Silu Zheng , Haolin Yu , Xiatao Tang , Jiahe Zhou , Chuanyang Lu , Yuebing Li , Yanming He , Zengliang Gao
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引用次数: 0
Abstract
The in-vessel retention (IVR) strategy, designed to maintain the structural integrity of reactor pressure vessels (RPVs) during severe nuclear accidents, will induce a huge temperature gradient across the RPV wall. This temperature gradient may lead to an austenitic phase transformation within RPV materials. Due to the dual-phase microstructure caused by this phase transformation, predicting high-temperature mechanical properties, e.g. tensile strength, becomes challenging, thereby impeding the implementation of IVR for RPVs. In this work, crystal plasticity finite element method (CPFEM) coupled with austenite transformation kinetics (ATK) was employed to model the tensile behaviors of SA508 Gr.3 steel, a typical RPV material, at three stages: 1) before phase transformation with ferrite phase (700–973 K), 2) during phase transformation with dual phases (973–1073 K) and 3) after phase transformation with austenite phase (1073–1273 K). The results demonstrate that stress concentrations primarily occur at a deflection of 140–150° between the normal direction of slip plane and loading direction in both ferrite and austenite grains, consistent with Schmid’s law. In materials undergoing phase transformation, the locations of stress-concentrated grains and their stress distributions are influenced by: 1) deflection angle, 2) grain type, and 3) misorientation angles between neighboring grains. The tensile behaviors during phase transformation with dual phases are predicted using this CPFEM-ATK method. These findings will provide comprehensive insights into the high-temperature tensile behaviors of RPV materials in IVR conditions.
期刊介绍:
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.