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Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments

Abstract

Fatigue strain-life tests were conducted on ASMESA 106-B piping steel base metal and weld metal specimens in 288{sup 0}C (550{sup 0}F) pressurized water reactor (PWR) environments as a function of strain amplitude, strain ratio, notch acuity, and cyclic frequency. Notched base metal specimens tested at 0.017 Hz in 0.001 part per million (ppm) dissolved oxygen environments nearly completely used up the margins of safety of 2 on stress and 20 on cycles incorporated into the ASMA Section III design curve for carbon steels. Tests conducted with smooth base metal and weld metal specimens at 1.0 Hz showed virtually no degradation in cycles to failure when compared to 288{sup 0}C air test results. In all cases, however, the effect of temperature alone reduced the margin of safety offered by the design curve in the low cycle regime for the test specimens. Comparison between the fatigue life results of smooth and notched specimens suggests that fatigue crack initiation is not significantly affected by 0.001 ppm dissolved oxygen, and that most of the observed degradation may be attributed to crack growth acceleration. These results suggest that the ASMA Section III methodology should be reviewed, taking into account the PWR environment variables which degrade  More>>
Authors:
Terrell, J B [1] 
  1. Materials Engineering Associates, Inc., Lanham, MD (USA)
Publication Date:
Jan 01, 1989
Product Type:
Journal Article
Reference Number:
AIX-21-039346; EDB-90-067802
Resource Relation:
Journal Name: International Journal of Pressure Vessels and Piping; (UK); Journal Volume: 39:5
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CARBON STEELS; FATIGUE; PWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS; CRACK PROPAGATION; LIFETIME; MECHANICAL TESTS; PIPES; STRAINS; ALLOYS; COOLING SYSTEMS; ENERGY SYSTEMS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS; 360103* - Metals & Alloys- Mechanical Properties; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
7035533
Country of Origin:
United Kingdom
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 0308-0161; CODEN: PRVPA; Other: CNN: NRC-04-84-102
Submitting Site:
GBN
Size:
Pages: 345-374
Announcement Date:
May 15, 1990

Citation Formats

Terrell, J B. Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments. United Kingdom: N. p., 1989. Web. doi:10.1016/0308-0161(89)90107-5.
Terrell, J B. Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments. United Kingdom. https://doi.org/10.1016/0308-0161(89)90107-5
Terrell, J B. 1989. "Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments." United Kingdom. https://doi.org/10.1016/0308-0161(89)90107-5.
@misc{etde_7035533,
title = {Fatigue life response of ASME SA 106-B steel in pressurized water reactor environments}
author = {Terrell, J B}
abstractNote = {Fatigue strain-life tests were conducted on ASMESA 106-B piping steel base metal and weld metal specimens in 288{sup 0}C (550{sup 0}F) pressurized water reactor (PWR) environments as a function of strain amplitude, strain ratio, notch acuity, and cyclic frequency. Notched base metal specimens tested at 0.017 Hz in 0.001 part per million (ppm) dissolved oxygen environments nearly completely used up the margins of safety of 2 on stress and 20 on cycles incorporated into the ASMA Section III design curve for carbon steels. Tests conducted with smooth base metal and weld metal specimens at 1.0 Hz showed virtually no degradation in cycles to failure when compared to 288{sup 0}C air test results. In all cases, however, the effect of temperature alone reduced the margin of safety offered by the design curve in the low cycle regime for the test specimens. Comparison between the fatigue life results of smooth and notched specimens suggests that fatigue crack initiation is not significantly affected by 0.001 ppm dissolved oxygen, and that most of the observed degradation may be attributed to crack growth acceleration. These results suggest that the ASMA Section III methodology should be reviewed, taking into account the PWR environment variables which degrade the fatigue life of pressure-retaining components. (author).}
doi = {10.1016/0308-0161(89)90107-5}
journal = []
volume = {39:5}
journal type = {AC}
place = {United Kingdom}
year = {1989}
month = {Jan}
}