Extrapolation of the J-R curve for predicting reactor vessel integrity
Technical Report
·
OSTI ID:5764532
- 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:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5764532
- Report Number(s):
- NUREG/CR-5650; ORNL/Sub--89-99732/1; ON: TI92003229
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
CRACKS
DIAGRAMS
EXTRAPOLATION
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOW ALLOY STEELS
MANGANESE ALLOYS
MECHANICAL PROPERTIES
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NUMERICAL SOLUTION
PRESSURE VESSELS
REACTOR VESSELS
STEEL-ASTM-A302
STEEL-ASTM-A508
STEEL-MNMO
STEELS
WELDED JOINTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CONTAINERS
CRACK PROPAGATION
CRACKS
DIAGRAMS
EXTRAPOLATION
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOW ALLOY STEELS
MANGANESE ALLOYS
MECHANICAL PROPERTIES
MOLYBDENUM ADDITIONS
MOLYBDENUM ALLOYS
NUMERICAL SOLUTION
PRESSURE VESSELS
REACTOR VESSELS
STEEL-ASTM-A302
STEEL-ASTM-A508
STEEL-MNMO
STEELS
WELDED JOINTS