skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: THE CHANGE IN THE MECHANICAL PROPERTIES OF ALLOY 718, 304L AND 316L STAINLESS STEEL AND AL6061 AFTER IRRADIATION IN A HIGH ENERGY PROTON BEAM

Abstract

No abstract prepared.

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
784680
Report Number(s):
LA-UR-99-4175
TRN: US200306%%148
DOE Contract Number:
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Conference title not supplied, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Aug 1999
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; ALLOYS; IRRADIATION; MECHANICAL PROPERTIES; PROTON BEAMS; STAINLESS STEELS

Citation Formats

S. A. MALOY, M. R. JAMES, and ET AL. THE CHANGE IN THE MECHANICAL PROPERTIES OF ALLOY 718, 304L AND 316L STAINLESS STEEL AND AL6061 AFTER IRRADIATION IN A HIGH ENERGY PROTON BEAM. United States: N. p., 1999. Web.
S. A. MALOY, M. R. JAMES, & ET AL. THE CHANGE IN THE MECHANICAL PROPERTIES OF ALLOY 718, 304L AND 316L STAINLESS STEEL AND AL6061 AFTER IRRADIATION IN A HIGH ENERGY PROTON BEAM. United States.
S. A. MALOY, M. R. JAMES, and ET AL. 1999. "THE CHANGE IN THE MECHANICAL PROPERTIES OF ALLOY 718, 304L AND 316L STAINLESS STEEL AND AL6061 AFTER IRRADIATION IN A HIGH ENERGY PROTON BEAM". United States. doi:. https://www.osti.gov/servlets/purl/784680.
@article{osti_784680,
title = {THE CHANGE IN THE MECHANICAL PROPERTIES OF ALLOY 718, 304L AND 316L STAINLESS STEEL AND AL6061 AFTER IRRADIATION IN A HIGH ENERGY PROTON BEAM},
author = {S. A. MALOY and M. R. JAMES and ET AL},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1999,
month = 8
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:
  • This paper describes the fracture toughness characterization of annealed 304L and 316L stainless steels and precipitation hardened Alloy 718, performed at the Oak Ridge National Laboratory as a part of the experimental design and development for the Accelerator Production of Tritium (APT) target/blanket system. Materials were irradiated at 25 to 200 C by high-energy protons and neutrons from an 800-MeV, 1-mA proton beam at the Los Alamos Neutron Science Center (LANSCE). The proton flux produced in LANSCE is nearly prototypic of anticipated conditions for significant portions of the APT target/blanket system. The objective of this testing program was to determinemore » the change in crack-extension resistance of candidate APT materials from irradiation at prototypic APT temperatures and proton and neutron fluxes. J-integral-resistance (J-R) curve toughness tests were conducted in general accordance with the American Society for Testing and Materials Standard Test Method for Measurement of Fracture Toughness, E 1820-99, with a computer-controlled test and data acquisition system. J-R curves were obtained from subsize disk-shaped compact tension specimens (12.5 mm in diameter) with thicknesses of 4 mm or 2 mm. Irradiation up to 12 dpa significantly reduced the fracture toughness of these materials. Alloy 718 had the lowest fracture toughness in both the unirradiated and irradiated conditions. All irradiated specimens of Alloy 718 failed by sudden unstable crack extension regardless of dose or test temperature. Type 304L and 316L stainless steels had a high level of fracture toughness in the unirradiated condition and exhibited reduction in fracture toughness to saturation levels of 65 to 100 MPa{radical}m. The present reduction in fracture toughness is similar to changes reported from fission reactor studies. However, the currently observed losses in toughness appear to saturate at doses slightly lower than the dose required for saturation in reactor-irradiated steels. This difference might be attributed to the increased helium and hydrogen production associated with irradiation in the high-energy, mixed proton/neutron spectrum.« less
  • Abstract not provided.
  • Databases of mechanical properties for both the piping and reactor vessels at the Savannah River Site (SRS) were developed from weldment components (base, weld, and weld heat-affected-zone (HAZ)) of archival piping specimens in the unirradiated and irradiated conditions. Tensile, Charpy V-notch (CVN), and Compact Tension C(T) specimens were tested at 25 and 125C before and after irradiation at low temperatures (90 to 150C) to levels of 0.065 to 2.1 dpa. irradiation hardened the weldment components and reduced the absorbed energy and toughness properties from the unirradiated values. A marked difference in the Charpy V-notch absorbed energy and the elastic-plastic fracturemore » toughness (J[sub IC]) was observed for both the base and HAZ components with the C-L orientation being lower in toughness than the L-C orientation in both the unirradiated and irradiated conditions. Fracture surface examination of the base and HAZ components of unirradiated C(T) specimens showed a channel'' morphology in the fracture surfaces of the C-L specimens, whereas equiaxed ductile rupture occurred in the L-C specimens. Chromium carbide precipitation in the HAZ component reduced the fracture toughness of the C-L and L-C specimens compared to the respective base component C-L and L-C specimens. Optical metallography of the piping materials showed stringers of second phase particles parallel to the rolling direction along with a banding or modulation in the microchemistry perpendicular to the pipe axis or rolling direction of the plate material.« less