Ductile fracture behaviour of primary heat transport piping material of nuclear reactors |
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Authors: | S Tarafder V R Ranganath S Sivaprasad P Johri |
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Affiliation: | (1) Fatigue & Fracture Group, National Metallurgical Laboratory, 831007 Jamshedpur, India |
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Abstract: | Design of primary heat transport (PHT) piping of pressurised heavy water reactors (PHWR) has to ensure implementation of leak-before-break
concepts. In order to be able to do so, the ductile fracture characteristics of PHT piping material have to be quantified.
In this paper, the fracture resistance of SA333, Grade 6 steel — the material used for Indian PHWR — under monotonic and cyclic
tearing loading has been documented. An attempt has also been made to understand the mechanism responsible for the high fracture
toughness of the steel through determination of the effect of constraint on the fracture behaviour and fractographic observations.
FromJ-R tests over a range of temperatures, it was observed that SA333 steel exhibits embrittlement tendencies in the service temperature
regime. The fracture resistance of the steel is inferior in the longitudinal direction with respect to the pipe geometry as
compared to that in the circumferential direction. Imposition of cyclic unloading during ductile fracture tests for simulation
of response to seismic activities results in a dramatic decrease of fracture resistance. It appears, from the observations
of effects of constraint on fracture toughness and fractographic examinations, that fracture resistance of the steel is derived
partly from the inability of voids to initiate and grow due to a loss of constraint in the crack-tip stress field. |
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Keywords: | SA333 steel monotonicJ-R curve cyclicJ-R curve constraint effect stretch zone |
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