Extrapolation of the J-R curve for predicting reactor vessel integrity
- Tennessee Univ., Knoxville, TN (United States)
the work in this report was conducted in support of the issues studied by the US Nuclear Regulatory Commission (NRC) J{sub D}/J{sub M} Workers Group during the period 1987--1989. The major issues studies were the J-R curve extrapolation techniques for using small-specimen test results to predict ductile instability in larger structures where the extent of crack extension from the small-specimen test was not sufficient. This included the choice of parameter in characterizing the J-R curve, deformation J, or modified J, J{sub M}. These issues are studied both by comparing small- and large-specimen J-R curves and by using J-R curves from smaller specimens to predict the behavior of larger specimens and pressure vessel models. An additional issue was raised during the course of this work by the testing a low-upper-shelf A 302 shelf. The results from these tests were not typical of ductile fracture in many steel and suggested that small-specimen J-R curves may not predict the behavior of large structures in some cases. The causes of this behavior were studies as well as the consequences of using the J-R curve results from small specimens of this kind of material. Finally, a discussion and recommendations are given relating to the use of extrapolated J-R curves.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab., TN (United States); Tennessee Univ., Knoxville, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10121770
- Report Number(s):
- NUREG/CR-5650; ORNL/Sub-89-99732/1; ON: TI92003229
- Resource Relation:
- Other Information: PBD: Jan 1992
- Country of Publication:
- United States
- Language:
- English
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