上圖為車諾比核電廠的沸水式反應器（RBMK）示意圖，這是一種錯誤的設計，因為有「正空泡係數」，亦即當冷卻水減少時核子的連鎖反應及輸出功率都會上升（感謝美國能源部國際核能安全中心提供此圖）。 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.)
本課程包含核能電廠系統的結構元件，元件的功能、操作條件及機械結構的設計要求。課程中將力學技術與材料行為的模型結合來確定元件設計的正確性。其中考慮到機械負載、脆性斷裂、彈性行為、上升的溫度、中子照射及地震效應。 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.
