Simulation of the loosening of 316 steel screw inside a pressurized water reactor vessel

Guillaume Zumpicchiat,Benoit Tanguy, S. Carassou, J. Vidal

7TH INTERNATIONAL CONFERENCE INTEGRITY-RELIABILITY-FAILURE (IRF2020)（2020）

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摘要

Simple structural computations are performed to simulate the fall of the release torque of the screwed assembly of the PWR core internals. The in-reactor mechanical behavior of the 316 stainless steel is identified from several experiments in and out of neutron flux. The numerical results are compared with EDF operating data.

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关键词

stainless steel, 316, plasticity, viscoplasticity, creep, relaxation, swelling, irradiation, screw, PWR core internals

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