THE THERMAL-HYDRAULICS BEHAVIOR ANALYSIS BEFORE THE CANDU FUEL CHANNEL DRY-OUT

摘要：

The CANDU 6 nuclear power plant is modeled with SCDAP/RELAP5 code including the heat transport system (HTS), pressure and inventory control system, calandria vessel (CV) and main steam lines, etc. Through simulation of station blackout (SBO), the results obtained before the fuel channel dry-out are illustrated. Before the steam generators (SGs) dry out, the core decay heat could be removed through the SG secondary side, and fuel temperature, pressure of the HTS could keep low. The loss of the HTS inventory results in the fuel channel dry-out, heat-up of the fuel, the calandria and pressure tubes. The moderator temperature remains low in the whole process.

作者: Jingtian Yuan Lili Tong Xuewu Cao

作者单位: School of Mechanical Engineering Shanghai Jiao Tong University Dongchuan Road 800,Shanghai 200240, C School of Mechanical Engineering Shanghai Jiao Tong University Dongchuan Road 800, Shanghai 200240,

会议类型: 国际会议

会议名称: 18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)

会议地点: 西安

会议语种:英文

页码: 1-6

在线出版日期: 2010-05-17（万方平台首次上网日期，不代表论文的发表时间）