上图为车诺比核电厂的沸水式反应器（RBMK）示意图，这是一种错误的设计，因为有“正空泡系数”，亦即当冷却水减少时核子的连锁反应及输出功率都会上升（感谢美国能源部国际核能安全中心提供此图）。 The RBMK reactor design pictured above was used at the Chernobyl nuclear power plant. This severly flawed design has a "positive void coefficient", meaning the nuclear chain reaction and power output increases when cooling water is lost. (Image courtesy of U.S. Dept. of Energy's International Nuclear Safety Center.)
本课程包含核能电厂系统的结构元件，元件的功能、操作条件及机械结构的设计要求。课程中将力学技术与材料行为的模型结合来确定元件设计的正确性。其中考虑到机械负载、脆性断裂、弹性行为、上升的温度、中子照射及地震效应。 This course deals with structural components in nuclear power plant systems, their functional purposes, operating conditions, and mechanical-structural design requirements. It combines mechanics techniques with models of material behavior to determine adequacy of component design. Considerations include mechanical loading, brittle fracture, in-elastic behavior, elevated temperatures, neutron irradiation, and seismic effects.
