Low cycle fatigue characteristics of irradiated type 304 stainless steel

Journal Article · Wed Sep 01 04:00:00 EDT 1982 · Nucl. Technol.; (United States)

OSTI ID:5912846

Murty, K L; Holland, J R

Tensile and low cycle fatigue characteristics of Type 304 stainless steel were determined at room temperature and 325/sup 0/C in both the unirradiated and irradiated (about 8 X 10/sup 26/ n/m/sup 2/, >0.1 MeV) conditions. The irradiated tensile specimens exhibited radiation hardening and embrittlement with a significant drop in ductility at 325/sup 0/C; however, they still behaved as ductile materials with 4 to 5% total elongation. Fatigue tests were conducted at a fixed frequency of 0.1 cps in four-point bending mode with full strain reversal, and all tests were carried out under strain control. Both the deflection and load were continously monitored, and the number of cycles to failure was determined at total axial strain ranges varying from about 1.0 to 2.4%. The number of cycles to failure varied from about 500 to 40,000. Data at both the room temperature and 325/sup 0/C indicated that irradiation improved fatigue life at strains lower than about 1.6%, whereas a slight decrease in life is noted at higher strain ranges. Correlations of the experimental data with predictions of the universal and characteristic slopes equations, based on appropriate tensile properties, are discussed. A modified equation predicting the present data was developed based on the universal slopes concept and tensile properties, such as the ultimate tensile stress, ductility, and work-hardening coefficient.

• Research Organization: North Carolina State University, Department of Nuclear Engineering, Raleigh, North Carolina 27650
• OSTI ID: 5912846
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 58:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
AMBIENT TEMPERATURE
BENDING
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
DUCTILITY
EMBRITTLEMENT
EXPERIMENTAL DATA
FAILURES
FATIGUE
HARDENING
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH TEMPERATURE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
NICKEL ALLOYS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIATION HARDENING
REACTOR MATERIALS
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRAIN RATE
TENSILE PROPERTIES
TESTING