FATIGUE CRACK GROWTH CHARACTERISTICS OF NUCLEAR PRESSURE VESSEL GRADE MATERIALS. Paper No. 1. Page: 2 of 11
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Fatigue Crack Growth Characteristics
Of Nuclear Pressure Vessel Grade Materials
T. R. Mager
Westinghouse Electric Corporation
The fatigue crack growth rate of pressure vessel grade materials is being
studied in high temperature pressurized water. Initially, ultrasonic monitoring
techniques were used to measure the crack growth in the 2T WOL specimens.
However, utilization of ultrasonic monitoring techniques required fixing the
test specimen to the test chamber head. It was concluded that because of the
constrainment of the head, the stress intensity "KIc" at the crack tip was not
well defined. As a result, the experiment was redesigned to utilize compliance
calibration to experimentally measure rates of crack propagation.
Twelve (12) 2T WOL specimens fabricated from A533, Grade B, Class 1 base plate
and weldment material were evaluated in PWR and BWR water environment. It was
concluded that the water environment did not have an effect on the fatigue crack
growth rate of the materials investigated.
Using the fracture mechanics approach, the effect of an environment of high
temperature primary reactor grade water on the fatigue crack growth character-
istics of nuclear pressure vessel grade materials is being studied. The stress
intensity concept of linear elastic fracture mechanics provides a parameter K
which describes the stress situation at the tip of an existing crack. It has
been shown that the cyclic range of the stress intensity factor, AK, is the
controlling stress parameter which determines the fatigue crack growth rate.
The crack growth rate da/dN of pressure vessel materials is being measured as
a function of AKI, the change in the stress intensity at the tip of the crack.
This report was prepared as an account of work
sponsored by the United. States Government. Neither
the United States nor the United States Atomic Energy
Commission, nor any of their employees, nor any of
their contractors, subcontractors, or their employees,
makes any warranty, express or implied, or assumes any
legal liability or responsibility for the accuracy, com-
pleteness or usefulness of any information, apparatus,
product or process disclosed, or represents that its use
would not infringe privately owned rights. U; C" rn a*! *r R 1
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Mager, T.R. FATIGUE CRACK GROWTH CHARACTERISTICS OF NUCLEAR PRESSURE VESSEL GRADE MATERIALS. Paper No. 1., report, January 1, 1971; Country unknown/Code not available. (https://digital.library.unt.edu/ark:/67531/metadc1034097/m1/2/: accessed March 19, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.