Published March 1995 | Version v1
Report Open

Effects of material and loading variables on fatigue life of carbon and low-alloy steels in LWR environments

Creators

Description

The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Section III of the Code specifies fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitly addressed by the design curves, test data suggest that the Code fatigue curves may not always be adequate in coolant environments. This paper reports the results of recent fatigue tests that examine the effects of steel type, strain rate, dissolved oxygen level, strain range, loading waveform, and surface morphology on the fatigue life of A106-Gr B carbon steel and A533-Gr B low-alloy steel in water

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95014152; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
13 p.
Report number
ANL--ET/CP-84320

Conference

Title
13. international conference on structural mechanics in reactor technology.
Dates
13-18 Aug 1995.
Place
Porto Alegre (Brazil).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27008521
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CARBON STEELS; DYNAMIC LOADS; FATIGUE; FERRITIC STEELS; MATERIALS TESTING; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; STRAIN RATE; STRAINS; TENSILE PROPERTIES
Descriptors DEC
ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; STEELS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract W-31-109-ENG-38
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-950804--4.