A Comprehensive Overview of the Design Procedure, Bimodular Fracture Mechanics Analysis, and Potential Uses of Nuclear-Grade Graphite for Nuclear Applications
摘要
This study provides a comprehensive review of the design process, bimodular fracture mechanics analysis, and potential applications of nuclear-grade graphite. Nuclear-grade graphite is an essential material of nuclear reactor technology because of its remarkable neutron moderating, reflecting, thermal conductivity, and radiation resistance qualities. Its capabilities range from more modern versions like high-temperature gas-cooled reactors (HTGR) and molten salt reactors to older ones like Chicago Pile-1. Despite its advantages, problems including intrinsic brittleness, bimodular behavior, and embrittlement caused by neutron irradiation affect its fracture mechanics and structural integrity. Understanding these issues and ensuring stability over time requires the use of finite element analysis and other sophisticated predictive modeling techniques. Despite the challenges posed by graphite's porous structure, oxidation susceptibility, and radiation damage, further research and innovative design are essential. By overcoming these limitations, nuclear-grade graphite remains crucial to the sustainability, safety, and efficiency of current and future nuclear reactors.