Fatigue Crack Growth of A508 Steel in High-Temperature, Pressurized Reactor-Grade Water,
Abstract
Fatigue crack growth tests of A508-2 pressure vessel steel have been conducted at two test temperatures (93 degrees C and 288 degrees C) using a variety of constant amplitude waveforms. The load ratios were either 0.1 or 0.125, and the water chemistry was carefully monitored and controlled so as to simulate the nominal pressurized water reactor chemistry. The test procedures are described, and an examination of all the data indicates that the results fall into one of two rather clearly defined categories. One band of data, termed 'low', lies close to or essentially on, the ASME Section XI Code air environment default line. The other band of data, termed 'high', resides approximately midway between the ASME Sec. XI air and water environment default lines. The two bands of data are the result of certain combinations of the waveform and temperature variables listed above, and are determined by the following rules: (1) a ramp time in excess of one second is needed to obtain the high crack growth rate; and (2) the application of a hold time, together with a high temperature, serves to depress a normally high crack growth rate test (i.e. one with a long ramp time) and force it into the low category. A hydrogen embrittlement model is used as a basis for the explanation of this behavior. During the longer ramp times (approximately one second) hydrogen, formed by aqueous hydrolysis, diffuses into the plastic zone, resulting in local embrittlement.
Document Details
- Document Type
- Technical Report
- Publication Date
- Sep 28, 1979
- Accession Number
- ADA075506
Entities
People
- Frank J. Loss
- Henry E. Watson
- K. J. Torronen
- V. Provenzano
- W. H. Cullen Jr.
Organizations
- United States Naval Research Laboratory