資源描述:
《核電廠事故分析》由會員上傳分享,免費(fèi)在線閱讀,更多相關(guān)內(nèi)容在行業(yè)資料-天天文庫。
1、核電廠事故分析研究生試用講義俞爾俊,俞冀陽編著清華大學(xué)工程物理系2008目錄第一章緒論.......................................................................................................51.1核電工業(yè)概況......................................................................................51.2核電廠安全性的特征.
2、.........................................................................61.2.1潛在的危險性............................................................................61.2.2心理因素...................................................................................81
3、.2.3事故會造成巨大的損失...........................................................91.3核電廠安全的總目標(biāo)..........................................................................91.4核電廠有關(guān)安全的基本設(shè)計思想....................................................10第二章事故分析的基本知識............
4、.............................................................132.1定義.....................................................................................................132.1.1壓水堆典型的運(yùn)行工況.........................................................132.1.2安全功能..
5、................................................................................132.2單一故障準(zhǔn)則....................................................................................162.3核電廠運(yùn)行工況的分類..................................................................
6、..202.4驗收準(zhǔn)則............................................................................................212.4.1通用的驗收準(zhǔn)則......................................................................212.4.2具體的驗收準(zhǔn)則.......................................................
7、...............222.5事故分析的基本假設(shè)........................................................................222.5.1初始條件及各項參數(shù)..............................................................232.5.2四項基本假設(shè)................................................................
8、.........232.6壓水堆核電廠設(shè)計基準(zhǔn)事故............................................................242.7核電廠事故分析的計算機(jī)程序........................................................26第三章失流事故.......................................