Tension bending ratcheting tests of NiCrFe alloy 600

Book · Sun Dec 31 04:00:00 EST 1995

OSTI ID:191354

Larson, L D; Hoppe, R G; Jones, D P ^[1]

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1. Bettis Atomic Power Lab., West Mifflin, PA (United States)

This paper discusses an experimental program which was conducted to investigate the strain ratcheting behavior of Alloy 600 under various combinations of applied membrane load and displacement controlled cyclic bending strain. Tests were performed on uniaxial specimens at temperatures of 70 F (21 C) and 550 F (288 C). Bending strain, ratchet strain and axial displacement of the specimen were monitored throughout the test. Membrane stress to monotonic yield stress ratios of 2/3, 1/2, and 1/3 were tested with equivalent elastic bending stress to yield stress ratios ranging from 1.5 to 10. Test output was in the form of cumulative axial membrane strain versus cycles plots up to the point of shakedown, i.e., the point at which no additional progressive strain was observed. The results are shown in terms of shakedown membrane strain versus equivalent bending stress ratio for each of the tested membrane stress ratios. The cyclic and monotonic stress-strain curves for the test materials are presented to enable the use of various prediction models for predicting the ratcheting and shakedown behavior. This material exhibits rapid shakedown and the data demonstrate that the ASME Boiler and Pressure Vessel Code ratchet rules are conservative suggesting that the rules could be relaxed at low values of P{sub m}/S{sub Y} when some small amount of membrane straining is not objectionable.

• OSTI ID: 191354
• Report Number(s): CONF-950740--; ISBN 0-7918-1337-1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AMBIENT TEMPERATURE
EXPERIMENTAL DATA
INCONEL 600
MECHANICAL TESTS
RATCHETING
REACTOR MATERIALS
STANDARDS
TEMPERATURE RANGE 0400-1000 K
WATER COOLED REACTORS