reviewed. The available information concerning flaws in both static and centrifugally cast materials has been examined. Problems in nuclear power plants employing both statically and centrifugally cast stainless steel have not manifested themselves, thereby, suggesting high reliability. To date, from a review of operating experience, centrifugally cast stainless piping has displayed no problems. The only indication of likely flaws and their detectability has come from staticallymore » cast pump bodies. From this base, the likely nature of flaws in centrifugally cast piping has been postulated and the likelihood of growth and achievement of critical dimensions examined. It is concluded that the flaw evaluation procedures of the ASME Code can be extended to the cast piping products on the basis that weldments are of initially lower fracture toughness than the pipe. Based on the outcome of current thermal aging programs, the point in plant life at which the pipe dominates flaw evaluation procedures will be better determined. Fatigue crack growth considerations suggest that large flaws can be present in pipe welds or fully-aged base pipe, while maintaining adequate safety margins.« less