Reactor Materials Program -- weldment component toughness of SRS PWS piping materials. Task number: 89-023-1

Technical Report · Mon Feb 01 00:00:00 EST 1993

DOI:https://doi.org/10.2172/10169736· OSTI ID:10169736

Sindelar, R L

The mechanical properties of austenitic stainless steel materials from the reactor systems in the unirradiated (baseline) and the irradiated conditions have been developed previously for structural and fracture analyses of the pressure boundary of the SRS reactor Process Water System (PWS) components. Individual mechanical specimen test results were compiled into three separate weldment components or regions, namely, the base, weld, and weld heat-affected-zone (HAZ), for two orientations (L-C and C-L) with respect to the pipe axis of the source materials and for two test temperatures of 25 and 125{degrees}C. Twelve separate categories were thus defined to assess the effect of test conditions on the mechanical properties and to facilitate selection of properties for structural and fracture analyses. The testing results show high fracture toughness of the materials and support the demonstration of PWS pressure boundary structural integrity under all conditions of reactor operation. The fracture toughness of a fourth weldment component, namely, the weld fusion line region, has been measured to evaluate the potential for a region of low toughness in the interface between the Type 308 stainless steel weld metal and the Type 304 stainless steel pipe. The testing details and results of the weld fusion line toughness are contained in this report.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10169736
• Report Number(s): WSRC-TR-93-007; ON: DE93017275; TRN: 93:016706
• Resource Relation: Other Information: PBD: Feb 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
STAINLESS STEEL-304
FRACTURE PROPERTIES
REACTOR COOLING SYSTEMS
WELDED JOINTS
SAVANNAH RIVER PLANT
EXPERIMENTAL DATA
TENSILE PROPERTIES
YIELD STRENGTH
ELONGATION
DEFORMATION
MICROSTRUCTURE
PIPES
220600
360103
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
MECHANICAL PROPERTIES